ML023390151
| ML023390151 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/07/2002 |
| From: | Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-250/02-301, 50-251/02-301 | |
| Download: ML023390151 (54) | |
Text
Administrative Documents TURKEY POINT EXAM 2002-301 50-250, 50-251/2002-301 OCTOBER 7 - 11 & 15, 2002 L4.
/ Exam Preparation Checklist.......
-e2. XExam Outline Quality Checklist....
K-. XiExam Security Agreement........
4 v-Administrative Topics Outline (Final)
ES-201-1 ES-201-2 ES-201-3 ES-301-1
,,Control Room Systems and Facility Walk-through Test Outline (F ina l)...........................
LOT Operating Test Quality Check Sheet.........
..... S-3 1-2 ES-301-3 13
/Simulator Scenario Quality Check Sheet...........
ES-301-4 t/8. ->Transient and Event Checklist...................
ES-301-5 jg. XCompetencies Checklist........................
ES-301-6 4 0.X/Written Exam Quality Check Sheet...............
)12/Written Exam Review Worksheet.................
ES-401-9 Pt*. -Written Exam Grading Quality Checklist...........
- 13. v#Post-Exam Check Sheet............
........ I... ES-501 -1
ES-201 Examination Preparation Checklist Form ES-201-1 Facility:
Turkey Point Nuclear Plant Date of Exam: October 7-11, 2001 Examinations Developed by:
Written:
NRC Operating:
NRC (outline)/Facilty (guts)
Target Chief Date*
Task Description / Reference Examiner's Initials
-180
- 1. Examination administration date confirmed (C.l.a; C.2.a & b) rfa
-120
- 2. NRC examiners and facility contact assigned (C.l.d; C.2.e) rfa
-120
- 3. Facility contact briefed on security & other requirements (C.2.c) rfa
-120
- 4. Corporate notification letter sent (C.2.d) rfa
[-90]
[5. Reference material due (C.1.e; C.3.c)]
rfa
-75
- 6. Integrated examination outline(s) due (C.1.e & f; C.3.d) rfa
-70
- 7. Examination outline(s) reviewed by NRC and feedback provided rfa to facility licensee (C.2.h; C.3.e)
-45
- 8. Proposed examinations, supporting documentation, and tia reference materials due (C.l.e, f, g & h; C.3.d)
-30
- 9. Preliminary license applications due (C.1.1; C.2.g; ES-202) tie
-14
- 10. Final license applications due and assignment sheet prepared rfa (C.1.1; C.2.g; ES-202)
-14
- 11. Examination approved by NRC supervisor for facility licensee rfa review (C.2.h; C.3.f)
-14
- 12. Examinations reviewed with facility licensee (C.11.; C.2.f & h; C.3.g) tie
-7
- 13. Written examinations and operating tests approved by rfa NRC supervisor (C.2.i; C.3.h)
-7
- 14. Final applications reviewed; assignment sheet updated; waiver rfa letters sent (C.2.g, ES-204)
- 15. Proctoring/written exam administration guidelines reviewed with rfa
-7 facility licensee and authorization granted to give written exams (if applicable) (C.3.k)
-7
- 16. Approved scenarios, job performance measures, and questions rfa 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.
ES-201 Examination Outline Form ES-201-2 Quality Checklist Facility: Turkey Point Date of Examination:
Initials Item Task Description a
b*
cI
- 1.
- a. Verify that the outline(s) fit(s) the appropriate model per ES-401.
W R
- b. Assess whether the outline was systematically and randomly prepared in accordance with I
Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
Tr T
- c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
r E
N
- d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.
1 r*,
- 2.
- a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of Sg normal evolutions, instrument and component failures, and major transients.
S I
- b. Assess whether there are enough scenario sets (and spares) to test the projected number and gh M
mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure 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 scenarios will not be repeated over successive 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:
rh (1) the outline(s) contain(s) the required number of control room and in-plant tasks, W
(2) no more than 30% of the test material is repeated from the last NRC examination,
/
(3)* no tasks are duplicated from the applicants' audit test(s), and T
(4) no more than 80% of any operating test is taken directly from the licensee's exam banks.
- b. Verify that:
gh (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) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.
- c. Verify that the required administrative topics are covered, with emphasis on performance based activities.
- d. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on successive days.
- 4.
- a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the raA appropriate exam section.
G E
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
r ra E
- c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
R
- d. Check for duplication and overlap among exam sections.
ra ra A
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- e. Check the entire exam for balance of coverage.
raA
r*r r-
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- j P'ed Name / Signature Date
- a. Author Written (Steve Rose)
,/test (Ron Aiello) 8/29/02
- b. Facility Reviewer (*)
N/A
_7
- c. NRC Chief Examiner (#)
Writt0--est George H 9/04/02
- d. NRC Supervisor Mike Ernstes Mee 9/4/02) 1/yIoz Note:
- Not applicable for NRC-developed examinations.
A# Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.
'2C0-zo ZI+/-X&h5 (TaNsecxtnb((
?a~je t of2-ES-201 Examination Security Agreement Form ES-201-3
- 1.
Pre-Examination 7ý,AA I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of oct 2002 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC.Furthermore, I am aware of the physical security measures and requirements (as documented In the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2.
Post-Examination To the best of my knowlep7ge/ id not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 0 From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATU-1)
- 13.
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?%e Zi-ES-201 Examination Security Agreement Form ES-201-3
- 1.
Pre-Examinatlon
/n/2*
I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of /0//y/01-as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC.Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2.
Post-Examination --- £fec-;s, k0 y6
/o-02_
CLw To the best of my knowledgel cid not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of i{.LZFrom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME
- 1.
2.
- 5.
- 6.
- 7.
- 8.
9.14 11 JOB TITLE / RESPONSIBILITY k4e SLAPV SIGNATURE (1)
DATE SIGNATURE (2) DATENOTE
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- 2.
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NOTES:
NUREG-1021, Revision 8, Supplement 1 V
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A 24 of 24
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Date of Examination:
10/07/02 Examination Level (circle one): RO / SRO Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 JPM Verify Axial Flux Difference Compliance with ERDADS Inoperable (*-ONOP-059.4 & *-OSP-201.1 Att 8)
JPM Perform RCS Leak Rate Calculation Using Manual Method (Facility Bank)
(JPM#R0410362)
A.2 JPM Write a Boric Acid Pump Discharge Valve Clearance (RO)
A.3 JPM Calculate Dose During Emergency Operations A.4 JPM Make Emergency Notification (RO)
(Modified)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Date of Examination:
10/07/02 Examination Level (circle one):
RO / SRO Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 JPM Verify Axial Flux Difference Compliance with ERDADS Inoperable (*-ONOP-059.4 & *-OSP-201.1 Att 8)
JPM (Facility Bank)
Perform RCS Leak Rate Calculation Using Manual Method (JPM#R0410362)
A.2 JPM Review a Boric Acid Pump Discharge Valve Clearance A.3 JPM Calculate Dose During Emergency Operations A.4 JPM Classify Event and Make Protective Action Recommendations (Facility Bank)
L-b-Ul control Rioom bystems and racility WalK-I nrougn I est uutine F-orm Eb-3Ul-2 Facility:
Turkey Point Date of Examination:
10/07/02 Exam Level (circle one): RO / SRO(I) I SRO(U)
Operating Test No.:
1 B.1 Control Room Systems I
Safety System / JPM Title Type Code*
Function
- a. Sys. 064/JPM, Perform EDG Normal Start Test. (Build (M) (A) (S) 6 from bank R0230060, Perform the Emergency Diesel Generator Operability Test. Includes voltage regulator malfunction at end of JPM.)
- b. Sys.O15IJPM #R0590030, Adjust High Flux at (D) (S) (L) 7 Shutdown Alarm (N-31)
- c. Sys. 061/JPM #A0750190, Perform the AFW Flow Control (M) (S) (L) 4S Valve Operability Test.
- d. Sys. 007/JPM, Drain the Pressurizer Relief Tank. Lift PORV during draining. Fail PORV, block valve yielding (N) (A) (S) 5 auto reactor trip.
I
- e. APE 068/JPM, Control Room Evacuation as Unit 3 RCO (
(N) (S)
Fire in Cable Spreading Room). Fire damage causes spurious train A equipment actuation.
- f.
Sys. 006/JPM, Restore Accumulator Pressure and Level (M) (S) 3
- g. Sys. 003/JPM, Perform a Dropped Rod Recovery. Drop a (M) (A) (S) 1 second control rod thus requiring a reactor trip. (Use R0280160, Recover Misaligned Control Rod as a Guide)
B.2 Facility Walk-Through
- a. Sys. 068/JPM #S0610390, Pump Waste Holdup Tank (D) (R)
Contents to Unit 4 Containment
(
R 9
- b.
Sys. 062/JPM #N0030180, Transfer 4P07 Instrument bus (D) 6 from CVT to Inverter (Internal Transfer)
F
- c. Sys. O08/JPM #S0300090, Align Emergency Cooling (D) (R) 8 Water to the 4A Charging Pump F
- 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 Note: JPM's in BOLD and Italics are the five JPM's the SRO(U) applicants receive. RO and SRO(I) applicants receive all ten JPM's.
Operating Test Quality Checklist Form ES-301-3 Facility: Turkey Point Date of Examination: October 7-11, 02 Operating Test Number: 1
- 1. GENERAL CRITERIA
- 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).
- b.
There is no day-to-day repetition between this and other operating tests to be administered during this examination.
- c.
The operating test shall not duplicate items from the applicants' audit test(s)(see Section D.l.a).
- d.
Overlap with the written examination and between operating test categories 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 (CATEGORY A & B) CRITERIA
- a.
Each JPM includes the following, as applicable:
initial conditions initiating cues references and tools, including associated procedures 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 important observations to be made by the applicant
- criteria for successful completion of the task
- identification of critical steps and their associated performance standards
- restrictions on the sequence of steps, if applicable
- b.
The prescripted questions in Category A are predominantly open reference and meet the criteria rb A
in Attachment 1 of ES-301.
- c.
Repetition from operating tests used during the previous licensing examination is within rb A
acceptable limits (30% for the walk-through) and do not compromise test integrity.
Z
- d.
At least 20 percent of the JPMs on each test are new or significantly modified.
r" rb a
- 3. SIMULATOR (CATEGORY C) CRITERIA
- a.
The associated simulator operating tests (scenario sets) have been reviewed in accordance with
?
rbb Ya Form ES-301-4 and a copy is attached.
Pr' N
a I'mDate
- a. Author Glen Blende 9/9/02
- b. Facility Reviewer(*)
Richard Bretten 9/9/02
- c. NRC Chief Examiner (*)
MRon Aiello 10/01/02
- d. NRC Supervisor ()
Mike Erstes 7
4 L
a oz
(*) The facility signature is not applicable for NRC-developed tests; two independent NRC reviews are required.
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Turkey Point Date of Exam: October 7-11, 02 Scenario Numbers: 1 / 2 /
Operating Test No.:1 I QUALITATIVE ATTRIBUTES Initials a
b c
- 1.
The initial conditions are realistic, in that some equipment and/or instrumentation may be out of r
rab service, but it does not cue the operators into expected events.
- 2.
The scenarios consist mostly of related events.
r rab
- 3.
Each event description consists of r
ra, the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
- 4.
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario rb r4 without a credible preceding incident such as a seismic event.
- 5.
The events are valid with regard to physics and thermodynamics.
ra
- 6.
Sequencing and timing of events is reasonable, and allows the examination team to obtain rb re complete evaluation results commensurate with the scenario objectives.
- 7.
If time compression techniques are used, the scenario summary clearly so indicates. Operators rb rat have sufficient time to carry out expected activities without undue time constraints. Cues are given.
- 8.
The simulator modeling is not altered.
- rb ra
- 9.
The scenarios have been validated. Any open simulator performance deficiencies have been r 4 rab evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
'A
- 10.
Every operator will be evaluated using at least one new or significantly modified scenario. All rb ra*
other scenarios have been altered in accordance with Section D.4 of ES-301.
14
- 11.
All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit rb raA the form along with the simulator scenarios).
/45
- 12.
Each applicant will be significantly involved in the minimum number of transients and events rb raA specified on Form ES-301-5 (submit the form with the simulator scenarios).
5
- 13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
rr rbZ TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.4.D)
Actual Attributes
- 1.
Total malfunctions (5-8) 8
/ 8/7
'"rb ra
- 2.
Malfunctions after EOP entry (1-2) 2
/ 1 /2 4P raA
- 3.
Abnormal events (2-4) 5
/6
/4 rb ra'A
- 4.
Major transients (1-2) 1
/1 rb ra
- 5.
EOPs entered/requiring substantive actions (1-2) 2
/1 1
rb raI
- 6.
EOP contingencies requiring substantive actions (0-2) 2 0 10 rb rat;
- 7.
Critical tasks (2-3) 2
/ 4 /2 rb
ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.:
Instructions:
Aut,+e Chief Examine (1)
Enter the operating test number and Form ES-D-1 event numbers for each evolution type.
(2)
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.
A n ogloewolz-r:
ES-301 Competencies Checklist Form ES-301-6 AMPS ROD SOP Applicant #1 Applicant #2 Applicant #3 RO/SRO-I/SRO-U RO/SRO-I/SRO-U RO/SRO-I/SRO-U Competencies SCENARIO SCENARIO SCENARIO 1
2 3
1 2
3 1
2 3
2,S,4,5 1,2,3,4
,25,4,5 2,34-1,43,.'
34,S, 5,,,G
,2*S,,4 2,3,1,(5 Understand and Interpret 0
6,1,89 6,7,s 1,,9 7, S 9
g,7,ia9 7, Annunciators and Alarms z,S,4,$. 1,23.4 7,35,5 7,S,4,7,1,4,5, 5, -,4,2,z,4-Z,3,6,(
Diagnose Events 6,7,8,9 5,6,7,8 'Y,,
8,9 i-, 8 9
- ,ei,8 t,,9 and Conditions I,Z,.5,4-4,Z,a,,4 1,2,ý,,-
i,Z -,4 1,4,5,te, 3,4,,(5, 6,
Understand Plant 6,G,4,852,8
,7 5,e,7,
-7,S,9 1,9,4O 7,8,9 8,9
(@,
4,Z,,9 and System Response 9
9, AD 9
9,4o0 C,23.4 1,7,,"A-4,2,34 4,2z3,4 4,4.G,7 34,s.,%
,Z3,4 14,2,3,5 Comply With and 6,,7,8,9 5,,,9 08,9 AC0 7,e,9 9 1,9,7,8)9 Use Procedures (1) io I
0 I
1,Z,15,4 i4-s/,( 3,45. L,(
'- (.2,4,5 i,ZT.'
Operate Control 0:76
,O
,7
,9
&i,9,89 Boards (2) i I0 Communicate and 6,6,17,,
5,:,z,8 6,7,S,6,9
'7,5,4 4.h',
8,6/9 5,0,7* 7,'6,9 Interact With the Crew 9
9, A0 9,10 Demonstrate Supervisory
,7,,,8
',i,,
/-/A Ability (3) 9__
.)
Comply With and
$,4 43,
/
Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable 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.
tACf ti
(-
Chief Examiner:
Written Examination Quality Checklist Form ES-401-7 (R8, S1)
Facility:
,"tk:,
/2g'ar Date of Exam:
&/I e
"/at Exam Level: RO/SRO Initial Item Description a
b*
c#
- 1.
Questions and answers technically accurate and applicable to facility 4v-ril A
- 2.
- a. NRC K/As referenced for all questions
- b. Facility learning objectives referenced as available
- 3.
RO/SRO overlap is no more than 75 percent, and SRO questions are appropriate per
,Jtvo Section D.2.d of ES-401
- 1.
Question selection and duplication from the last two NRC licensing exams appears consistent with a systematic sampling process
- 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
_*~e 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 Bank Modified New AM percent from the bank at least 10 percent new, I
and the rest modified); enter the actual question 46/41 19/23 35/36 distribution at right
- 7.
Between 50 and 60 percent of the questions on Memory C/A the exam (including 10 new questions) are written at the comprehension/analysis level; 45/46 55/54 enter the actual question distribution at right
- 8.
References/handouts provided do not give away answers
- 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 ES, Appendix B, guidelines
)&
- 11.
The exam contains 100, one-point, multiple choice items; the total is correct and agrees with value on cover sheet Printed Name / Signature Date
- a. Author Steven D. Rose/*'-/**-
641*o~.
b. Facility Reviewer (*)
- '.vv
,-//
/*,' *
- c. NRC Chief Examiner (#)
r
- d. NRC Regional Supervisor *v" i/y
/10)* 4"f"..
- dj'
'*/_.*J 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 Written Examination Form ES-401-9 (R8, Si)
Review Worksheet for Turkey Point (Facility)
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
U/E/S Explanation Stem Cue T/F Cred. Partial Job-Minutia
- 1 Back-Q=
SRO Focus s
Dist.
Link units ward KJA 'Only Ir tructions
,ppendix B for ad itional information regarding each of the following concepts.]
- 1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
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).
- 4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
- 5.
Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6.
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. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
U/E/S Explanation Stem Cue T/F CredE.Partial Jo-Minutia
- /
Back-Q= ýSf0 Focus s
Dist.
Link units ward K/A Only I
LIA S
R 0)01AG2.4.tt 2
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
UIEIS Explanation Stem Cue TF Cred. Partial Job-IMinutia #/ Back-Q-=
SR Focus s
Dist.
Link units ward K/A Only R
2 H
3 001K4.20 2 R
3 H
3 S
003A2.02 1 Added "and close" to two responses to make them more in line with plant operations.
CE (rfa) Accept R
4 F
2 003AK1.02 I R
5 H
3 004K1.10 1 R
6 H
3 E
004K3.08 1 Question responses were incorrect as written. Letdown isolates and charging and seal injection flows increase due to charging pump (PD Pump) speed increase. Changes to Distractor Analysis.
CE (rfa) Accept S R 7
H 3
005AA1.05 1 Minor word changes to be more in line with plant terminology.
CE (rfa) Accept H
3 S
006K4.14 2 S R 9
H 2
007EK3.01 1 10 H
3 U
008AK2.01 1 Question has been rewritten. The original version was based on operator knowledge of the power supply to a specific MOV. The new version is more operationally oriented. Changes to Distractor Analysis.
CE (rfa) Accept R
11 F
2 S
009EA1.12 1
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
Q#
LOK LOD (F/H)
(1-5)
U/E/S Explanation Stem Cuef T/F Cred. Partial Job-Minutia
- /
Back-Q= SRO Focus s
Dist.
Link unts wardI K/A Only R
12 H
4 S
o1oK3.03 1 Change in stem clarifies the malfunction is associated with PC-4-444J vs. other control components. Additionally the actions stated in the stem were not in accordance with applicable ONOP-041.5.
CE (rfa) Accept R
13 H
3 OI011A3.03 2 Replaced original question. No correct answer and too close to common question # 6 (KA 004K3.08).
NOTE: The instrument air system failure has affected the LCS by its impact on charging and letdown. Charging and letdown are integral parts of the LCS. Changes to Distractor Analysis.
CE (rfa) Accept R
14 F
2 011EK3.05 1 Minor change to emphasize the initial injection path which is in keeping with the intent of the question.
CE (rfa) Accept 15 F
2 S
- 2 50 R
15 F
2012K5.01 1
Minor wording changes to be more in line with plant terminology.
CE (rfa) Accept R
16 H
~013K5.O1 I
Revised to have the applicable Tech Spec be provided based on the complexity of the question. Note that providing the Tech Spec does not create a direct lookup because the applicant has to review the Tech Spec LCO statement and the accompanying foot notes and answering the question correctly is further contingent upon realizing the train/EDG dependency for which HHSI pump to choose.
CE (rfa) Accept 17 H
3 1
014K4.03 I
R
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
UEIS Explanation Stem Cue T/F Cred. Partial Job-Minutia
- 1 Back-Q= SRO Focus s
Dist.
Link units ward K/A Only R
18 H
4 E
015/017AA1.02 1 As written, the answer was not correct. Revised stem to make the answer correct per the applicable ONOP. Changes to Distractor Analysis.
CE (rfa) Accept R
19 H
3 E
015/017AK1.01 1 Question was confusing as written. Rewrote question to make it read better.
CE (rfa) Accept R
20 H
4 S
o15K.,0 1 R
21 F
2 016A4.02 1 R
22 H
3 S
017K6.01 1 Second bullet was removed because it was redundant.
Deleted RVLMS statement because with level being shown on RVLMS, the CET temps could not be superheated.
CE (rfa) Accept R
23 F
2 S
022A1.03 I R
24 H
4 S
022AA2.04 1 R
25 F
3 E
022K1.01 1 Responses revised to reflect PTN terminology and the fact that CRDM Coolers do not trip on Phase A. Changes to Distractor Analysis.
CE (rfa) Accept 26 H
3 S
025AK2.02 1
7.
Explanation R
026A4.05 1 Changed situation to a LOCA. As Written two distractors (B & D) could be construed as correct. Revised wording to ensure B & D are incorrect. Changes to Distractor Analysis.
CE (rfa)
R 027AK2.03 I Revised responses A and C to reflect controller output. Correct answer is "A". Correction made. Changes to Distractor Analysis.
CE (rfa) Accept R
028A1.01 1 Replaced question under the same KA. PTN no longer has provisions for use of a hydrogen recombiner. Changes to Distractor Analysis.
CE (rfa) Accept R
032AA1.01 I A Tech Spec. Reference will need to be made available to the applicant.
This Question is designed to be open reference. It tests an Action Statement that is > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AOT.
RW E
U E
327AA2.17 I
Explanation I36AA1.02 1 R )38EG2.1.7 I Revised because D. response was correct as written because there was no endpoint.
CE (rfa) Accept R
039K5.05 2 Rewrote question due to distractor ambiguity. Changes to Distractor Analysis.
CE (rfa) Accept R
045A1.05 1 Added the reactor does not trip to the stem. If the reactor trips immediately and SDTC actuates, response C. could be argued as correct. Changes to Distractor Analysis.
CE (rfa) Accept R 051AG2.1.08 I F 55EK3.02 2
055K3.01 1 Revision based on the stem describing a condition that would not exist during the transfer from spare to normal inverter.
CE (fla) Accept
%61AK1.01 I
061K6.01 1
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD Explanation (F/H)
(1-5)
U/WES Stem Cue T/F Cred. Partial Job-Minutia
- /
Back-Q= SRO Focus s
Dist.F Link units ward K/A Only R
45 H
4 U
062K2.01 2 The question assumes the unit is operating without a battery powering the DC Bus. The 3B Battery would be immediately replaced by the spare battery assuring the DC bus is always powered by a battery.
Please see the replacement question that satisfies the KA & cognitive level. Changes to Distractor Analysis.
CE (rfa) Accept R
46 F
3 E
0631<2.01 1 Corrected DC Bus titles.
CE (rfa) Accept 47 F
3 S
064K2.02 I R
48 F
3 E
067AK1.01 1 Could not locate a reference to support original question. Revised question per ONOP-016.10. Changes to Distractor Analysis.
CE (rfa) Accept R
49 F
2 068A3.02 1 The question has been replaced for two reasons. 1) As written, Distractor A was correct. 2) The question is double jeopardy with similar question, # 66 (common). The replacement question matches Mne KA and cognitive level. Changes to Distractor Analysis.
CE (afa) Accept R
51 H
3 S
068AA1.31 1 Minor change to match plant terminology.
CE (ira) Accept R
51 H
3 S
069AK2.03 1 Reference needed based on answer derived from Tech Spec and a TSPS.
R 52 H
3 072K3.01 1
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
U/ESExplanation Stem [Cue T/F Cred. Partial Job-Minutia
- /
Back-Q= SRO Focus i
Dst.
Link units ward K/A IOnly 53 H
3 S
073K1.01 1 R
54 H
4 S
07E20 1 R
55 H
4 S
075A2.01 I Revised waterfall heights to get 3B1 value off of the exact value that requires reactor trip.
CE (rfa) Accept R
56 F
S 076AA2.01 1 Added word "first* to the stem. Otherwise responses A. and D. can be argued as correct. Minor wording change to be consistent with plant terminology.
CE (rfa) Accept R
57 H
3 076K3.05 1 Modified stem. The situation is not related to ONOP-O50. This is an in operability issue not a loss of RHR issue.
CE (rfa) Accept R
58 H
4 S
078A4.01 I Made human factor improvements to make question clearer and more easily read.
CE (rfa) Accept R
59 F
2 103A3.01 1 Removed word "complete" to clarify the stem CE (rfa) Accept R
60 F
3 S
G2.1.22 2 Revised question to make it more operationally oriented and to more closely fit the KA. Changes to Distractor Analysis.
CE (rfa Accept
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
U/E/SExplanation Stem Cue T/F Cred. Partial Job-Minutia
- 1 Back-Q=
SRO Focus s
I st.
Link units ward K/A Only R
61 H
4 G2.1.29 1 Added Distractor Analysis.
CE (rfa) Accept R
62 H
4 S
G2.1.32 1 Revised stem. Otherwise applicant would be required to know how many detectors exist in Containment. Added Distractor Analysis.
CE (rfa) Accept 63 H
3 S
G2.2.01 2 R
64 H
4 U
G2.2.11 1 Replaced question. This question was technically correct. However, with the exception of the NPS, Operations has minimal involvement with TSAs and operators do not sponsor TSAs. As written, this was an SRO only question. Changes to Distractor Analysis.
CE (rfa) Accept 65 H
3 S
G2.3.01 1 R
66 H
4 E
G2.3.11 1 Two responses revised due to two right answers on original question.
Response D. was also correct. When the Circ. Water Pump trips, the discharge MOV doses and the release is isolated via the seal well solenoids per EWD. Changes to Distractor Analysis.
CE (rfa) Accept 67 H
4 S
G2.4.091 3G2.4.20 1 68 H
3 S
I R
69 H
4 S
W/E02EAI.1 1 R
70 F
3 S
W/E03EK3.1 I
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other]
- 6.
- 7.
Q#
LOK LOD Explanation (F/H)
(1-5)
UIEISEplnto Is ira I
LTM
,=S Stem Cue T/F Cred. Partial Job-Minutia
- /
Back-71 H
4E E
W/E09EG2.4.48 I Added additional information in the stem to make response D the only correct answer. Revised responses to improve symmetry and readability. Changes to Distractor Analysis.
CE (rfa) Accept R
72 H
3 S
WIE11 EG2.4.18 1 Added one word to Response D to improve distractor symmetry.
CE (rfa) Accept S
S W/E12EK1.3 1 Could not find a firm basis for B. as the correct answer. Revised question to make cooldown rate > 1 00°/hr to ensure only one correct answer. Changes to Distractor Analysis.
ICF (rfa* Accent C Rf)Acp W/E13EA2.1 1 Minor revisions to incorporate plant specific terminology.
CE (rfa) Accept I
I I
IR W/E15EK3.1 1 Minor revisions to incorporate plant specific terminology.
CE (rfa) Accept 73 I H 3
75 F r 2 I
I I
I I
I R%
E r74 1 H 4 IR
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
Q#
LOK LOD Explanation (F/H)
(1-5)
UIE/S Stem Cue lTIF Cred. Partial Job-Minutia X# Back-Q=
0 SRO Focus s
Dist.
Link units ward K/A Only R
2 H
4 S
002A2.04 (S) 2 Revised response to be more in line with actual practice per ONOP-05O.
Changes to Distractor Analysis.
CE (rfa) Accept R
3 H
4 E
003G2.1.20 (S) 1 Multiple correct answers as written because the stem does not define where the operators are in the procedure. Revised all responses to remove subjectivity regarding when procedure transition should be made and which actions may be performed early. Changes to Distractor Analysis.
CE (rfa) Accept R
4 H
4 005A2.04 (S) 2 Added temperature rising to allow exit from ONOP-05O.
Removed hot leg injection from answer. Attachment 2 does not dictate hot leg injection (original path development was incorrect).
CE (rfa) Accept R
5 H
3 S
013G2.4.9 (S) 1 R
6 F
3 S
024AA2.02 I Added valve titles.
CE (rfa) Accept R
7 H 4 R026AA2.02 (S) 1 Deleted tCCW head tank level slowly decreasing." because the stem bullet was ambiguous CE (rfa) Accept
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD Explanation (F/H)
(1-5)
UWEIS Stem Cue TIF red. fPartial Job-Minutia
- /
Back-Q= SRO Focusj s DIst.
Link units ward K/A Only R
8 F
3 033A2.03 (S) 1 Added "initial" because D. could be a correct action taken subsequently.
Added "potential" because until condition is verified valid, there may be no impact.
CE (rfa) Accept R
9 H
4 037AA2.16 1 051AA2.02 1 10 F
2 S
R 11 H
3 E
054AA2.01 1 Answer not correct as written. Only the affected S/G valve fast closes.
Revised all responses for consistency. Changes to Distractor Analysis.
CE (rfa) Accept R
12 H
4 S
058AG2.1.12 1 This question is designed to be open reference. Operators are not "required to memorize Action Statements > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Modified question to increase plausibility of distractors. Changes to Distractor Analysis.
CE (rfa) Accept R
13 H
4 E
062AA2.04 1 As written, there is no time to implement any actions except for prepare for the trip (2 minutes). Argument can be made that responses B, C, and D are correct.. Revised to more closely satisfy the KA. Changes to Distractor Analysis.
CE (rfa) Accept R
15 F
2 S
G2.1.06 1 Rearranged the stem to improve readability.
CE (rfa) Accept
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
Q4 LOK LOD (F/H)
(1-5)
U/E/S Explanation Stem Cue iT/F Cred. Partial Job-Minutia
- /
Back-Q= SRO Focus s
Dst.[
Link unitsI ward K/A Only R
16 H
2 S
G.2.1.09 2 Revised Response C. As written it is a subset of D and is therefore not wrong. Changes to Distractor Analysis.
CE (rfa) Accept 17 H
4 S
G2.1.12 (S) I R
18 H
3 S
G2.2.12 (S) 1 R
19 H
3 S
G2.3.10 (S) 2 Tech Spec. reference needed for this Tech Spec involving Action Statement > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Revised stem to include E-bar and gross activity value to improve plausibility of distractors. Changes to Distractor Analysis.
CE (rfa) Accept R
20 H
4~
S G2.4.08 1 R
21 H
3 S
G2.16 (S) I R
22 H
5*
S G2.4.41 1
- Reference required for this very difficult classification. Providing a reference would lower the difficulty level to a 4. Changes to Distractor Analysis.
CE (rfa) Accept R
23 F
2 W/E04EA2.1 I Changes to Distractor Analysis.
CE (rfa) Accept R
24 H
3 S
W/E0EA,.i 1
7.
Explanation
- V/E08EA2..1 I 01MA2
,10 1
D02A04 (R) I R
)R03G2.1.20(R) I Minor word changes to improve readability. Changes to Distractor Analysis.
CE (rfa) Accept R
005A2.02 1 "This is the same question as #67 on the common exam. See replacement that satisfies the KA and cognitive level. Changes to Distractor Analysis.
CE (rfa) Accept R
005A2.04 (R) 1 R
01G..
RThis question was too easy as written. See the revision that meets the required KA and cognitive level. Changes to Distractor Analysis.
CE (rfa) Accept R
015A3.03 2 Middle of the IR is too vague. 1% on the power range is equivalent to 2 decades prompt drop. Changes to Distractor Analysis.
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
UJEIS Explanation Stem Cue FCred Partial Job-Minutia
- 1 Back-Q=
SRO Focus s
Dist.
Link units ward K/A Only R
9 F
2 S
033A2.03 (R) 2 Changed "correct" to "initial" because A. could be a correct action taken subsequently.
CE (rfa) Accept R
10 F
4 S
033G2.2.3 1 Minor wording changes based on plant specific terminology.
CE (rfa) Accept R
11 H
4 E
056K1.03 1 No correct answer as written. Revised to give correct answer. Refer to Logic diagram, Sheet 25. Changes to Distractor Analysis.
CE (rfa) Accept R
12 F
4058AA2.03 1
Changed B distractor - Operators are not expected to know whether A or B Train MSIV solenoids deenergize upon a loss of 3D23. Changes to Distractor Analysis.
CE (rfa) Accept R
13 F
2 059A1.03 2 Changes to Distractor Analysis.
CE (rfa) Accept R
14 H
4 059A4.08 1 Replaced B. distractor with one that is more plausible. CV-2900 does not have a diaphragm. Changes to Distractor Analysis.
CE (rfa) Accept
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD (FIH)
(1-5)
U/E/S Explanation Sterm Cue T/F Cred. Partial Job-Minutia
- /
Back-Q=
SRO Focus s
Dist.
Link [
units ward KIA Only R
15 H
4 U
061 K4.02 2 This question tests the same knowledge as Common Q#69. Please see the new question testing the same KA at the same cognitive level.
Changes to Distractor Analysis.
CE (rfa) Accept R
16 F
3 S
068A2.02 1 The liquid release procedure does not refer to the samples as "grab" samples.
CE (rfa) Accept R
17 H
3 S
071 G2.4.10 (R) 2 R
18 H*
3 E
071K4.05 1 Revised question. Operators are not expected to know the power supplies to these non-safety related plant components.
- Revision is at the Fundamental level. Changes to Distractor Analysis.
CE (rfa) Accept R
19 H
4 S
076K3.01 1 R
20 H
3 086A4.06 1 Revised two distractors. Operators are not expected to memorize local panel numbers (286 vs 288).
CE (rfa) Accept R
21 F
3 S
G2.1.12 (R) 1 Minor word changes to improve readability.
CE (rfa) Accept R
22 H
4 S
G2.2.12 (R) 1 I Identified the References to be provided.
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 7.
U/QKS Explanation Se Cue T/F Cred. Partial Job-Minutia
- /
Back-Q=
SRO Focs si iD
- t.
Lik unitsi ward K/A only 23 H
5U G2.3.10 (R) 1 Revised Q to remove DAC component. Operators are not responsible for DAC calculations. See revised question of equal cognitive level and appropriate difficulty level.
New difficulty level = 4. Changes to Distractor Analysis.
CE (df) Accept 24 F
3 S
G.2.4.16 (R) 1 25 F
2 W/E04EA2.2 1
Quality Checklist Facility:
Turkey Point Date of Exam:
10/15/02 Exam Level:jO&k Initials Item Description a
b c
- 1.
Clean answer sheets copied before grading rf rs
- 2.
Answer key changes and question deletions justified and N/A N/A documented
- 3.
Applicants' scores checked for addition errors rfa\\l (reviewers spot check > 25% of examinations)
- 4.
Grading for all borderline cases (80% +/- 2%) reviewed in N/A N/A detail
- 5.
All other failing examinations checked to ensure that grades N/A N/A are justified
- 6.
Performance on missed questions checked for training rfrsb deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name / Signature Date
- a. Grader Ronald F. Aiello /
ge_
10/30/02
- b. Facility Reviewer(*)
N/A N/A
- c. NRC Chief Examiner (*) Richard S. Baldwin_
10/30/02
- d. NRC Supervisor (*)
njci-iegt F. C/,srtzrOZ4 '-*
l/co
(*)
The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
NUREG-1021, Revision 8, Supplement 1 Form ES-403-1 Written Examination Grading ES-403
ES-501 Ps-xmnto hc he omE-a-Turkey Point Nuclear Station Task Description Date Complete
- 1.
Facility written exam comments or graded exams received and 10/30/02 verified complete
- 2.
Facility written exam comments reviewed and incorporated and 11/04/02 NRC grading completed, if necessary
- 3.
Operating tests graded by NRC examiners 10/30/02
- 4.
NRC Chief examiner review of written exam and operating test 10/30/02 grading completed
- 5.
Responsible supervisor review completed 11/04/02
- 6.
Management (licensing official) review completed 11/04/02
- 7.
License and denial letters mailed 11/06/02
- 8.
Facility notified of results 11/08/02
- 9.
Examination report issued (refer to NRC MC 0610) 11/07/02
- 10.
Reference material returned after final resolution of any appeals N/A Form ES-501-1 Post-Examination Check Sheet FR-501
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, SI)
Facility: Turkey Point Date of Exam: 10/14/2002 Exam Level: SRO K/A Category Points Tier Group K
K K
K K
K A
A2 A
A G
Total 1
2 3
4 5
6 1
3 4
- 1.
1 4
2 3
%4 7
24 Emergency&
2 1
3 2
j 2
6 2
16 Abnormal Plant Evolutions 3
Tier Totals 5T5 1
6 1
2 2
7 14 2121 2
6 21 21 3 43 19
- 2.
2 1
2 3
1 2
1 3
2 2
17 Plant Systems 3
1 1
1 1
4 Tier 3
2 6
3 3
2 3
6 4
5 3
40 Totals
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat4 1
=Z;Z6 13 3
[i5q 17 Note: 1.
Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4.
Systems/evolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the category/tier.
6.*
The generic 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.
- 7.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
PWR SRO Examination Outline Form ES-401-3 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier i/Group 1 EIAPE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic s)
Imp.
Points 000001 Continuous Rod Withdrawal / 1 4.12 AG2.4.12 General operating crew responsibilities during emergency 3.413.9 operations 000003 Dropped Control Rod I 1 02 AKi.02 Effects of turbine-reactor power mismatch on rod control 3.1/3.4 000005 Inoperable/Stuck Control Rod 11 05 AAi.05 RPI 3.4/3.4 000011 Large Break LOCA /3 05 EK3.05 Injection into cold leg 4.0/4.1 W/E04 LOCA Outside Containment / 3 2
EA2.2 Adherence to appriate procedures and operation within the 3.6/4.2 S/R limitations in the facility s license and amendments W/EOI & E02 Rediagnosis & SI Termination 3 1
EAI.1 Components and functions of control and safety systems, 4.0/3.9 including instrumenfation, signals, interlocks, failure modes, and automafic and manual features 000015117 RCP Malfunctions / 4 01 AKI.01 Natural circulation in a nuclear power plant 4.4/4.6 000015/17 RCP Malfunctions/ 4 02 AA1.02 RCP oil reservoir level and alarm indicators 2.8/2.7 BW/E09; CE/Ai 3; W/E09&E10 Natural Circ./ 4 4.49 EG2.4.49 Perform without reference to procedures those actions that 4.0/4.0 1 require immediate operation of system components and controls 000024 Emergency Boration / 1
- 2a AA2.02 When use of manual boration valve is needed 3.9/4.4 SRO 000026 Loss of Component Cooling Water / 8 02A AA2.02 The cause of possible CCW loss 2.9/3.6 S/R 000029 Anticipated Transient w/o Scram / 1 4.34 AG2'4 34 Knowledge of RO tasks performed outside the main control 3.8/3.6 room durn emergency operations including system geography and s stem impications 000040 (BW/E05; CE/E05
- W/E12) Steam Line EK1.3 Annunciators and conditions indicating signals, and remedial 3.413.7 ct-inns assnctiAtd with the (Uncontrolled Depressurization of all Rupture'- Excessive Heat Transfer / 4 CE/A1 1; W/E08 RCS Overcooling - PTS / 4 000051 Loss of Condenser Vacuum / 4 000055 Station Blackout / 6 000057 Loss of Vital AC Elec. Inst. Bus / 6 000059 Accidental Liquid RadWaste Rel. /9 000062 Loss of Nuclear Service Water / 4 000067 Plant Fire On-site / 9 m
02 01 7
1 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity IS 03 1.08
ý,03
,'04 t31 Steam Generators) duA? 1 F acilit cond tion s anedselectiontofnappropriate procedures during abnormal and emergency operations AG2.1.8 Coordinate personnel activities outside the control room EK3.02 Actions contained in EOP for loss of offsite and onsite power EK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus AA2.03 Failure modes, their symptoms, and the causes of misleading indications on a radioactive-
'u'dindication AA2.04 The normal values and upper limits for the temperatures of the components cooled by SWS AKi.01 Fire classifications, by type A1.31 ED/G AK2.03 Personnel access hatch and emergency access hatch 3.4/4.2 SRO 3.8/3.6 4.3/4.6 4.1/4.4 3.1/3.6 2.5/2.9 2.9/3.9 SRO SRO 3.4/4.2 SRO 01 3.9/4.0 2.8/2.9 I
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, $1)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000074 (W/E06&E07) Inad. Core Cooling / 4 06 AK2.06 Turbine bypass and atmospheric dump valves 3.5/3.6 BW/E03 Inadequate Subcooling Margin / 4 000076 High Reactor Coolant Activity / 9 04 AA2.04 Process effluent radiation chart recorder 2.6/3.0 BW/A02&A03 Loss of NNI-XN / 7 K/A Category Totals:
jT4 I2 3 1 4
7 4
1 Group Point Total:
j24
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier I/Group 2 E/APE # / Name / Safety Function Ki K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000007 (BW/E02&EI0; CE/E02) Reactor Trip -
01 EK3.0l Actions contained in EOP for reactor trip 4.0/4-6 Stabilizae ion - Recovery /1 BW/A01 Plant Runback / 1 BW/A04 Turbine Trip / 4 000008 Pressurizer Vapor Space Accident / 3 01 AK2.01 Valves 2.7/2.7 000009 Small Break LOCA / 3 12 EA1.12 RPS 4.2/4.2 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 1
EK3.1 Facilit operating characteristics during transient conditions, 3.3/3.7 including coolant chemistr and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these opereIng characteristics W/E1 1 Loss of Emergency Coolant Recirc. / 4 2.11 EG2.2.11 Process for controlling temperature changes 2.5/3.4 000022 Loss of Reactor Coolant Makeup / 2 04 AA2.04 How long PZR level can be maintained within limits 2.9/3.8 000025 Loss of RHR System / 4 02 AK2.02 LPI or decay heat removal/RHR pumps 3.2/3.2 000027 Pressurizer Pressure Control System 03 AK2.03 Controllers and positioners 2.6/2.8 Malfunction / 3 000027 Pressurizer Pressure Control System 17 AA2.17 Allowable RCS temperature difference vs. reactor power 3.1/3.3 Malfunction / 3 000032 Loss of Source Range NI / 7 01 AA1.01 Manual restoration of power 3.1/3.4 000033 Loss of Intermediate Range NI / 7 1
000037 Steam Generator Tube Leak / 3 16 AA2.16 Pressure at which to maintain RCS during S/G cooldown 4.1/4.3 SRO 000038 Steam Generator Tube Rupture / 3 1.19 E02.1.19 Use plant computer to obtain and evaluate parametric 3.0/3.0 information on system or component status 000054 (CE/E06) Loss of Main Feedwater / 4 0,14 AA2.01 Occurrence of reactor and/or turbine trip 4.3/4.4 SRO BW/E04 W/E05 Inadequate Heat Transfer - Loss EA2.1 Facility conditions and selection of appropriate procedures 3.4/4.4 SRO of Secondary Heat Sink / 4 during abnormal and emergency operations 000058 Loss of DC Power/ 6 AA2.01 That a loss of dc power has occurred; verification that 3.7/4.1 S/R substitute power sources have come on line 000060 Accidental Gaseous Radwaste Rel. /9 000061 ARM System Alarms / 7 01 AKI.01 Detector limitations 2.5/2.9 W/E16 High Containment Radiation /9 000065 Loss of Instrument Air / 8 K ACategoryPointTotals:
11 3 12 12 16 2 J Group Point Total:
16
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE 4*/Name / Safety Function K1 K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000028 Pressurizer Level Malfunction /2 000036 (BWIA08) Fuel Handling Accident 18 02 AA1.02 ARM system 3.1/3.5 000056 Loss of Off-site Power / 6 BW/E13&E14 EOP Rules and Enclosures BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 CEIA16 Excess RCS Leakage / 2 W/E13 Steam Generator Over-pressure 14 2
EA2.2 Adherence to appropriate procedures and operation within the 3.0/3.4 limitations in the facilityes license and amendments W/E1 5 Containment Flooding /5 1
EK3.1 Facility operating characteristics during transient conditions, 2.7/2.9 including coo ant chemist and the effects of temperature, pressure, and reactivity changes ana operating limitations and reasons for these operating charactenstics K/ACategory Point Totals:
I I 1
111 JGroup Point Total:
J 3
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)
Plant Systems - Tier 2/Group 1 f!__
System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 001 Control Rod Drive 20 K4.20 The permissives and interlocks 3.2/3.4 associated with increase from zero power 001 Control Rod Drive
[,9P A2.09 Station blackout 3.814.0 SIR 003 Reactor Coolant Pump 02 A2.02 Conditions which exist for 3.7/3.9 abnormal S/D of a RCP in comparison to a normal S/D of a RCP 003 Reactor Coolant Pump 1.2120 G2.1.20 Execute procedure steps 4.3/4.2 S/R 004 Chemical and Volume Control 10 K1.10 Pneumatic valves and RHRS 2.7/2.9 004 Chemical and Volume Control 08 K3.08 RCP seal injection 3.6/3.8 013 Engineered Safety Features Actuation 01 K5.01 Definitions of safety train and ESF 2.8/3.2 channel 013 Engineered Safety Features Actuation
?4. 9, G2.4.9 Low power / shutdown 3.3/3.9 S/R
-4w, <
implications in accident (e.g. LOCA or S>
loss of RHR) mitigation strateLies 014 Rod Position Indication 03 K4.03 Rod bottom lights 3.213.4 015 Nuclear Instrumentation 01 K6.01 Sensors, detectors, and indicators 2.9/3.2 017 In-core Temperature Monitor 01 A3.01 Indications of normal natural, and 3.6/3.8 interrupted circulation of RdS 022 Containment Cooling 01 K1.01 SWS/cooling system 3.5/3.7 022 Containment Cooling 03 1
A1.03 Containment humidity 3.1/3.4 025 Ice Condenser 026 Containment Spray 05 A4.05 Containment spray reset switches 3.5/3.5 056 Condensate 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 01 K6.01 Controllers and positioners 2.5/2.8 1 063 DC Electrical Distribution 03 A4.03 Battery discharge rate 3.0/3.1 068 Liquid Radwaste 02 A3.02 Automatic isolation 3.6/3.6 0 Wt a07e i G2.4.10 Annunciator response 3.0/3.1 S/R 071 Waste Gas Disposal procedures 072 Area Radiation Monitoring 01 K3.01 Containment ventilation isolation 3.2/3.4 K/A Category Point Totals:
=2
=
j 2
212 1j2 iJ2 2
12 3 1 GroupPointTotal:
19
ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)
Plant Systems - Tier 2/Group 2 System #/ Name K1 K2 K3 K4 K5 K6 IAl A2 A3 A4 G
KIA Topic(s)
Imp.
Points 002 Reactor Coolant 04 A2.04 Loss of heat sinks 4.3/4.6 SIR 006 Emergency Core Cooling 14 K4.14 Cross-connection of HPIILPI/SIP 3.9/4.2 010 Pressurizer Pressure Control 03 K3.03 ESFAS 4.0/4.2 011 Pressurizer Level Control 01 A3.01 Boration/dilution 2.8/2.8 012 Reactor Protection 01 K5.01 DNB 3.3/3.8 016 Non-nuclear Instrumentation 02 A4.02 Recorders 2.7/2.6 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 01 A1.01 Hydrogen concentration 3.4/3.8 029 Containment Purge 02 K3.02 Containment entry 2.9/3.5 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 01 A4.01 Shift of S/G controls between manual 3.7/3.6 and automatic control, by bumpless transfer 039 Main and Reheat Steam 05 K5.05 Bases for RCS cooldown limits 2.7/3.1 055 Condenser Air Removal 01 1
K3.01 Main condenser 2.5/2.7 062 AC Electrical Distribution 01 1
K2.01 Major system loads 3.3/3.4 064 Emergency Diesel Generator 02 K2.02 Fuel oil pumps 2.8/3.1 073 Process Radiation Monitoring 01 K1.01 Those systems served by PRMs 3.6/3.9 075 Circulating Water 01 A2.01 Loss of intake structure 3.0/3.2 079 Station Air
[41 A2.01 Cross-connection with IAS 2.9/3.2 S/R 086 Fire Protection 103 Containment 01 A3.01 Containment isolation 3.9/4.2 IA Category Point Totals:
J1121 3
2 1
321 212 IGroup Point Total:
I17
ES-4O1 PWR SRO Examination Outline Form ES-401-3 (RS, Si)
Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 005 Residual Heat Removal A2.04 RHR valve malfunction 2.9/2.9 SIR 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 05 A1.05 Expected response of primary plant 3.8/4.1
? arameters (temperature and pressure)
[ollowing T2G trip 076 Service Water 07 K3.07 ESF loads 3.7/3.9 078 Instrument Air 01 A4.01 Pressure gauges 3.1/3.1 K/A Category Point Totals:
I1I11.. L j..tl
.l LJ I Group Point Total:
4 Plant-Specific Priorities System I Topic Recommended Replacement for...
Reason Points Plant-Specific Priority Total: (limit 10)
I
f*1 flarir Knowledge, and Abilities Outline (Tier 3)
Fr S415(8 I
ES-40 P~~~- --
- ,~i
'n l
n hlte Ouln-(ir3 r..^.;I;:,,,. Ti mr'L,'o,t lPnin" Fdt.IIIL rDate of Exam: 10/14/2002 Exam Level: SRO y:
urIIL Category Conduct of Operations Equipment Control K/A#
Topic Imp.
- I Ah.1IW1 Apolv technical specifications for a system 2.9/4.0 Points S/R 2.1.29 How to conduct and verify valve lineups 3.4/3.4 2.1.32 Explain and apply all sys limits and precautions 3.4/3.8 2.1.22 Determine mode of operation 2.8/3.3 Supervise and assume a management role during 2.1/4.3 SRO plant transients 2;.1 09t Direct personnel activities inside the control room 2.5/4.0 SRO Total 6
Surveillance procedures 3.0/3.4 SIR 2.2.04 Explain the variations in CB layouts, systems, 2.8/3.0 instr, and procedural actions between units 2.2.01 Perform pre-startup procedures for the facility, 3.7/3.6 including operating those controls associated with plant equipment that could affect reactivity Total I_
Radiation Control Emergency Procedures/
Plan 2.3.01 23107 10 CFR: 20 and related facility radiation control requirements Perform procedures to reduce excessive levels of radiation and auard against personnel exposure 2.6/3.0 2.9/3.3 S/R 2.3.11 Control radiation releases 2.7/3.2 Total 3
2.4.4 Emer action level thresholds and classifications 2.3/4.1 SRO 2.4.15 Communication procedures associated with EOP 3.0/3.5 implementation 2.4.20 Total Operational implications of EOP warnings, cautions and notes EOP implementation hierarchy and coordination with other support procedures How the event based emergency/abnormal operating procedures are used in conjunction with symptom based EOPs 3.3/4.0 3.0/4.0 3.0/3.7 S/R SRO 5
17 Tier 3 Point Total (SRO)
Form ES-401-5 (R8, S1)
- 4 3
PWR RO Examination Outline Facility: Turkey Point Date of Exam: 10/14/2002 Exam Level: RO K/A Category Points Tier Group iiiPoint K
K K
K K
K A
A G
Total 1
2 3
4 5
6 1
2 3
4 Emergency&
2
&4 Abnormal 2
2 2
3 3
3 4
1 Plant 3
11 1
3 Evolutions Tier 5
5 6
17 71 6
36 Totals 1
3 1
2 2
1 2
2 3
3 1
3 23
- 2.
Plant 2
1 2
3 2
2 3
2 5
20 Systems 3
2
_t 2
8_
8 Tier 4
3 7
4 3
2 4
8 6
7 3
51 Totals
- 3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 I 4 3
3_
3 13 Note:
- 1.
Ensure that at (east two topics from every K/A category are sampled within each tier (i.e., 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 +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4.
Systems/evolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the category/tier.
6V The generic 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.
- 7.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, 81)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # I Name I Safety Function K1 K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000005 Inoperable/Stuck Control Rod/ 1 05 AA1.05 RPI 3.4/3.4 000015/17 RCP Malfunctions /4 01 AKI.01 Natural circulation in a nuclear power plant 4.4/4.6 000015117 RCP Malfunctions /4 02 AA1.02 RCP oil reservoir level and alarm indicators 2.8/2.7 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 4.49 EG2.4.49 Perform without reference to procedures those actions that 4.0/4.0 require immediate operation of system components and controls 000024 Emergency Boration / I 000026 Loss of Component Cooling Water / 8 AA2.02 The cause of possible CCW loss 2.9/3.6 SIR 000027 Pressurizer Pressure Control System 03 AK2.03 Controllers and positioners 2.6/2.8 Malfunction / 3 000027 Pressurizer Pressure Control System 17 AA2.17 Allowable RCS temperature difference vs. reactor power 3.1/3.3 Malfunction /3 000040 (BW/E05; CE/E05; W/E12) Steam Line 3
EK1.3 Annunciators and conditions indicating signals, and remedial 3.4/3.7 Rupture - Excessive Heat transfer / 4 actions associated with the (Uncontrolled Depressurization of all Steam Generators)
CE/A 1; W/E08 RCS Overcooling - PTS / 4 000051 Loss of Condenser Vacuum /4 1.08 AG2.1.8 Coordinate personnel activities outside the control room 3.8/3.6 000055 Station Blackout / 6 02 EK3.02 Actions contained in EOP for loss of offsite and onsite power 4.3/4.6 000057 Loss of Vital AC Elec. Inst. Bus /6 01 EK3.01 Actions contained in EOP for loss of vital ac electrical 4.1/4.4 instrument bus 000062 Loss of Nuclear Service Water / 4 000067 Plant Fire On-site / 9 01 AK1.01 Fire classifications, by type 2.9/3.9 000068 (BW/A06) Control Room Evac. / 8 31 AA1.31 ED/G 3.9/4.0 000069 (W/E14) Loss of CTMT Integrity / 5 03 AK2.03 Personnel access hatch and emergency access hatch 2.8/2.9 000074 (N/E06&E07) Inad. Core Cooling / 4 06 AK2.06 Turbine bypass and atmospheric dump valves 3.5/3.6 BW/E03 Inadequate Subcooling Margin / 4 000076 High Reactor Coolant Activity /9 04 AA2.04 Process effluent radiation chart recorder 2.6/3.0 BW/A02&AO3 Loss of NNI-XN / 7 K/A Category Totals:
1 3 J 2
3 3
2 1 Group Point Total:
[16
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000001 Continuous Rod Withdrawal/ 1 4.12 AG2.4.12 General operating crew responsibilities during emergency 3.4/3.9 operations I
000003 Dropped Control RodI 1 02 AK1.02 Effects of turbine-reactor power mismatch on rod control 3.1/3.4 000007 (.W/EO2&E10; CEIE02) Reactor Trip -
01 EK3.01 Actions contained in EOP for reactor trip 4.0/4.6 Stabilizat on - Recovery /1 BW/A01 Plant Runback 11 BW/A04 Turbine Trip / 4 000008 Pressurizer Vapor Space Accident / 3 01 AK2.01 Valves 2.7/2.7 000009 Small Break LOCA 13 12 EA1.12 RPS 4.2/4.2 000011 Large Break LOCA / 3 05 EK3.05 Injection into cold leg 4.0/4.1 W/E04 LOCA Outside Containment / 3 EA2.2 Adherence to approprate procedures and operation within the 3.6/4.2 SIR limitations in the facility s license and amendments BW/E08; W/E03 LOCA Cooldown/Depress. / 4 1
EK3.1 Facility operating characteristics during transient conditions, 3.3/3.7 including coo ant chemistry and the effects o temperature, pressure, and reactivity changes ana operating limitations and reasons for these operanng characteristics W/El 1 Loss of Emergency Coolant Recirc. 14 2.11 EG2.2.11 Process for controlling temperature changes 2.5/3.4 WIEO1 & E02 Rediagnosis & SI Termination / 3 1
EA1.1 Components and functions of control and safety systems, 4.0/3.9 including instrumentation, signals, interlocks, failure modes, and automauic and manual features 000022 Loss of Reactor Coolant Makeup / 2 04 AA2.04 How long PZR level can be maintained within limits 2.9/3.8 000025 Loss of RHR System /4 02 AK2.02 LPI or decay heat removal/RHR pumps 3.2/3.2 000029 Anticipated Transient w/o Scram / 1 4.34 AG2.4.34 Knowledge of RO tasks performed outside the main control 3.8/3.6 room durina emergency operations including system geography and system imp ications 000032 Loss of Source Range NI / 7 01 AA1.01 Manual restoration of power 3.1/3.4 000033 Loss of Intermediate Range NI / 7 000037 Steam Generator Tube Leak / 3 000038 Steam Generator Tube Rupture / 3 1.19 EG2.1.19 Use plant computer to obtain and evaluate parametric 3.0/3.0 information on system or component status 000054 (CE/E06) Loss of Main Feedwater / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink /4 000058 Loss of DC Power /6 O<
AA2.01 That a loss of dc power has occurred; verification that 3.7/4.1 SIR substitute power sourcesnhave come on line 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. /19-
000061 ARM System Alarms 17 01 AKI.01 Detector limitations 2.5/2.9 WIE16 High Containment Radiation 19 CE/E09 Functional Recovery KIA Cateoy Point Totals:
I2 2
3 I3 3 4
Group PointTotal:
17
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, $1)
Emergency and Abnormal Plant Evolutions - Tier I/Group 3 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000028 Pressurizer Level Malfunction / 2 000036 (BW/A08) Fuel Handling Accident / 8 02 AA1.02 ARM system 3.1/3.5 000056 Loss of Off-site Power / 6 000065 Loss of Instrument Air /8 BW/E13&E14 EOP Rules and Enclosures BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 CE/A 6 Excess RCS Leakage / 2 W/E13 Steam Generator Over-pressure / 4 2
EA2.2 Adherence to appropriate procedures and operation within the 3.0/3.4 limitations in the facility s license and amendments W/E15 Containment Flooding / 5 EK3.1 Facility operating characteristics durinn transient conditions, 2.7/2.9 including coo ant chemistr and the effects o temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics K/A Category Point Totals:
i LLI 1111 i Group Point Total:
13
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)
Plant Systems - Tier 2/Group 1 System # I Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 001 Control Rod Drive 20 K4.20 The permissives and interlocks 3.2/3.4 associated with increase from zero power 001 Control Rod Drive 09, A2.09 Station blackout 3.8/4.0 SIR 003 Reactor Coolant Pump 02 A2.02 Conditions which exist for 3.713.9 abnormal S/D of a RCP in comparison to a normal SID of a RCP 003 Reactor Coolant Pump 1t20>
G2.1.20 Execute procedure steps 4.3/4.2 SIR 004 Chemical and Volume Control 10 K1.10 Pneumatic valves and RHRS 2.7/2.9 004 Chemical and Volume Control 08 K3.08 RCP seal injection 3.6/3.8 013 Engineered Safety Features Actuation 01 K5.01 Definitions of safety train and ESF 2.8/3.2 channel 013 Engineered Safety Features Actuation LTýg2ý G2.4.9 ow power / shutdown 3.3/3.9 SIR t
implications in accident (e.g. LOCA or
÷__
_ _._ loss of RHR) mitigation strategies 015 Nuclear Instrumentation 01 K6.01 Sensors, detectors, and indicators 2.9/3.2 015 Nuclear Instrumentation 0
A3.03 Verification of proper 3.9/3.9 RO F
functioning/operability 017 In-core Temperature Monitor 01 A3.01 Indications of normal, natural, and 3.6/3.8 interrupted circulation of RCS 022 Containment Cooling 01 K1.01 SWS/cooling system 3.5/3.7 022 Containment Cooling 03 A1.03 Containment humidity 3.1/3.4 025 Ice Condenser 056 Condensate 03 1
KI.03 MFW 2.6/2.6 RO 059 Main Feedwater 07 A1.07 Feed pump speed, including 2.5/2.6 RO normal contro speed for CS 059 Main Feedwater 08 A4.08 Feed regulating valve controller 3.0/2.9 RO 061 Auxiliary/Emergency Feedwater 01 K6.01 Controllers and positioners 2.5/2.8 061 Auxiliary/Emergency Feedwater K0 K2.03 AFW diesel driven pump 4.0/3.8 RO 068 Liquid Radwaste 02 A3.02 Automatic isolation 3.6/3.6 068 Liquid Radwaste A2.02 Lack of tank recirculation prior to 2.7/2.8 RO release
071 Waste Gas Disposal O5 K4.05 Point of release 2.7/3.0 Y E 071 Waste Gas Disposal 4
G2.4.10 Annunciator response 3.0/3.1 SIR procedures 072 Area Radiation Monitoring 01 K3.01 Containment ventilation isolation 3.2/3.4 K/A Category Point Totals:
LI---
F3 11 2
2 i11 2
II2 IZ3 F3 1 3
I Group Point Total:
I 23
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)
Plant Systems - Tier 2/Group 2 1
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 002 Reactor Coolant 04 A2.04 Loss of heat sinks 4.3/4.6 SIR 006 Emergency Core Cooling 14 K4.14 Cross-connection of HPI/LPI/SIP 3.9/4.2 010 Pressurizer Pressure Control 03 K3.03 ESFAS 4.0/4.2 011 Pressurizer Level Control 01 A3.01 Boration/dilution 2.8/2.8 012 Reactor Protection 01 K5.01 DNB 3.3/3.8 014 Rod Position Indication 03 K4.03 Rod bottom lights 3.2/3.4 016 Non-nuclear Instrumentation 02 A4.02 Recorders 2.7/2.6 026 Containment Spray 05 A4.05 Containment spray reset switches 3.5/3.5 029 Containment Purge 02 K3.02 Containment entry 2.9/3.5 033 Spent Fuel Pool Cooling "02 A3.02 Spent fuel leak or rupture 2.9/3.1 RO 035 Steam Generator 01 A4.01 Shift of S/G controls between manual 3.7/3.6 and automatic control, by bumpless transfer 039 Main and Reheat Steam 05 K5.05 Bases for RCS cooldown limits 2.7/3.1 055 Condenser Air Removal 01 K3.01 Main condenser 2.5/2.7 062 AC Electrical Distribution 01 K2.01 Major system loads 3.3/3.4 063 DC Electrical Distribution 1
03 A4.03 Battery discharge rate 3.0/3.1 064 Emergency Diesel Generator 02 K2.02 Fuel oil pumps 2.8/3.1 073 Process Radiation Monitoring 01 K1.01 Those systems served by PRMs 3.6/3.9 075 Circulating Water 01 A2.01 Loss of intake structure 3.0/3.2 079 Station Air 01 A2.01 Cross-connection with IAS 2.9/3.2 S/R 086 Fire Protection A4.06 Halon system 3.2/3.2 RO K/A Category PointTotals:
1 2 13 12 21 1
3 21 5I 2Group Point Total 1 20
ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)
Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 005 Residual Heat Removal 02 A2.02 Pressure transient protection during 3.5/3.7 RO cold shutdown 005 Residual Heat Removal 04 A2.04 RHR valve malfunction 2.9/2.9 SIR 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 01 A1.01 Hydrogen concentration 3.4/3.8 034 Fuel Handling Equipment 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 05 A1.05 Expected response of primary plant 3.8/4.1 parameters(temperature and pressure)
Sllowing TIG trip 076 Service Water Kl K3.01 Closed cooling water 3.4/3.6 RO 076 Service Water 07 K3.07 ESF loads 3.7/3.9 078 Instrument Air 01 A4.01 Pressure gauges 3.1/3.1 103 Containment 01 A3.01 Containment isolation 3.9/4.2 K/A Category Point Totals:
J12 1 J2J12 1111 J Group Point Total:
8 Plant-Specific Priorities System / Topic Recommended Replacement for...
Reason Points Plant-Specific Priority Total: (limit 10)
J
CO AAI flonerir Knowledge and Abilities Outline (Tier 3)
Fr SAlS(8 i
Facility: Turkey Point Date of Exam:10/14/2002 Exam Level: RO Category K/A #
Topic Imp.
Points M
2.9/4.0 Apply technical specifications for a system SIR 2.1.29 How to conduct and verify valve lineups 3.4/3.
4 Conduct of Operations 2.1.32 Explain and apply all sys limits and precautions 3.4/3.
8 2.1.22 Determine mode of operation 2.8/3.
3 Total 4
>2.l2 Surveillance procedures 3.0/3.
SIR 4
2.2.04 Explain the variations in CB layouts, systems, instr, 2.8/3.
and procedural actions between units 0
Equipment Control 2.2.01 Perform pre-startup procedures for the facility, 3.7/3.
including operating those controls associated with 6
plant equipment that could affect reactivity I
Total 3
2.3.01 10 CFR: 20 and related facility radiation control 2.6/3.
requirements 0
2.3.1i Perform procedures to reduce excessive levels of 2.9/3.
S/R Sradiation and guard against personnel exposure 3
Radiation Control 2.3.11 Control radiation releases 2.7/3.
2 Total 3
Emergency Procedures/
Plan I
2.4.15 Communication procedures associated with EOP implementation 3.0/3.
5 2.4.20 Operational implications of EOP warnings, cautions 3.3/4.
and notes 0
- 2. 1 EOP implementation hierarchy and coordination with 3.0/4.
SIR other support procedures 0
Total Tier 3 Point Total (RO)
Form ES-401-5 (R8, $1) 3 13
Record of Rejected K/As Form ES-401-10 Tier / Group Randomly Selected K/A Reason for Rejection T1G1 074EK2.06 Rejected due to Non-applicability to this facility, replaced by 074EK2.03 (both RO and SRO)
T2G2 079A2.01 Facility does not have procedure for handling effects on the Station Air System from being cross connected with the Instrument Air System therefore, a question could not be written addressing this K/A. Replaced by 033A2.03 (both RO and SRO)
T1G2 038EG2.1.19 Facility plant computer does not address using SGTR evaluation. Replaced by 038EG2.1.07 T2G1/T2G2 063A4.03 Facility does not have control room indication of battery discharge rate. Replaced by 063K2.01 T2G1 059A1.07 Facility does not have MFW pumps with speed control, SGFPs are electric. Replaced by 059A1.03 (RO only)
TiG1 W/E09EG2.4.49 Facility procedures associated with Natural Circulation Operations do not have designated immediate actions. Replaced by W/E09EG2.4.48 T1 G2 W/EI1EG2.2.11 Process for controlling temporary changes not compatible with Loss of Emergency Coolant Recirculation. Replaced by W/E11EG2.4.18 T1G3 W/E13EA2.2 Steam generator overpressure question could not be written addressing limitations in the facility's license and amendments. The facility's license does not address steam generator pressure as a condition of it's license. Replaced by W/E13EA2.1 T1G1/T1G2 OO1AG2.4.12 Question could not be written to this K/A (crew responsibilities during a rod withdrawal). Replaced by OOIAG2.4.1 1.
TI G2 058AA2.01 Question could not be written at a high enough difficulty level since facility verification of DC voltage loss and return is demonstrated by the use of lights and voltage checks. Replaced by 058AA2.03 (RO only)
TI G2 058AA2.01 Question could not be written at a high enough difficulty level since facility verification of DC voltage loss and return is demonstrated by the use of lights and voltage checks. Replaced by 058AG2.1.12 (SRO only)
T2G2 011 A3.01 Determined that a question could not be written for this facility at a high enough difficulty level to discern any discriminating value.
Replaced by 01 1A3.03.
T2G3 076K3.07 K/A not valid for this facility since service water does not cool ESF equipment. Replaced by 076K3.05.
T2G1 001A2.09 Facility does not have procedure to address mitigation of the effects of a station blackout on the CRDS. Replaced by 001A2.10 (RO)
T1G1 057AK3.01 Facility does not have actions within the EOPs for loss of a vital AC instrument bus (actions are contained in AOPs). Replaced by 057AA1.01.
T2G2 033A3.02 Facility does not have automatic actions associated with the SFP cooling system. Replaced by 033G2.2.3 (RO only).
T2G1 017A3.01 Question could not be written at a high enough difficulty. K/A not conducive to written exam, better used for evaluation on the operating exam. Replaced by 017K6.01.
T2G1 061 K2.03 Facility does not have diesel driven AFW pump. Replaced by 061K4.02 (RO only)
T1G1 059AA2.03 Question could not be written at the SRO level that would not cue the applicants to answers to other questions. Test author determined that Liquid Red Waste was highly sampled and randomly changed the K/A keeping the AA2 category. Replaced by 051AA2.02.
TIGI 076AA2.04 Facility does not have process radiation chart recorder for RCS activity. Replaced by 076AA2.01.
T2G1 071G2.4.10 SRO Only. K/A 2.4.10, Knowledge of annunciator response procedures is not conducive to SRO Only topic. Replaced by 071G2.4.44 T3 G2.4.15 Facility does not have communication procedures associated with EOP implementation. Replaced by G2.4.09.
T3 f92204 FPrilitv diffprnnrp* hctwpn nntrnl n.rd-Inyvnkt kinnt cinnifi.nnt Renlarecd byv 9 911 NUREG-1021, Revision 8, Supplement 1 46 of 46
Record of Rejected K/As Form ES-401-10 Facility: Turkey Point Tier / Group Randomly Selected K/A Reason for Rejection TIG3(R) 028A101 (3.413.8)
Changed K/A to 028A102 (3.4/3.7) because original KA not applicable to PTN T2G2 (S)
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