ML101520547
| ML101520547 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/04/2010 |
| From: | Widmann M Division of Reactor Safety II |
| To: | Baxter D Duke Energy Carolinas |
| References | |
| 50-269/10-301, 50-270/10-301, 50-287/10-301, ES-201-2 | |
| Download: ML101520547 (29) | |
Text
ES-201 Examination Outline Quality Checklist Form ES-201-2 Item b.
Facility Reviewer (*)
c.
NRC Chief Examiner (#)
d.
NRC Supervisor Facility:
Oconee 2010-301 Written Outline Date of Examination:
3/29/2009 a.
Task Description Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
b.
Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KJA categories are appropriately sampled.
a Initials c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
4 I.
w R
T T
d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
2.
a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major S
M b.
Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule L
without compromising exam integrity, and ensure that each applicant can be tested using at A
least one new or significantly modified scenario, that no scenarios are duplicated from the T
applicants audit test(s), and that scenarios will not be repeated on subsequent days.
c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
3.
a.
Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W
among the safety functions as specified on the form
/
(2) task repetition from the last two NRC examinations is within the limits specified on the form T
(3) no tasks are duplicated from the applicants audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
b.
Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations c.
Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
G E
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d.
Check for duplication and overlap among exam sections.
L e.
Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
Printed Name/Signature Date a.Author 1
/
,n
/
(MAlni 1f r-JIA-[)
74/2 1, LA Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Ort1'f1 ES-201 Examination Outline Quality Checklist Facility:
Oconee 2010-301 Written Outline Date of Examination:
Item
- 1.
W R
I T
T E
N
- 2.
S I
M U
L A
T o
R
- 3.
W
/
T
- 4.
G E
N E
R A
L Task Description
- a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
- b.
Assess whether the outline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all KiA categories are appropriately sampled.
- c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
- d.
Assess whether the justifications for deselected or rejected KiA statements are appropriate.
- a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.
- b.
Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
- c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
- a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed
. among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as speCified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations
- c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
- a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
- c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5.
- d. Check for duplication and overlap among exam sections.
- e. Check the entire exam for balance of coverage.
- f.
Assess whether the exam fits the appropriate job level (RO or SRO).
Printed Name/Signature
- a. Author
- c. NRC Chief Examiner (#)
.U:H£
- b. Facility Reviewer (*)
- d. NRC Supervisor Form ES-201-2 3/29/2009 Date -
5E D/t4 4iTi3 ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
OCONEE Date of Examination:
3/29/10 Initials Item Task Description
a b*
c#
1.
a.
Verify thaI the outline(s) fit(s) the appropriate model, in accordance with ES-401 w
R b.
Assess whether the outline was systematically and randomly prepared in accordance with I
Section 0.1 of ES-401 and whether all K/A categories are appropriately sampled.
T T
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
cY7 2.
a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S
and major transients.
M b.
Assess whether there are enough scenario sets (and spares) to test the projected number U
and mix of applicants in accordance with the expected crew composition and rotation schedule L
without compromising exam integrity, and ensure that each applicant can be tested using A
at least one new or significantly modified scenario, that rio scenarios are duplicated T
from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
(
3.
a.
Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
..i..
(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 T
(3) no tasks are duplicated from the applicants audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
b.
Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations c.
Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
S G
E b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5,
,q R
d.
Check for duplication and overlap among exam sections.
L e.
Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
Printed N
/ ignature Date
- a. Author
/
- b. Facility Reviewer ()
GAbriel
(
- c. NRCChiefExaminer(#)
-zqct tJ-(_4 /
d.
NRC Supervisor Note:
- Independent NRC reviewer initial items in Column c chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility OCONEE Date of Examination:
3/29/10 Item 1
W R
I T
T E
N
- 2.
S I
M U
L A
T o
R
- 3.
W I
T
- 4.
G E
N E
R A
L Task Description
- a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
- b.
Assess whether the outline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all KIA categories are appropriately sampled.
- c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
- d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.
- a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.
- b.
Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
- c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
- a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations
- c.
Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
- a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
- c.
Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.
- d. Check for duplication and overlap among exam sections.
- e.
Check the entire exam for balance of coverage.
- f.
Assess whether the exam fits the appropriate job level (RO or SRO).
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Supervisor GA~",e( lcJ~"b... ~,., / ~_[4j/y C::WA/\\b \\J.~ (
l a
Note:
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
- Not applicable for NRC-prepared examination outlines
---~- -
--~-------
~-- ----- --"---------------------------------------------------._-
Initials b*
c#
Date
\\7. - 2.~*U c:r If)..). '7..D"'\\
F ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Oconee Date of Exam: 04/07/2010 Exam Level: RO SRO Initial Item 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.
(/2 b.
Facility learning objectives are referenced as available.
1 kj 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 4.
The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).
5.
Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
the audit exam was systematically and randomly developed; or 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 Modified New from the bank, at least 10 percent new, and the rest A
new or modified); enter the actual RO / SRO-only 10 / 3 5/0 60 / 22 c//t.)
question distribution(s) at right.
I 13%/12%
7%/0%
80% /88%
7.
Between 50 and 60 percent of the questions Memory C/A on the RO exam are written at the comprehension!
analysis level; the SRO exam may exceed 60 34 / 6 41 / 19 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO /
45.3% / 24%
54.7% / 76%
SRO question distribution(s) at right.
8.
References/handouts provided do not give away answers or aid in the elimination of distractors.
9.
Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
Y
11.
The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.
Printed Name / Signature Date
- a. Author Ai.pc Q.Q
- b. Facility Reviewer (*)
43(AJ
(..Vc1LP
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor 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 Written Examination Quality Checklist Form ES-401-6 Il:::ty: Oconee Date of Exam: 04/07/2010 Exam Level: RO ~ SRO Initial Item Description a
b*
c#
- 1.
Questions and answers are technically accurate and applicable to the facility.
C(Jw ~(.~
- 2.
- a.
NRC K/As are referenced for all questions.
o.p'-v ~~vV
- b.
Facility learning objectives are referenced as available.
- 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 CPJ &1"'"
- 4.
The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).
- 5.
Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
_ the audit exam was systematically and randomly developed; or
_ 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 Modified New from the bank, at least 10 percent new, and the rest cftJ %(,uJ new or modified); enter the actual RO / SRO-only 10/3 5/0 60/22 question distribution(s) at right.
13% /12%
7%/0%
80% /88%
- 7.
Between 50 and 60 percent of the questions Memory CIA on the RO exam are written at the comprehension/
analysis level; the SRO exam may exceed 60 34 / 6 41 / 19 4uJ percent if the randomly selected KlAs support Cfv the higher cognitive levels; enter the actual RO /
45.3% / 24%
54.7% / 76%
SRO question distribution(s) at right.
- 8.
References/handouts provided do not give away answers C;V ~
or aid in the elimination of dis tractors.
- 9.
Question content conforms with specific KIA statements in the previously approved
~
~o.J examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
- 10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
~
~~
- 11.
The exam contains the required number of one-point, multiple choice items;
~
~
the total is correct and agrees with the value on the cover sheet.
P,;oted N,m, I S;9O"""~ _____
Date
- a. Author 2 *5>-\\'0
- b. Facility Reviewer (*)
~~t:rt~~+/-~_~--
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c'" chief examiner concurrence required.
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:
Date of Exam: 2
-cV RO K/A Category Points SRO-Only Points Tier Group
KKKKKKAAA1AG A2 G*
Total 1
2 3
4 5
6 1
2 Total 1.
i 3
3 i8, 3
3 6
Emergency &
2 1
1 1
2 2
2 9
2 2
4 Abnormal Plant
N/A N/A
Evolutions TierTotals 4
4 5
5 5
27 5
5 10 Systems Tier Totals 2
4 4
4 3
4 2
4 4
3 4
38 5
3 8
- 3. GenericKnowledgeandAbilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 3
2 2
2 1
2 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
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 +/- I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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 (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.
7.
- The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
- 1 does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the 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, Rev. 9 PWR Examination Outline Form ES-401-2 I~
o CtPW -c-<..
Date of Exam:
2-c7/~
RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1
'3 3
~
\\(3
\\
"3
'3 1'8, 3
3 6
Emergency &
2 1
1 1
2 2
2 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 4
4 4
5 5
5 27 5
5 10 1
1 3
3 3
2 3
2 3
3 2
3 28 3
2 5
- 2.
1 1
1 1
1 1
0 1
1 1
1 10 2
1 3
Plant 2
Systems Tier Totals 2
4 4
4 3
4 2
4 4
3 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 3
2 2
2 1
2
- 1.
Ensure that at leasttwo topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 pOints.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA 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 KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
- 7.
- The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
B.
On the following pages, enter the KIA 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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter 'it on the left side of Column A2 for Tier 2, Group 2 (Note
- 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 ofthe KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. LimitSRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
P0 SRO
,. OO8AK1.01 Pressurizer Vapor Space Accident! 3 3.2 3.7 Thermodynamics and flow characteristics of open or leak-ing valves
,/009EK1.01 Small Break L0CA / 3 4.2 4.7 Natural circulation and cooling, including reflux boiling
,0i 1 EK2.02 Large Break L0CA / 3 2.6 2.7 O15AA1.21 RCP Malfunctions! 4 4.4 4.5 Loss of RHIR System /4 4.0 4.2 Pumps Loss of Component Cooling Water! 8 3.2 3.5 025AG2.4.l 1 4 026AKl
/
,d27AK2.o3 029EK3.08
,038EK3.0l
/
Development of natural circulation flow E1 EI ElEl ElEl ElEl EJ ElEl ElEl DEl ElEl El ElElEl ElElElElEl ElElElElD ElElElEl ElElElElEl ElElElEl ElElElElEl ElElElEl ElElElEl ElElElEl ElElEEl El El El El El El El El El El El Knowledge of abnormal condition procedures.
ElElEl ElElEl ElElEl ElElEl ElEl ElElEl ElElEl ElElEl ElElEl ElElEl ElElEl Pressurizer Pressure Control System 2.6 2.8 Malfunction /3 ATWS/,1 3.6 3.8 I
C Steam Gen. Tube Rupture! 3 4.1 4.3 The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers Controllers and positioners
/
/054AAi.03 Loss of Main Feedwater! 4 3.5 3.7
.055EA1.02
/
Closing the main steam isolation valve io A5iC Station Blackout! 6 4.3 4.4 Equalizing pressure on primary and secondary sides of ruptured S!G AFW auxiliaries, including oil cooling water supply Manual ED/G start Page 1 of 2 6/22/2009 12:00 PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO AOBAK1.01 Pressurizer Vapor Space Accident 13 3.2 3.7
~ 0 0 0 0 0 0 0 0 0 0 09EK1.01 Small Break LOCA 1 3 4.2 4.7
~ 0 0 0 000
/0'11 EK2.02 Large Break LOCA 1 3 2.6 2.7 0 ~ 0 0 0 0 0 0 0 0 0 015AA1.21 RCP Malfunctions 1 4 4.4 4.5 0 oooo~ 000
/025AG2.4.11 Loss of RHR System 1 4 4.0 4.2 0 0 ooooooo~
"' /
/027AK2.03 I ;~
/
j03BEK3.01 054AA1.03
)'55EA1.02
/
Loss of Component Cooling Water 1 B 3.2 3.5 0 0 ~ 0 0 0 0 0 00 Pressurizer Pressure Control System 2.6 2.B 0 ~ 0 0 0 0 0 0 0 0 0 Malfunction 1 3 3.6 3.B o~oooooooo Steam Gen. Tube Rupture 1 3 4.1 4.3 0 0 ~ 0 0 0 0 0 0 0 0 Loss of Main Feedwater 1 4 3.5 3.7 0 0 0 0 0
~ooo Station Blackout 1 6 4.3 4.4 0 0 0 0 0 0 ~ 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC:
Thermodynamics and flow characteristics of open or leak-ing valves Natural circulation and cooling, including reflux boiling Pumps Development of natural circulation flow Knowledge of abnormal condition procedures.
The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers
~
Controllers and positioners Closing the main steam isolation valve NO
.~
Equalizing pressure on primary and secondary sides of ruptured S/G AFW auxiliaries, including oil cooling water supply Manual ED/G start 6/22/2009 12:00 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
7
/057AA2.15 Loss of Vital AC Inst. Bus /6 1
058AK1.01 Loss of DC Power/6 7
/062AG2.l.20 Loss of Nuclear Svc Water / 4 065AA2.07 Loss of Instrument Air / 8
,,d77AG2.2.22 BEO4EA2.2
/E05EK2. 1 T1G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 4.1 3.1 4.6 3.2 4.7 4.4 FORM ES-401-2 RO 3.8 2.8 4.6 2.8 4.0 3.6 3.8 Generator Voltage and Electric Grid Disturbances / 6 Inadequate Heat Transfer
- Loss of Secondary Heat Sink / 4 Steam Line Rupture
- Excessive Heat Transfer / 4 TOPIC:
That a loss of ac has occurred Battery charger equipment and instrumentation Ability to execute procedure steps.
Whether backup nitrogen supply is controlling valve position Knowledge of limiting conditions for operations and safety limits.
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Page 2 of 2 6/2212009 12:00PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
/057AA2.15 Loss of Vital AC Inst. Bus / 6 3.8 4.1 0 0 0 0 0 0 ~ 0 0 0 That a loss of ac has occurred
/58AK1.01 Loss of DC Power / 6 2.8 3.1
~DDD DDDDDn Battery charger equipment and instrumentation
/
- 662AG2.1.20 Loss of Nuclear Svc Water /4 4.6 4.6 DDDDDDDDDD~
Ability to execute procedure steps.
-/-
Loss of Instrument Air / 8 Whether backup nitrogen supply is controlling valve "l)65AA2.07 2.8 3.2 DDDDDDD~DDD position
- 077 AG2.2.22 Generator Voltage and Electric Grid 4.0 4.7 DDDDDDDDDD~
Knowledge of limiting conditions for operations and safety
(
Disturbances / 6 limits.
jBE04EA2.2 Inadequate Heat Transfer - Loss of 3.6 4.4 DDDDDDD~DDD Adherence to appropriate procedures and operation Secondary Heat Sink / 4 within the limitations in the facility s license and I
amendments.
!E05EK2.1 Steam Line Rupture - Excessive Heat 3.8 4
D~DDDDDDDDD Components, and functions of control and safety Transfer / 4 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Page 2 of 2 6/2212009 12:00 PM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Bypass of a heat detector cj_j3 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
E528AA1.07 Pressurizer Level Malfunction / 2 3.3 3.3 El Charging pumps maintenance of PZR level (including
/
manual backup)
II
,736AK2.ol Fuel Handling Accident! 8 2.9 3.5 El J Fuel handling equipment
/59AK3.03 Accidental Liquid RadWaste Rel. / 9 3
3.7 El Declaration that a radioactive-liquid monitor is inoperable I
Plant Fire On-site / 9 8 2.5 2.7 El El
/o?67AA1.04 d74EG2.1.7 lnad. Core Cooling! 4 4.4 4.7 [
El El El El El El [1
/
,A02AK1.3 Loss of NNI-X! 7 3.8 3.8 El El El El El El El El El El Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X).
%A04AA2.1 Turbine Trip! 4 3.3 3.7 El El El El El El El El El El Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
/
$AO7AA2.2 Flooding! 8 3.3 3.7 El El El El El El El El El El Adherence to appropriate procedures and operation I
within the limitations in the facility s license and
/
amendments.
/EO3EG2.2.3 Inadequate Subcooling Margin! 4 3.8 3.9 El El El El El El El El El El (multi-unit license) Knowledge of the design, procedural and operational differences between units.
Page 1 of 1 6/22/2009 12:00 PM f
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
!28AA1.07 Pressurizer Level Malfunction / 2 Fuel Handling Accident / 8
!S9AK3.03 Accidental Liquid RadWaste ReI. / 9 Plant Fire On-site / 9 8 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.3 3.3 0 0 0 0 0 0 ~ 0 0 0 0 2.9 3.S 0 ~ 0 0 0 0 0 0 0 0 0 3
3.7 0 0 ~ 0 0 0 0 0 0 0 0 2.S 2.7 FORM ES-401-2 TOPIC:
Charging pumps maintenance of PZR level (including manual backup)
Fuel handling equipment Declaration that a radioactive-liquid monitor is inoperable Bypass of a heat detector DDDDDD~DDDD j
vb:. i 1.Q3-*~,\\~I~~1 Z.>/21>
674EG2.1.7 Inad. Core Cooling / 4 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
Ability to evaluate plant performance and make 1*05" A02AK1.3 Loss of NNI-X / 7 3.8 A04AA2.1 Turbine Trip / 4 3.3 t
!A07AA2.2 Flooding / 8 3.3 L
'E03EG2.2.3 Inadequate Subcooling Margin / 4 3.8 3.8
~DDDDDDDDDD 3.7 DDDDDDD~DD 3.7 DDDDDDD~D 0 3.9 DDDDDDDDDD~
Page 1 of 1 operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X).
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
(multi-unit license) Knowledge of the design, procedural and operational differences between units.
6/2212009 12:00 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC
/
/03K4.J4 Reactor Coolant Pump 3.0 3.0 El El El El El El El El El El Isolation valve interlocks A r
.C:.
,9O3K6.04 Reactor Coolant Pump 2.8 3.1 El El El El El El El El El El Containment isolation valves affecting RCP operation
/
,p04K1.36 Chemical and Volume Control 2.6 2.8 El CCWS
Ø05K3.05 Residual Heat Removal 3.7 3.8 j
/
,,605K4.01 Residual Heat Removal 3.0 3.2 El El El El El El El El El Overpressure mitigation system
/
/606A3.05 Emergency Core Cooling 4.2 4.3 El El El El El El El El El El Safety Injection Pumps
/
/607K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 El El El El El El El El El El Method of forming a steam bubble in the PZR
/08K2.02 Component Cooling Water 3.0 3.2 El El El El El El El El El El CCW pump, including emergency backup 0K2.03 Pressurizer Pressure Control 2.8 3.0 El El El El El El El El El El Indicator for PORV position
/0 Reactor ProtectiOn 3.6 3.6 El El El El El El El El El El Channel blocks and bypasses 2K2.01 Reactor Protection 3.3 3.7 El El El El El El El El El El RPS channels, components and interconnections Page 1 of 3 6/2212009 12:00 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO Reactor Coolant Pump 3.0 3.0 0 0 0 ~ 0 0 0 0 0 o
Isolation valve interlocks
,eA
/
p63K6.04 Reactor Coolant Pump 2.B 3.1 0 0 0 ~ 0 0 0 0 Containment isolation valves affecting RCP operation 04K1.36 Chemical and Volume Control 2.6 2.B
~ 0 0 0 0 0 0 0 0 0 0 CCWS
/
l05K3.05 Residual Heat Removal 3.7 3.B 0 0 ~ 0 0 0 0 0 0 0 0 ECCS 05K4.01 Residual Heat Removal 3.0 3.2 0 0 0 ~ 0 0 0 0 0 0 Overpressure mitigation system 06A3.05 Emergency Core Cooling 4.2 4.3 0 0 0 0 ooo~oo Safety Injection Pumps 07K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 0 0 0 0 ~
Method of forming a steam bubble in the PZR OBK2.02 Component Cooling Water 3.0 3.2 0 ~ 0 0 000 CCW pump, including emergency backup OK2.03 Pressurizer Pressure Control 2.B 3.0 0 ~ 0 0 0 0 0 000 Indicator for PORV position Reactor Protection 3.6 3.6 0 0 0 0 0 0 0 o~o Channel blocks and bypasses Reactor Protection 3.3 3.7 0 ~ 0 0 0 0
000 RPS channels, components and interconnections Page 1 of 3 6/2212009 12:00 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 1
064A1.08
/
M.03 KA NAME I SAFETY FUNCTION:
IR Ki 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
7 AC SAC
/Q3A3.02 Engineered Safety Features Actuation 4.1 4.2 El El Operation of actuated equipment Engineered Safety Features Actuation 2.7 3.1 El El El El El El El El El El Sensors and detectors 022A3.0l Containment Cooling 4.1 4.3 El El El El
[
lnitia tion of safeguards mode of operation 1
26A1.03 Containment Spray 3.5 3.5
] [ ]
Containment sump level 09G2.1.19 Main and Aeheat Steam 3.9 3.8 El El El El El El El El El El Ability to use plant computer to evaluate system or
,/
component status.
9A2.06 Main Feedwater 2.7 2.9 El El El El El El El El El El Loss of steam flow to MFW system
/
y59K3.02 Main Feedwater 3.6 3.7 El El ] El El El El El El El El AFW system 7
/611(6.02 Auxiliary/Emergency Feedwater 2.6 2.7 El El El El El El El El El El Pumps 72K3.03 AC Electrical Distribution 3.7 3.9 El El El El El El El El El El DC system 063K4.02 DC Electrical Distribution 2.9 3.2 El El El El El El El El El El Breaker interlocks, permissives, bypasses and cross-ties.
Emergency Diesel Generator El El El El El El El El El El 3.1 3.4 3 E?.3 Maintaining minimum load on ED/G (to prevent reverse power)
Page 2 of 3 6/22/2009 12:00 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G
/
RO SRO J3A3.02 Engineered Safety Features Actuation 4.1 4.2 0000 oo~oo
!3K6.01 Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 ~ 0 0 0 0 022A3.01
- 026A1.03 f
/
Containment Cooling Containment Spray l39G2.1.19 Main and Reheat Steam 0.59A2.06 Main Feedwater I
jS9K3.02 Main Feedwater Auxiliary/Emergency Feedwater
,62K3.03 AC Electrical Distribution 063K4.02 DC Electrical Distribution
/1
/64A1.0B Emergency Diesel Generator frl* o:?>
4.1 4.3 0 0 ooooo~oo 3.S 3.S 0 0 0 0 0 0 ~ 0 DO 3.9 3.B ooooooooo~
2.7 2.9 ODD ooo~ooo 3.6 3.7 0 0 ~ 0 0 0 0 0 0 0 0 2.6 2.7 0 0 0 0 0 ~ 0 0 0 0 3.7 3.9 0 0 ~ 0 0 0 0 0 0 0 2.9 3.2 0 o~ooo 3.1 3.4 0 0 0 0 ~ 0 0 0
3 :1.33 Page 2 of 3 FORM ES-401-2 TOPIC:
Operation of actuated equipment Sensors and detectors Initia tion of safeguards mode of operation Containment sump level Ability to use plant computer to evaluate system or component status.
Loss of steam flow to MFW system AFW system Pumps DC system Breaker interlocks, permissives, bypasses and cross-ties.
Maintaining minimum load on ED/G (to prevent reverse power) 6/2212009 12:00 PM
T2G1 PWR EXAMINATION OUTLINE IR Ki k2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 2.9 ELIDE ELIDE 3.1 3.1 DLIL1 DLLD LI ES-401, REV 9 KA NAME / SAFETY FUNCTION:
/
RO 64A2.02 Emergency Diesel Generator 2.7 5.01 Process Radiation Monitoring 2.5 3.0 LI FORM ES-401-2
)Y76A2.02 I
Service Water 2.7 3.1
[]
0718A4.01 Instrument Air F.
TOPIC:
Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level temperatures Lqvjz Let dSltQ.eci Radiation theory, including sources, types, units and effects Service water header pressure 1 03G2.1.20 Containment 4.6 4.6 103G2.4.20 Containment 3.8 4.3 Pressure gauges Ability to execute procedure steps.
Knowledge of operational implications of EOP warnings, cautions and notes.
Page 3 of 3 6/22/2009 12:00 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
!64A2.02 Emergency Diesel Generator
/
"73~5.01 Process Radiation Monitoring 6A2.02 Service Water OiBA4.01 Instrument Air
/-
103G2.1.20 Containment 103G2.4.20 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 2.9 DO oooo~ooo 2.5 3.0 o
~OOOOOO 2.7 3.1 ooooooo~ooo 3.1 3.1 0 0 0 0 0 0 0 0 0 ~ 0 4.6 4.6 0 0 0 0 0 0 0 0 0 ~
3.B 4.3 0 0 0 0 0 0 0 0 0 0 ~
Page 3 of 3 FORM ES-401-2 TOPIC:
Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level temperatures Lq\\',e Lev('l. as<\\t().e\\~ ~ o~l,J Radiation theory, including sources, types, units ana effects Service water header pressure Pressure gauges Ability to execute procedure steps.
Knowledge of operational implications of EOP wamings, cautions and notes.
6/2212009 12:00 PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
/
RO O2A4.O8 Reactor Coolant 3.4 3.7
[] ] []
[
Safety parameter display systems j
,A11K2.02 Pressurizer Level Control 3.1 3.2 El El El El El El El El El El PZR heaters
/
f29A2.04 Containment Purge 2.5 3.2 El El El El El El El Health physics sampling of containment atmosphere
/
/33A3.02 Spent Fuel Pool Cooling 2.9 3.1 El El El El El El El El El El Spent fuel leak or rupture
$Y4lK6.O3 Steam Dump/Turbine Bypass Control 2.7 2.9 El El El El El El El El El El Controller and positioners, including CS, SIG, CRDS I
y45K3.ol Main Turbine Generator 2.9 3.2 El El El El El El El El El El Remainder of the plant
\\56G2222 Condensate 4.7 El El El El El El El El El El Knowledge of limiting conditions for operations and safety limits.
72Kl.O3 Area Radiation Monitoring 3.6 3.7 El El El El El El El El El El Fuel building isolation r
/
5) 1 79K4.Ol Station Air 2.9 3.2 El El El El El El El El El El Cross-connect with AS 086K5.03 Fire Protection 3.1 3.4 El El El El El El El El El El Effect of water spray on electrical components Page 1 of 1 6/22/2009 12:00 PM ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G II
.1/
jD02A4.08 11K2.02 f29A2.04 33A3.02 d41K6.03 1
I 14SK3.01 RO SRO Reactor Coolant 3.4 3.7 0 0 0 0 0 0 0 0 0 ~ 0 Pressurizer Level Control 3.1 3.2 0 ~ 0 0 0 0 0 0 0 0
Containment Purge 2.S 3.2 0 0 0 0 0 0 0 ~ 0 0 0 Spent Fuel Pool Cooling 2.9 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Steam DumpfTurbine Bypass Control 2.7 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Main Turbine Generator 2.9 3.2 0 0 ~ 0 0 0 0 0 0 0 0
~6G~ Condensate ooooo~
~ 4.7 0000
\\72K1.03
/
j679K4.01 I
086KS.03 Area Radiation Monitoring Station Air Fire Protection ex 3.6 3.7
~oooooooooo 2.9 3.2 ooo~o 00000 3.1 3.4 0 0 0 000 fage 1 of 1 FORM ES-401-2 TOPIC:
Safety parameter display systems a~ ~
6a~ ~w~.>.
PZR heaters Health physics sampling of containment atmosphere Spent fuel leak or rupture Controller and positioners, including ICS, S/G, CRDS Remainder of the plant Knowledge of limiting conditions for operations and safety limits.
Fuel building isolation rJJ~
Cross-connect with lAS Ai 0 itd-..A[ sFt,
'T-solft-iwA r Effect of water spray on electrical components 6/2212009 12:00 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 Emergency Procedures/Plans KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.36 Conduct of operations 3.0 4.1 LI LI LI Knowledge of procedures and limitations involved in core alterations G2.l.45 Conduct of operations 4.3 LI LI LI LI LI LI LI LI LI LI Ability to identify and interpret diverse indications to validate the response of another indication G2.2.25 Equipment Control 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
G2.2.39 Equipment Control 3.9 4.5 Knowledge of less than one hour technical specification action statements for systems.
G2.2.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.l 1 Radiation Control 3.8 4.3 Ability to control radiation releases.
G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.16 Emergency Procedures/Plans 3.5 4.4 LI Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
o G2.4.44 4.4 LI LI LI LI LILILILILI LI Knowledge of emergency plan protective action recommendations.
Page 1 of 1 6/22/2009 12:00 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.36 Conduct of operations G2.1.45 Conduct of operations G2.2.25 Equipment Control G2.2.39 Equipment Control G2.2.42 Equipment Control G2.3.11 Radiation Control G2.3.12 Radiation Control G2.3.7 Radiation Control G2.4.16 Emergency Procedures/Plans G2.4.44 T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 4.1 0 0 0 0 0 0 0 0 0 0 ~
4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~
3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~
3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~
3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.8 4.3 0 0 0 0 0 0 0
O~
3.2 3.7 0 oooooooo~
3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~
3.5 4.4 0 0 0 0 0 0 0 0 0 0 ~
oooo~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of procedures and limitations involved in core alterations Ability to identify and interpret diverse indications to validate the response of another indication Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Knowledge of less than one hour technical specification action statements for systems.
Ability to recognize system parameters that are entry-level conditions for Technical Specifications Ability to control radiation releases.
Knowledge of radiological safety principles pertaining to licensed operator duties Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
Knowledge of emergency plan protective action recommendations.
6/2212009 12:00 PM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
I AC SRO iOi 1 EG2.4.41 Large Break LOCA /3 2.9 4.6
[] El El El El El El El El El Knowledge of the emergency action level thresholds and classifications.
/
96AG2*+.
Loss of Component Cooling Water / 8 3.9 3.8 El El El El El El El El El El Ability to use plant computer to evaluate system or Z.i.Z.3 component status.
A7AA2.09 Pressurizer Pressure Control System 3.5 3.6 El El El El El El El El El El Reactor power Malfunction / 3
/O9EA2.02 ATWS / 1 4.2 4.4 El El El El El El El El El El Reactor trip alarm
/
058.G2.4.l 1 Loss of DC Power / 6 4.0 4.2 El El El El El El El El El El Knowledge of abnormal condition procedures.
BE 9
4EA2.l Inadequate Heat Transfer
- Loss of Secondary Heat Sink / 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
3.2 4.4 ElElElElElElElElElEl Page 1 of 1 6/22/2009 12:00 PM ES-401, REV 9 KA
/
NAME / SAFETY FUNCTION:
- 011 EG2.4.41 Large Break LOCA / 3 SRO T1 G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 4.6 D D D D D D D D D D ~
J26AG~ Loss of Component Cooling Water /8 3.9 3.8 D D D D D D D D D D ~
Z.1*l.3 7AA2.09
/
)d29EA2.02 058 Pressurizer Pressure Control System 3.5 3.6 D D D D D D D ~ D D Malfunction / 3 ATWS / 1 4.2 4.4 D D D D D D D ~ D D D Loss of DC Power / 6 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 4.0 4.2 D D D D D D D D
~
3.2 4.4 D D D D D D D ~ D D
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of the emergency action level thresholds and classifications.
Ability to use plant computer to evaluate system or component status.
Reactor power Reactor trip alarm Knowledge of abnormal condition procedures.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
6/2212009 12:00 PM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO O32AG2.4.45 Loss of Source Ran e NI /7 4.1 4.3 Ability to prioritize and interpret the significance of each i-p annunciator or alarm.
34( 033AG2.l.25 Loss of Intermediate Range NI /7 3.9k 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
(t23) 4 BAO1AA2.l Plant Runback/ 1 3
3.7 El El El El El El El Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BAO4AA2.2 Turbine Trip / 4 3.7 3.7 El El El El El El El El El El Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
f Page 1 of 1 6/22/2009 12:00 PM f
rp ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO
--7i032AG2.4.45 Loss of Source R:;fu NI/7 4.1
~
Tt( f -t of J:::~e R-PllJfl-4.3 0000 0000
~
lI¥ 033AG2.1.25 Loss of Intermediate Range NI/7 3.9. 4.2 000000000 4-1.5. 15A51S.
~
~ 1./*?/&
~ 2.\\.23 BA01AA2.1 Plant Runback 11 3
3.7 0 0 0 0 0 0 0 ~ 0 0 0 BA04AA2.2 Turbine Trip 1 4 3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0
~ 1-0010 qf 9ef Bcac CIt later.
Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to prioritize and interpret the significance of each annunciator or alarm.
Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
i'QU)t? ~
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
6/2212009 12:00 PM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Knowledge of low power! shutdown irnpHcations in accident (e.g. LOCA or loss of RHR) mitigation strategies.
KA NAME/SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
/
RO 403A2.O5 Reactor Coolant Pump 2.5 2.8 Effects of VCT pressure on RCP seal leakoff flows
/
,p2A2.04 Containment Cooling 2.9 3.2 El Loss of service water 3
A2.O4 Containment Spray 3.9 4.2 Failure of spray pump
/
0,9G2.242 Main Feedwater 3.9 4.6 El El El El El El El El El El Ability to recognize system parameters that are entry
/
level conditions for Technical Specifications Containment 3.8 4.2 El El El El El El El El El El 103G2.4.9 Page 1 of 1 6/22!2009 12:00 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
03A2.05 Reactor Coolant Pump 2A2.04 Containment Cooling
,6A2.04 Containment Spray
/
f9G2.2.42 Main Feedwater
)03G2.4.9 Containment SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 2.8 0 0 0 0 0 0 0 ~ 0 0 0 2.9 3.2 0
D~DDD 3.9 4.2 0 0 0 0 0 0 0 ~ 0 0 0 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.8 4.2 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Effects of VCT pressure on RCP seal leakoff flows Loss of service water Failure of spray pump Ability to recognize system parameters that are entry-level conditions for Technical Specifications Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
6/2212009 12:00 PM
/
NAME / SAFETY FUNCTION:
/
yiA2.06 Pressurizer Level Control 027A2.0l Containment Iodine Removal 072G,4l Area Radiation Monitoring SRO T2G2 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO DELI 3.0 3.3 4.6
4.8 TOPIC
Inadvertent PZR spray actuation High temperature in the filter system Pt cc L \\. 01 1 Knowledge of EOP entry conditions and immediate action steps.
FORM ES-401 -2 Page 1 of 1 6/22/2009 12:00 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
r A2.06 Pressurizer Level Control 027A2.01 Cont.
oL7 G, z. 2.. 4Q ""monliod'" Remo,"'
-,L~
l
~
Area Radiation Monitoring SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.9 D D D D D D D ~ D D D 3.0 3.3 D D D DD~DD 4.6 4.8 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Inadvertent PZR spray actuation High temperature in the filter system PIC\\(, AJJ.~ v./A t\\.O l citw Knowledge of EOP entry conditions and immediate action steps.
6/22/2009 12:00 PM
~
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.l.14 Conduct of operations G2.1.41 Conduct of operations G2.2.2 Equipment Control G2.2.35 Equipment Control G2.3.4 Radiation Control G2.4.27 Emergency Procedures/Plans G2.4.8 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SAC 3.1 3.7 4.1 4.5 3.7 3.9 4.5 FORM ES-401-2 RO 3.1 2.8 4.6 3.6 3.2 3.4
3.8 TOPIC
Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
Knowledge of the refueling processes Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
Ability to determine Technical Specification Mode of Operation Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of fire in the plant procedures.
Knowledge of how abnormal operating procedures are used in conjunction with EOP5.
Page 1 of 1 6/22/2009 12:00 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.14 Conduct of operations G2.1.41 Conduct of operations G2.2.2 Equipment Control G2.2.35 Equipment Control G2.3.4 Radiation G2.4.27 Emergency Procedures/Plans G2.4.8 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.1 D D D D D D D D D D ~
2.8 3.7 D D D D D D D ~
4.6 4.1 D D D D D D D D D D ~
3.6 4.5 D D D D D D D D D D ~
3.2 3.7 D D D D D D D D D D ~
3.4 3.9 D D D D D D D D D D ~
3.8 4.5 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
Knowledge of the refueling processes Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
Ability to determine Technical Specification Mode of Operation Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of "fire in the plant" procedures.
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
6/2212009 12:00 PM
JCor £JrFcf ES-401 Record of Rejected KIAs Form ES-401-4 Tier /
Randomly Reason for Rejection Group Selected K/A RO 2/1 003K4.04 (9/10/09) KA required CCWS question. KA changed due to oversampling of CCWS. NRC selected 003K4.1 1.
RO 1/2 067AA1.05 (11/17/09) There are no plant or control room ventilation systems operated or monitored from control room as a result of a fire. NRC selected 067AA1.03.
RO 2/1 064A1.08 (11/17/09) Could not make the KA apply to Keowee Hydro Units since it was specific to DGs. NRC selected 064A1.03.
SRO 2/2 027A2.01 (11/17/09) Containment Iodine Removal at ONS is accomplished using Reactor Building Spray and Caustic baskets therefore there are no associated filters as required by KA. NRC selected 027G2.2.40.
SRO 1/2 033AG2.1.32 (11/17/09) ONS has no Operations procedural limits and precautions specific to either Intermediate Range or Wide Range nuclear instrumentation. NRC selected 033AG2.1.23 ZOla -SD(
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA RO 2/1 003K4.04 (9/10109) KA required CCWS question. KA changed due to oversampling of CCWS. NRC selected 003K4.11.
RO 1/2 067AA1.05 (11/17/09) There are no plant or control room ventilation systems operated or monitored from control room as a result of a fire. NRC selected 067AA1.03.
RO 2/1 064A1.08 (11/17/09) Could not make the KA apply to Keowee Hydro Units since it was specific to OG's. NRC selected 064A1.03.
SRO 2/2 027A2.01 (11/17/09) Containment Iodine Removal at ONS is accomplished using Reactor Building Spray and Caustic baskets therefore there are no associated "filters" as required by KA. NRC selected 027G2.2.40.
SRO 1/2 033AG2.1.32 (11/17/09) ONS has no Operations procedural limits and precautions specific to either Intermediate Range or Wide Range nuclear instrumentation. NRC selected 033AG2.1.23 j,
crrw ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
3129/10 Examination Level:
I Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-114, Mode Change Verification for Mode 1&2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2)
PT/1/A10600/001 B, End. 13.23 (Both) (Simulator) (20 mm)
Admin-I13, Calculate an Estimated Critical Rod Position Conduct of Operations D,R PTI1IA/1103!015 (Reactivity Balance Procedure) End.
GEN 2.1.19 (3.9/3.8) 13.4 (Computerized ECP Calculation) (RO Only)
(17 Minutes)
Admin-207 Perform SG Downcomer Temperature Surveillance Equipment Control N,S OP/1/A/1105/014 EncI4.1 (Mode 1&2) and End. 4.16 GEN 2.2.12 (3.7/4.1)
(Channel Check Of OTSG Downcomer Temperatures)
(RO Only)
N/A Radiation Control ADMIN-402, Perform Actions for Medical Emergency RP/1 000/01 6, End. 4.1 (Medical Response)
Emergency Procedures/Plan D,C (RO Only) (15 mm)
Gen 2.4.39 (3.9/3.8)
NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (1)
(P)revious 2 exams (1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
3/29/10 Examination Level: ROG SRoD Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-114, Mode Change Verification for Mode 1 &2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2)
PT/1IA/06001001 B, Enel. 13.23 (Both) (Simulator) (20 min)
Admin-113, Calculate an Estimated Critical Rod Conduct of Operations Position D,R PT/1/A/1103/015 (Reactivity Balance Procedure) Encl.
GEN 2.1.19 (3.9/3.8) 13.4 (Computerized ECP Calculation) (RO Only)
(17 Minutes)
Admin-207 Perform SG Downcomer Temperature Equipment Control Surveillance N,S OP/1/A/1105/014 Encl 4.1 (Mode 1 &2) and Encl. 4.16 GEN 2.2.12 (3.7/4.1)
(Channel Check Of OTSG Downcomer Temperatures)
(RO Only)
Radiation Control N/A ADMIN-402, Perform Actions for Medical Emergency Emergency Procedures/Plan D,C RP/1 000/016, Encl. 4.1 (Medical Response)
Gen 2.4.39 (3.9/3.8)
(RO Only) (15 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 all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~4 for SROs & RO retakes)
(N)ew or (M)odified from bank (;:::1)
(P)revious 2 exams (~1; randomly selected)
DRAFT ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
3/29110 Examination Level:
RO El SRO L1 Operating Test Number:
i Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-114, Mode Change Verification for Mode 1&2 Conduct of Operations D
entry GEN 2.1.25 (3.9/4.2)
PTI1IAJO600IOO1B, End. 13.23 (Both) (Simulator) (20 mm)
Conduct of Operations N,R Admin-1 17, Evaluate SSF-ASW operability based on GEN 2.1.7 (4.4/4.7)
Pressurizer Relief Valve leakage PT/2/A/0610/001 (Reactor Coolant Leakage) Attach.
13.5 (Pzr Relief Valve Leakage Calculation)
(SRO Only) Group Activity Equipment Control D,R Admin-203, Complete Plant Configuration Sheet GEN 2.2.18 (2.6/3.9)
(Calculate Time to Core Boil)
S. D. 1.3.5 Attachment 9.3A (SRO only) (group activity) (1 1 mm)
Radiation Control M,R Admin-303, Stay time calculation GEN 2.3.7 (3.5/3.6)
NSD-507, Radiation Protection (SRO Only) (13 minutes)
Emergency Procedures/Plan DR Admin-405, Determine Emergency Classification GEN 2.4.41 (2.9/4.6) and Protective Action Recommendations RP/0/B/1 000/01, RP/0/B/1 000/02 BASIS Document (Volume A, Section D of the Emergency Plan) (SRO Only) (20 minutes)
NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (3 for RO5; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (1)
(P)revious 2 exams (1; randomly selected)
F ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
3/29/10 Examination Level: RO D SRO G Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-114, Mode ChangeVerification for Mode 1&2 Conduct of Operations D,S entry GEN 2.1.25 (3.9/4.2)
PT/1/A/06001001 B, Ene!. 13.23 (Both) (Simulator) (20 min)
Conduct of Operations N,R Admin-11l, Evaluate SSF-ASW operability based on GEN 2.1.7 (4.4/4.7)
Pressurizer Relief Valve leakage PT/2/Al0610/001 (Reactor Coolant Leakage) Attach.
13.5 (pzr Relief Valve Leakage Calculation)
(SRO Only) Group Activity Equipment Control D,R Admin-203, Complete Plant Configuration Sheet GEN 2.2.18 (2.6/3.9)
(Calculate Time to Core Boil)
S. D. 1.3.5 Attachment 9.3A (SRO only) (group activity) (11 min)
Radiation Control M,R Admin-303, Stay time calculation GEN 2.3.7 (3.5/3.6)
NSD-507, Radiation Protection (SRO OnlY) (13 minutes)
Emergency Procedures/Plan D,R Admin-405, Determine Emergency Classification GEN 2.4.41 (2.9/4.6) and Protective Action Recommendations RP/O/B/1 000/01, RP/O/B/1000/02 BASIS Document (Volume "A", Section "D" of the Emergency Plan) (SRO Only) (20 minutes)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (::;3 for ROs; ::;4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~1)
(P)revious 2 exams (::;1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee
Date of Examination: March 29, 2010 Exam Level: RD X SRO-l El SRO-U Li Operating Test No.:
1 Control Room Systems© (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a.
CRO-108 Perform Reactor Manual Trip Test PT/1/N0305/001 (Reactor Manual Trip Test)
N, S, L 1
014 A4.01 (3.3/3.1)_(20_mm) b.
CRO-207 Pressure makeup to CFT with failure.7 of OP/i/A/i 104/01 M, A, S 2
006 A1.13 (3.5/3.7)_(10_mm) c.
CR0- 301 Verify HPI flow following LBLOCA with degraded HPI N, A, 5, F, 3
FOP Rule 2 (Loss Of SCM)
EN 006 A4.07 (4.4/4.4)_(10_mm) d.
CRO-402, Align ECCS Suction from Emergency Sump during SBLOCA (LP-15 Failed Closed)
M, A, 5, L, F, 4P FOP, End. 5.12 (ECCS Suction Swap to RBFS)
EN BW!F08 EA1.1 (4.0/3.7)_(12_mm) e.
CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow D, A, 5, L, E 4S FOP, LOHT Tab APE 054 AK3.04 (4.4/4.6)_(15_mm) f.
CRO-601, Synchronization with the grid following a load rejection D, 5 6
AP!1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 mm) g.
CRO-085, Adjust Radiation Monitor Setpoints OP/i &2/A/1 104/018, GWD System, End. 4.9 & 4.10 D, 5, P 7
PT/0/A/230/01, (Radiation Monitor Check) 073 A4.01 (3.9/3.9) (8 mm) h.
CRO-800, Perform Required Actions for an Intake Canal Dam Failure D, S 8
AP/13, (Dam Failure) 075 A2.Oi (3.0*/3.2) (20 mm)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: March 29, 2010 Exam Level: RO X SRO-I D SRO-U D Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / J PM Title Type Code*
Safety Function
- a. CRO-108 Perform Reactor Manual Trip Test PT/1/AI03051001 (Reactor Manual Trip Test)
N,S,L 1
014 A4.01 (3.3/3.1) (20 min)
- b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/11 04/01 M,A, S 2
006 A1.13 (3.5/3.7) (10 min)
EOP Rule 2 (Loss Of SCM)
EN 006 A4.07 (4.4/4.4) (10 min)
M, A, S, L, E, 4P EOP, Encl. 5.12 (ECCS Suction Swap to RBES)
EN BW/E08 EA1.1 (4.0/3.7) (12 min)
- e. CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow D,A,S,L,E 4S EOP, LOHT Tab APE 054 AK3.04 (4.4/4.6) (15 min)
- f.
CRO-601, Synchronization with the grid following a load rejection D,S 6
AP/1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 min)
- g. CRO-085, Adjust Radiation Monitor Setpoints OP/1 &2/A/11 04/018, GWD System, Encl. 4.9 & 4.10 D,S,P 7
PT/0/A/230101, (Radiation Monitor Check) 073 A4.01 (3.9/3.9) (8 min)
- h. CRO-800, Perform Required Actions for an Intake Canal Dam Failure D,S 8
AP/13, (Dam Failure) 075 A2.01 (3.0*/3.2) (20 min)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, F 2
FOP End 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE 022 G2.4.35_(3.8/4.0)_(15_mm) j.
CRO-401, Aligning SSF-ASW for SC Feed FOP End. 5.34, (Aligning SSF-ASW for SG Feed)
D, A, E 4S APE_054_AA1_.01_(4.5/4.4)_(10_mm) k.
NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of CS Power) End. 5.2, (Restoration of D, A, F 7
ICS AUTO Power)
BW/A02 AK3.2 (3.7/4.0) (16 mm)
© All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 /
1 /
1 (EN)gineered safety feature
- I I 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1(A) 2 /
2/
1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA 1/1I1 (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout D,R,E 2
EOP Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE 022 G2.4.35 (3.8/4.0) (15 min)
- j.
CRO-401, Aligning SSF-ASW for SG Feed EOP Encl. 5.34, (Aligning SSF-ASW for SG Feed)
D,A,E 4S APE 054 AA 1.01 (4.5/4.4) (10 min)
- k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, (Restoration of D,A,E 7
ICS AUTO Power)
BW/A02 AK3.2 (3.7/4.0) (16 min)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank
- 59/:58/:54 (E)mergency or abnormal in-plant
~1/~1/~1 (EN)gineered safety feature 1 ~1 (control room system)
(L)ow-Power 1 Shutdown
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
- 5 3/:5 3/:5 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator
N
Oconee Date of Examination: March 29, 2010 Exam Level: RO El SRO-l X SRO-U El Operating Test No.:
1 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function a.
CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305!00l (Reactor Manual Trip Test)
N, 5, L 1
014 A4.01 (3.3/3.1) b.
CRO-207 Pressure makeup to CFT with failure.7 of OP/i/All 104/01 M, A, S 2
006 Al.13 (3.5/3.7) c.
CR0- 301 Verify HPI flow following LBLOCA with degraded HPI N, A, 5, F, 3
FOP Rule 2 (Loss Of SCM)
EN 006 A4.07 (4.4/4.4) d.
CRO-402, Align ECCS Suction from Emergency Sump during SBLOCA (LP-15 Failed Closed)
M, A,, L, F 4P FOP, End. 5.12 (ECCS Suction Swap to RBES)
EN BW/E08 FA1.l (4.0/3.7) e.
CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow D, A, 5, L, F 4S FOP, LOHT Tab APF-054 AK3.04_(4.4/4.6)_(15_mm) f.
CRO-601, Synchronization with the grid following a load rejection D, S 6
AP/1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 mm) g.
CRO-085, Adjust Radiation Monitor Setpoints OP/l&2/A/1104/018, GWD System, End. 4.9 &4.10 D, S, P 7
PT/0/A/230/01, (Radiation Monitor Check)
KA: 073 A4.Ol (3.9/3.9) (8 mins) h.NIA 8
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: March 29, 2010 Exam Level: RO D SRO-I X SRO-U D Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)
N,S, L 1
014 A4.01 (3.3/3.1)
- b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/1104101 M,A,S 2
006 A1.13 (3.5/3.7)
EOP Rule 2 (Loss Of SCM)
EN 006 A4.07 (4.4/4.4)
M, A, S, L, E 4P EOP, Enci. 5.12 (ECCS Suction Swap to RBES)
EN BW/E08 EA1.1 (4.0/3.7)
- e. CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow D,A,S, L, E 4S EOP, LOHT Tab APE-054 AK3.04 (4.4/4.6) (15 min)
- f.
CRO-601, Synchronization with the grid following a load rejection D,S 6
AP/1, (Unit Runback) 062 A4.07 (3.1*/3.1*) (10 min)
- g. CRO-085, Adjust Radiation Monitor Setpoints OP/1 &2/A/11 04/018, GWD System, Encl. 4.9 & 4.10 D,S,P 7
PT/0/A/230/01, (Radiation Monitor Check)
KA: 073 A4.01 (3.9/3.9) (8 mins)
- h. N/A 8
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, E 2
EOP End 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APEO22G2.4.35 (3.8/4.0)_(15_mm) j.
CRO-401, Aligning SSF-ASW for SG Feed EOP End. 5.34, (Aligning SSF-ASW for SG Feed)
D, A, E 4S APE_054_AA1_.01_(4.5/4.4)_(10_mm) k.
NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of CS Power) End. 5.2, (Restoration of D, A, E 7
CS AUTO Power)
BW/A02 AK3.2 (3.7/4.0) (16 mm)
All RD and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RD / SRO-l / SRO-U (A)Iternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 /
8 /
4 (E)mergency or abnormal in-plant 1 /
1 /
1 (EN)gineered safety feature
- /
/ 1 (control room system)
(L)ow-Power / Shutdown 1 /
1 /
1 (N)ew or (M)odified from bank including 1 (A) 2 /
2 /
1 (P)revious 2 exams 3 I 3 /
2 (randomly selected)
(R)CA 1/1I1 (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout O,R,E 2
EOP Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE022G2.4.35 (3.8/4.0) (15 min)
- j.
CRO-401, Aligning SSF-ASW for SG Feed EOP Ene!. 5.34, (Aligning SSF-ASW for SG Feed)
O,A, E 4S APE 054 AA1.01 (4.5/4.4) (10 min)
- k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) Enc!. 5.2, (Restoration of O,A,E 7
ICS AUTO Power)
BW/A02 AK3.2 (3.7/4.0) (16 min)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank
$9/$8/$4 (E)mergency or abnormal in-plant 2':1/2':1/2':1 (EN)gineered safety feature
- / -
/ 2':1 (control room system)
(L)ow-Power / Shutdown 2':1/2':1/2':1 (N)ew or (M)odified from bank including 1 (A) 2':2/2':2/2':1 (P)revious 2 exams
$ 3/$ 3/$ 2 (randomly selected)
(R)CA 2':1/2':1/2':1 (S)imulator
rzN r
/
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
Oconee
Date of Examination: March 29, 2010 Exam Level: RD Li SRO-l Li SRO-U X
Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a.
CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)
N, S, L 1
014 A4.01 (3.3/3.1) b.
N/A c.
N/A d.
CRO-402, Align ECCS Suction from Emergency Sump during SBLOCA (LP-15 Failed Closed)
M, A,, L, E, 4P EOP, End. 5.12 (ECCS Suction Swap to RBES)
EN BW/E08 EA1.1 (4.0/3.7) e.
N/A f.
CRO-601, Synchronization with the grid following a load rejection 6
AP/1, (Unit Runback)
D,S 062 A4.07 (3.1*73.1*) (10 mm) g.
N/A h.
N/A ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: March 29, 2010 Exam Level: RO SRO-I D SRO-U X Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. CRO-10B Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test)
N,S,L 1
014 A4.01 (3.3/3.1)
- b. N/A
- c.
N/A
M, A, S, L, E, 4P EOP, Ene!. 5.12 (ECCS Suction Swap to RBES)
EN BW/E08 EA1.1 (4.0/3.7)
- e. N/A
- f.
CRO-601, Synchronization with the grid following a load rejection 6
AP/1, (Unit Runback)
D,S 062 A4.07 (3.1*/3.1*) (10 min)
- g. N/A
- h. N/A
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout D, R, E 2
FOP End 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APEO22 G2.4.35 (3.8/4.0)_(15_mm) j.
N/A k.
NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) End. 5.2, (Restoration of D, A, F 7
CS AUTO Power)
BW!A02 AK3.2 (3.7/4.0) (16 mm)
All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-l I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9/814 (E)mergency or abnormal in-plant 1 /
1 /
1 (EN)gineered safety feature
- /
I 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1(A) 2 /
2 /
1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA 1/1I1 (S)imulator In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout D,R,E 2
EOP Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE022 G2.4.35 (3.8/4.0) (15 min)
- j.
N/A
- k. NLO-700, Restoration of ICS AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, (Restoration of D,A, E 7
ICS AUTO Power)
BW/A02 AK3.2 (3.7/4.0) (16 min)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank
- 59/:58/:54 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature
- / -
/ 2:1 (control room system)
(L)ow-Power / Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)revious 2 exams
- 5 3 / :5 3/:5 2 (randomly selected)
(R)CA 2:1/2:1/2:1 (S)imulator
JPM Overview (Initial Submittal) a.
CRO-108 Perform Reactor Manual Trip Test PT/i/A/0305/001 (Reactor Manual Trip Test) 014 A4.0i (3.3/3.1)
This new JPM will take place with the simulator in MODE 3 at 532°F. The candidate will be required to perform a latch and P1 alignment of group 1 rods, withdraw group ito 10% withdrawn, place Turbine Bypass Valves in HAND, manually trip the Reactor, and verify appropriate indications are received.
- b. CRO-207 Pressure makeup to CFT with failure.7 of OP/i/A/1104/0i 006 A1.13 (3.5/3.7)
This modified JPM will take place on the simulator at 100% power. The candidate will be required to initiate Nitrogen makeup to a Core Flood Tank, monitor the pressure increase, and attempt to secure Nitrogen when appropriate pressure is reached. When the Control Room isolation valve fails to respond, the candidate will be required to use procedure guidance to direct an NEO to use a manual isolation valve to isolate the Nitrogen supply.
This new JPM will take place on the simulator following a LBLOCA. The candidate will be required to perform Rule 2 (Loss Of SCM). When verifying HPI flow, the candidate will note that there is only 1 HPI pump providing flow down one HPI header. The steps opening the HPI header cross connect valves will be bypassed.
The candidate will be required to verify HPI flow is less than max and will be required to add seal injection flow to get the correct actual flow. Flow will be exceeding the limit and require the candidate to throttle flow to be maximized at <
475 gpm.
EOP, End. 5.12 BW/E08 EA1.1 (4.0/3.7)
This modified JPM will take place on the simulator following a SBLOCA. The candidate will be required to use procedure guidance to align HPI/LPI piggyback to allow HPI pumps to take suction on the RBES. When performing the alignment one of the valves in the suction path (1 LP-1 5) will fail to open requiring the candidate to secure one of the LPI pumps previously started and verify LPI and HPI flows.
Page 1 of 3 JPM Overview (Initial Submittal)
- a. CRO-108 Perform Reactor Manual Trip Test PT/1/A/0305/001 (Reactor Manual Trip Test) 014 A4.01 (3.3/3.1)
This new JPM will take place with the simulator in MODE 3 at 532°F. The candidate will be required to perform a latch and PI alignment of group 1 rods, withdraw group 1 to 10% withdrawn, place Turbine Bypass Valves in HAND, manually trip the Reactor, and verify appropriate indications are received.
- b. CRO-207 Pressure makeup to CFT with failure.7 of OP/1/A/1104/01 006 A 1.13 (3.5/3.7)
This modified JPM will take place on the simulator at 100% power. The candidate will be required to initiate Nitrogen makeup to a Core Flood Tank, monitor the pressure increase, and attempt to secure Nitrogen when appropriate pressure is reached. When the Control Room isolation valve fails to respond, the candidate will be required to use procedure guidance to direct an NEO to use a manual isolation valve to isolate the Nitrogen supply.
This new JPM will take place on the simulator following a LBLOCA. The candidate will be required to perform Rule 2 (Loss Of SCM). When verifying HPI flow, the candidate will note that there is only 1 HPI pump providing flow down one HPI header. The steps opening the HPI header cross connect valves will be bypassed.
The candidate will be required to verify HPI flow is less than max and will be required to add seal injection flow to get the correct actual flow. Flow will be exceeding the limit and require the candidate to throttle flow to be maximized at:::
475 gpm.
EOP, Encl. 5.12 BW/E08 EA1.1 (4.0/3.7)
This modified JPM will take place on the simulator following a SBLOCA. The candidate will be required to use procedure guidance to align HPI/LPI piggyback to allow HPI pumps to take suction on the RBES. When performing the alignment one of the valves in the suction path (1 LP-15) will fail to open requiring the candidate to secure one of the LPI pumps previously started and verify LPI and HPI flows.
Page 1 of 3
JPM Overview (Initial Submittal) e.
CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow EOP, LOHT Tab APE-054 AK3.04 (4.4/4.6) (15 mm)
This bank JPM will take place on the simulator following a reactor trip and loss of all FDW where Rule 3 has established Condensate Booster Pump feed to the SGs.
Subsequently the 1A MFDWE pump has become available and is operating in Auto.
The candidate will be required to determine appropriate initial FDW flow to the dry SGs using Rule 7, use guidance in the LOHT tab to re-establish Main FDW to the SGs, and initiate a controlled cooldown.
f.
CRO-601, Synchronization with the grid following a load rejection AP/1, Unit Runback 062 A4.07 (3.1*/3.1*) (10 mm)
This bank JPM will take place on simulator following a load rejection. The candidate will be required to use the guidance provided in the newly issued AP/1 (Unit Rundback) to synchronize the electrical generator with the grid and put the generator on-line.
g.
CRO-085, Adjust Radiation Monitor Setpoints OP/1&2!A/1104/018, GWD System, End. 4.9 &4.10 PT/0/A/230/01, Radiation Monitor Check 073 A4.01 (3.9/3.9) (8 mins)
This bank JPM will take place on the simulator. The candidate will be required to adjust RIA setpoints as required to support a GWD release. This JPM was randomly selected from past 2 years exam.
h.
CRO-800, Perform Required Actions for an Intake Canal Dam Failure AP/13, Dam Failure 075 A2.01 (3.0*/3.2) (20 mm))
This bank JPM will take place on the simulator and require the candidate to perform actions required in AP/13 (Dam Failure). The candidate will be required to stop CCWPs, RCPs, and LPSWPs as well as take actions to reduce the amount of lost inventory.
Page2of3 JPM Overview (Initial Submittal)
- e. CRO-017, Re-establish Main FDW Flow From Condensate Booster Pump Flow EOP, LOHT Tab APE-054 AK3.04 (4.4/4.6) (15 min)
This bank JPM will take place on the simulator following a reactor trip and loss of all FDW where Rule 3 has established Condensate Booster Pump feed to the SG's.
Subsequently the 1A MFDWE pump has become available and is operating in Auto.
The candidate will be required to determine appropriate initial FDW flow to the dry SG's using Rule 7, use guidance in the LOHT tab to re-establish Main FDW to the SG's, and initiate a controlled cooldown.
- f.
CRO-601, Synchronization with the grid following a load rejection AP/1, Unit Runback 062 A4.07 (3.1 */3.1 *) (10 min)
This bank JPM will take place on simulator following a load rejection. The candidate will be required to use the guidance provided in the newly issued AP/1 (Unit Rundback) to synchronize the electrical generator with the grid and put the generator on-line.
- g. CRO-OBS, Adjust Radiation Monitor Setpoints OP/1 &2/A/11 04/018, GWD System, Ene!. 4.9 & 4.10 PT/0/A/230/01, Radiation Monitor Cheek 073 A4.01 (3.9/3.9) (8 mins)
This bank JPM will take place on the simulator. The candidate will be required to adjust RIA setpoints as required to support a GWD release. This JPM was randomly selected from past 2 years exam.
- h. CRO-BOO, Perform Required Actions for an Intake Canal Dam Failure AP/13, Dam Failure 075 A2.01 (3.0*/3.2) (20 min))
This bank JPM will take place on the simulator and require the candidate to perform actions required in AP/13 (Dam Failure). The candidate will be required to stop CCWP's, RCP's, and LPSWP's as well as take actions to reduce the amount of lost inventory.
Page 2 of 3
JPM Overview (Initial Submittal)
I.
NLO-200 Align HPI Pump Suction to BWST During a Blackout EOP End 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE 022 G2.4.35 (3.8/4.0) (15 mm)
This bank JPM will take place in the plant. The candidate will be required to manually align the HPIP sucition to the BWST. This will require entry into the RCA and then locating several valves. These valves will be manually operated. Findally the candidate will be required to manually throttle one of the HPI injection valves per direction from the control room.
j.
CRO-401, Aligning SSF-ASW for SG Feed EOP End. 5.34, Aligning SSF-ASW for SG Feed APE 054 AA1.01 (4.5/4.4) (10 mm)
This bank JPM will start in the Unit 1&2 Control Room but will take place in the SSF.
The candidate will be required to locate designated keys and flashlight then go to the SSF. Once in the SSF, the candidate will start the SSF D/G (this will require manually starting a cooling water pump that fails to auto start), and perform various valve and breaker manipulations.
k.
NLO-700, Restoration of CS AUTO Power AP/23 (Loss of ICS Power) End. 5.2, Restoration of ICS AUTO Power BW/A02 AK3.2 (3.7/4.0) (16 mm)
This bank JPM will take place in the plant. The candidate will be required to restore power to the ICS inverter (KI). This will include resetting a tripped breaker and then attempting to close it. The breaker will trip open again requiring the candidate to perform several breaker operations to restore power to the inverter.
Page3of3 JPM Overview (Initial Submittal)
- i.
NLO-200 Align HPI Pump Suction to BWST During a Blackout EOP Encl 5.7 (HPI Pump Operations from ASW Pump Switchgear)
APE 022 G2.4.35 (3.8/4.0) (15 min)
This bank JPM will take place in the plant. The candidate will be required to manually align the HPIP sucition to the BWST. This will require entry into the RCA and then locating several valves. These valves will be manually operated. Findally the candidate will be required to manually throttle one of the HPI injection valves per direction from the control room.
- j.
CRO-401, Aligning SSF-ASW for SG Feed EOP Encl. 5.34, Aligning SSF-ASW for SG Feed APE 054 AA 1.01 (4.5/4.4) (10 min)
This bank JPM will start in the Unit 1 &2 Control Room but will take place in the SSF.
The candidate will be required to locate designated keys and flashlight then go to the SSF. Once in the SSF, the candidate will start the SSF DIG (this will require manually starting a cooling water pump that fails to auto start), and perform various valve and breaker manipulations.
- k. NLO-700, Restoration of les AUTO Power AP/23 (Loss of ICS Power) Encl. 5.2, Restoration of ICS AUTO Power BW/A02 AK3.2 (3.7/4.0) (16 min)
This bank JPM will take place in the plant. The candidate will be required to restore power to the ICS inverter (KI). This will include resetting a tripped breaker and then attempting to close it. The breaker will trip open again requiring the candidate to perform several breaker operations to restore power to the inverter.
Page 3 of 3