ML110390352
| ML110390352 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/2011 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/10-302, 50-328/10-302 | |
| Download: ML110390352 (74) | |
Text
ES-201 Examination Preparation Checklist Form ES-201-l Facility: 2010 -302 Seguoyah Written Date of Examination: 09/29/20210 lit NRC Examinations Developed by:
Written / Written / Operating Test Taraet Chief Dat e
- Task Description (Reference) Examiner s Initials
-180 1. Examination administration date confirmed (C. 1 .a; C.2.a and b) RSB
-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) RSB
-120 3. Facility contact briefed on security and other requirements (C.2.c) RSB
-120 4. Corporate notification letter sent (C.2.d) RSB
[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] RSB
{-75) 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, RSB as applicable (C.1.e and f; C.3.d)
{-70) {7. Examination outline(s) reviewed by NRC and feedback provided to facility RSB licensee (C.2.h; C.3.e))
{ -45) 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, RSB ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)
-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) RSB
-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-RSB 202)
-14 11. Examination approved by NRC supervisor for facility licensee review RSB (C.2.h; C.3.t)
-14 12. Examinations reviewed with facility licensee (C.l .j; C.2.f and h; C.3.g) RSB
-7 13. Written examinations and operating tests approved by NRC supervisor RSB (C.2.i; C.3.h)
-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent RSB (C.2.i;_Attachment 4;_ES-202,_C.2.e;_ES-204)
-7 15. Proctoring/written exam administration guidelines reviewed RSB with facility licensee (C.3.k)
-7 16. Approved scenarios, job performance measures, and questions distributed to RSB NRC examiners (C.3.i)
Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.
[Applies only] {Does not apply) to examinations prepared by the NRC.
ANAL ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Sequoyah Nuclear Plants I & 2 Date of Examination: 911312010 Item Initials Task Description a b* c#
- 1. a. Verifythatthe outline(s) fit(s) the appropriate model, in accordance with ES-401.
w /l4f. s- /v.4 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.
T I4 s 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. J 1
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- 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, frp J,I 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 4j4_ jYV
.1.
A 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.
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- 3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form , ,
T (3) no tasks are duplicated from the applicants audit test(s) ,
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(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. Verifythatthe administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (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.
7, b?
- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. / it4 12 I/li
- 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. i( j2 R d. Check for duplication and overlap among exam sections.
h L e. Check the entire exam for balance of coverage.
Printed9amSi ature Date
- a. Author Michael Buckner I
- b. Facility Reviewer (*) Van Ford / 7-d- cl:?2)1 ic:,
- c. NRC Chief Examiner (#) -iAc
- d. NRC Supervisor vJl AA Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
1YNId ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Sequoyah Nuclear Plants I & 2 Date of Examination: 912912010 Initials Item Task Description a b*
- 1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
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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. I 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.
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- 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 no 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:
(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. 11ii_.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. i
- c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
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- d. Check for duplication and overlap among exam sections. 21 liY k..
L e. Check the entire exam for balance of coverage. 13 iii
- a. Author Michael Buckner_/ etAm.2 A
- b. Facility Reviewer (*) Van Ford / z4-.--
- c. NRC Chief Examiner (#) Richard S. Baldwin I f/JJ//U
- d. NRC Supervisor Malcolm T. Widmann Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines 0 d-tie avipI b iviZi; 1Z
ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination 913 A4d sI&a I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 69!O6O94aI2O4as 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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 myJnoJed e, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the 9
week(s) of l ji Iioi, bm the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or 0
provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
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ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination o9/3/o 4k-4$
I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 8/46/949-&81 -/261e4f5 /y.
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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 knowledge, I did npt divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of iIii* &trom 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.
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ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09/13 99120t204-O-- 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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 mynowlee, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of I3 I,ilO tirm 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 I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE
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ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination (i1( iDA I
5 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 09113- O9!2Ot2frtOas 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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ofth3- 1/f, 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.
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ES-301 FINAL
- Administrative Topics Outline Form ES-301-1 Facility: Secuoyah Nuclear Station 1 & 2 Date of Examination: 09/13/2010 Examination Level: RO X SRO Operating Test Number_2010302_
Administrative Topic Type Describe activity to be performed (see Note) Code*
M, R, P 2.1 .5 Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime Conduct of Operations limitations, etc (2.9/3.9)
A.1 .a Evaluate Overtime Restrictions (Both RO & SRO)
D, R 2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2)
Conduct of Operations A.1 .b Calculate Manual Makeup to VCT M, R 2.2.12 Knowledge of surveillance procedures (3.9/4.2)
Equipment Control A.2 Boric Acid Storage Tank Level Operability Determination N, R 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions. (3.2/3.7)
Radiation Control A.3 Determine Potential Total Dose for Valve Alignment Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
Type Codes & Criteria: (C)ontrol room, (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)
ANAL Admin l.a This JPM requires the candidate to evaluate different schedules and determine if any of the required work-hour rules were violated. This is a Bank JPM that was used on the 2009 NRC exam which has been Modified.
Admin l.b This JPM requires the candidate to calculate the amount of boric and demin water necessary to make a manual makeup to the VCT that is equal to existing RCS boron concentration. This is a Bank JPM.
Admin 2 This JPM requires the candidate to evaluate the conditions of a Boric Acid Storage Tank to determine if it meets the Tech Spec requirements. This is a Modified Bank JPM.
Admin 3 This JPM requires the candidate to determine the potential dose they would receive while performing a surveillance that verifies the timed operation of a valve in the RCA. This is a New JPM.
ANAL ES-301 Administrative Topics Outline Form ES-301-1 Facility: Secuoyah Nuclear Station 1 & 2 Date of Examination: 09/13/2010 Examination Level: RO SRO X Operating Test Number: 2010302 Administrative Topic Type Describe activity to be performed (see Note) Code*
M, R, P 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime Conduct of Operations limitations, etc. (2.9/3.9)
A.1.a Evaluate Overtime Restrictions (Both RO & SRO)
N, R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2)
Conduct of Operations A.1 .b Review of Estimated Critical Position Calculation M, R 2.2.43 Knowledge of the process used to track inoperable alarms. (3.0/3.3)
Equipment Control A.2 Review and Approve a Disabled Alarm Checklist D, R 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions. (3.2/3.7)
Radiation Control A.3 Evaluate Worker Exposure D, R 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as Emergency Procedures/Plan emergency coordinator if required. (2.4/4.4)
A.4 Classify the Event per the REP (SGTR with_Failed_S/G_Safety)
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)
ANAL Admin l.a This JPM has the candidate review several different work schedules and determine if any of the required work-hour rules were violated. This is a Bank JPM that was on the 2009 NRC exam but has been Modified.
Admin I .b This JPM has the candidate review a completed ECP calculation and identify any and all errors that were committed during the development of the ECP. This is a New JPM.
Admin 2 This JPM has the candidate review a Disabled Annunciator request and identify any and aN errors that may have been committed during the development of the request. This is a Modified Bank JPM.
Admin 3 This JPM has the candidate review projected workers dose for performing a job in the RCA and determine if any Federal or Administrative dose limits may be exceeded by any of the workers and any additional approvals that would need to be made if the actual doses were to reach the estimated values. This is a Bank JPM.
Admin 4 This JPM has the candidate review the data presented during a proposed accident and determine the Emergency Event Classification, also indentify and report any Protective Action Recommendations (PARs) which would be appropriate for the accident. This is a Bank JPM.
ES-301 ANAL Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Nuclear Station 1 & 2 Date of Examination: 09/13/2010 Exam Level: RO X SRO-l X SRO-U Operating Test No.:
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. 001 Control Rod Drive System; A2.17 (3.3/3.8) M, A, S, L 1 SIM A Shutdown Bank Withdrawal
- b. 006 Emergency Core Cooling System; Al .13 (3.5/3.7) D, S 2 SM B Refill #3 CLA to within Normal Range
- c. 007 Pressurizer Relief Tank System; A2.02 (2.6/3.2) D, S 5 SIM C Return PRT to Normal
- d. 003 Reactor Coolant Pump System; Al .02 (2.9/2.9) N, S 4P SIM D Respond to Loss of Flow to RCP Oil Cooler
- e. W/E14 High Containment Pressure; EA1.1 (3.7/3.7) D, A, S 3 SIM E Respond to HI CNMT Pressure, Place RHR Spray In Service
- f. 015 Nuclear Instrumentation System; A4.02 (3.9/3.9) D, S 7 SIM F Calibrate Power Range NIs
- g. 036 Fuel Handling Incidents AA2.02 (3.4/4.1) M, A, 5, L 8 SIM G Initiate Makeup to the Refueling Cavity
- h. 064 Emergency Diesel Generation; A4.06 (3.9/3.9) D, S 6 SIM H Shutdown the Diesel Generators Following Auto Start In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. 063 D.C. Electrical Distribution; A4.01 (2.7/3.0) D 6 In Plant I Spare out a Vital Batt Charger
- j. 061 Auxiliary/Emergency Feedwater System; A2.07 (3.4/3.5) D, A, R 4S In Plant J Local control of MD AFW Pump Flow
- k. 002 Reactor Coolant System; A3.01 (3.7/3.8) D, R 8 In Plant K Local Alignment of 2-RM-90-1 12 to Lower CNMT
ANAL
@ 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 I I I I 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) 2I 2I 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA 1I1I1 (S)imulator SIM A This JPM has the candidate identify misaligned control rods while attempting to withdraw the Shutdown banks in preparation for a reactor start-up. This is a Modified Bank, Low Power, Alternate Path JPM.
SIM B This JPM has the candidate refill a cold leg accumulator to its normal level using a safety injection pump and place the SI pump back in standby status after fill complete. This is a Bank JPM.
SIM C This JPM has the candidate return the PRT to normal temperature and pressure following a leaking PZR PORV. This is Bank JPM.
SIM 0 This JPM has the candidate determine that a loss of cooling has occurred to the RCP oil coolers which will require the candidate to stop the affected RCP. This is a New JPM.
SIM E This JPM directs the candidate to respond to continued High CNMT pressure following a LOCA by aligning RHR to provide CNMT spray. The Alternate path develops when the normal spray supply valve will not open. This is an Alternate Path, Bank JPM.
SIM F This JPM has the candidate review the NIS readings against a calorimetric power calculation.
The Alternate path is that a calibration adjustment is required to be made to a power range NI. This is a BankJPM.
SIM G This JPM has the candidate respond to lowering level in the Refueling Cavity. The Alternate path is that the normal supply of fill from the charging pumps will be unavailable and will require re-alignment of the suction of RHR pumps to provide the fill. This is a Modified Bank, Low Power, Alternate path JPM.
SIM H This JPM has the candidate shutdown an EDG that has been running unloaded for an extended period of time following an auto start. This will require the diesel to be paralleled and loaded prior to shutdown. This is a bank JPM. (proposed RO only)
In-plant I This JPM has the candidate walk through process of placing the spare battery charger in service and removing the normal charger. This is Bank JPM.
In-plant J This JPM has the candidate take local control of AFW supply to #3 SG due to valve not responding from the control room. Alternate path is that the valve will not respond to local control switch manipulations either and will require manual operation for control. This is an Alternate Path, Bank JPM performed in the RCA.
In-plant K This JPM directs the candidate to locally realign 2-RM-90-1 12 to monitor Lower Containment vs Upper Containment as part of the Unit 2 RCS leak detection system. This is a Bank JPM performed in the RCA.
ANAL ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Sequoyah Nuclear Station 1 & 2 Date of Examination: 09/13/2010 Operating Test Number: 2010302 Initials
- 1. General Criteria a b* f
- a. The operating test conforms with the previously approved outline; changes are consistent with
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sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). tYP 14. )
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- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination. Va, 9 I
- c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 .a.) *i4 ti
- d. Overlap with the written examination and between different parts of the operating test is within acceptable limits.
.y Li)
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. /3
=
4i4 M I
- 2. Walk-Through Criteria -- --
- a. Each JPM includes the following, as applicable:
initial conditions initiating cues
- references and tools, including associated procedures I
reasonable and validated time limits (average time allowed for completion) and specific V1 designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable
- b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified 14 on those forms and Form ES-201-2.
- 3. Simulator Criteria -- --
The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
jy
.....L.
Printed Name / Signature Date
- a. Author Michael Buckner o
- b. Facility Reviewer(*) Van Ford
- c. NRC Chief Examiner (#) Zu4MO q q/z / ,
- d. NRC Supervisor lWkLCCL) f 1Ji (
NOTE: The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
ANAL ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Sequoyah Nuclear Station I & 2 Date of Exam:09!13I2010 Scenario Numbers: 1/213 Operating Test No.:
2010302 QUALITATIVE ATTRIBUTES InWals a b*
- 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. ir Wt
- 2. The scenarios consist mostly of related events.
- 3. Each event description consists of lk( f-
. 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 P
. the expected operator actions (by shift position)
. the event termination point (if applicable)
- 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 9,
- 5. The events are valid with regard to physics and thermodynamics.
Zf W 1
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints. i Cues are given. 9Q ij7
- 8. The simulator modeling is not altered. 3t liy
- 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
- 10. Every operator will be evaluated using at least one new or significantly modified scenario.
All other scenarios have been altered in accordance with Section D.5 of ES-301. -1 n
I
/
- 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
- 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
3?.f(V IT
- 13. The level of difficulty is appropriate to support licensing decisions for each crew position.
Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --
- 1. Total malfunctions (58) 5/ 8 / 8 fj it
- 2. Malfunctions after EOP entry (12) 1 / 1 /3 74 .(4)
- 3. Abnormal events (24) 3/ 4 /4
- 4. Major transients (12) 1 / 1 /2 r
7 1
- 5. EOPs entered/requiring substantive actions (12) 3/ 2 /4 17t !.\
- 6. EOP contingencies requiring substantive actions (02) 1 / 2 /2 )
- 7. Critical tasks (23) 1 / 2 /3 71
H j
tlH 9 9
.1 ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Sequoyah Nuclear Station 1 & 2 Date of Exam:0911312010 Scenario Numbers: 41617 Operating Test No.: 2010302 QUALITATIVE ATTRIBUTES lnftials a b* c#
- 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out 1 ,
of service, but it does not cue the operators into expected events.
/fr i4t
- 2. The scenarios consist mostly of related events. 44 91_ 1
- 3. Each event description consists of
. the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position) 1
- the event termination point (if applicable)
- 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario
/
without a credible preceding incident such as a seismic event. jLW f? 1i
- 5. The events are valid with regard to physics and thermodynamics.
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints.
Cues are given. 1ik I
- 8. The simulator modeling is not altered.
- 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
- 10. Every operator will be evaluated using at least one new or significantly modified scenario.
All other scenarios have been altered in accordance with Section D.5 of ES-301. /
1iL
- 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
1V
- 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). .b
- 13. The level of difficulty is appropriate to support licensing decisions for each crew position.
Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- --
- 1. Total malfunctions (58) 8/ 6/8 aL4 *11/2
- 2. Malfunctions after EOP entry (12) 2/ 1 / 1 1/v fji
- 3. Abnormal events (24) 5 /4 / 5 f2< 114
- 4. Major transients (12) 1 /2I1
- 5. EOPs entered/requiring substantive actions (12) 2 /3/3 4f
- 6. EOP contingencies requiring substantive actions (02) 1 /1 /2 hf
- 7. Critical tasks (23) 4/ 2/2 h1. tjjJ)
ANAL ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 4 TM L N CREW CREW CREW CREW I N T POSITION POSITION POSITION C POSITION S A B S A M A T B S A B S A B L R T 0 R u N Y TO R T 0 R T 0 M*
r 0 C P 0 C P 0 C P 0 C P I r R IU E
RO RX 1 1110 o-X NOR I/C 1
2,3,4, iiiL 2,5,9 7 4 4 2 SRO-U MAJ 6 6,7 3 221 TS 2,3 2022 RX t5a 2 110 RO x NOR 2a 1 2 1 11 O-l I/C 2,4 38, 6 4 4 2 Li 10 MAJ 6 6,7 3221 TS 0022 RO RX 1 1 110 x
SRO-l NOR 1 1 1 1 1 I/C 3,5 2,5,9 5 4 4 2 SRO-U MAJ 6 6,7 3 2 2 1 1_J TS 0022 RO RX 1,5a 2 1 1 0 NOR 2a 1 SRO-l X I/C 2,4 2,3,4,5, 10 4 4 2 SRO-U 7,8,9,10 MAJ 6 6,7 3 2 2 1 TS 2,3,5 3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 Transient and Event Checklist Form ES-301-5
[ Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 4 T M L N CREW CREW CREW CREW POSITION I T POSITION POSITION POSITION T
c A
M S A B S A B S A B S A A T R T 0 R T 0 R TO R T B
0 L u N Mf*
0 C P 0 C P 0 C P 0 C P T
R lU E
RO RX 51110 X
NOR I/C I
2,3,4, 2,4,6,9 ii 8 4 4 i 2 SRO-U MAJ 6 TS 2,3 2 022 RX t5a RO x NOR 2a 52111 O-l I/C 2,4 1,3,4, 6 4 4 2 8
MAJ 6 72221 TS 0022 RO RX 5 1110 SROI NOR 1 I/C 3,5 2,4,6,9 6 4 4 2 SRO-U MAJ 6 7 2 2 2 1 U TS 0 0 22 RO RX 1,5a 2 NOR 2a 11 o-i 5 21 X I/C 2,4 1,2,3,4, 9 4 4 2 SRO-U 6,8,9 MAJ 6 7 2221 TS 1,2,4 3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a I -for-i basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant I & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 4 T M L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION c A M
A T S A B S A B S A B S A B L R T 0 U N Y R T 0 R T 0 R T MI*
T r 0 C P 0 C P 0 C P 0 C P F
R lU E
RD px 1 1 110 SROI X
NOR I/C 4
1,2,3, ii 2,5,9 iL 8 4 4 2 SRO-U 6,8 MAJ 7 6,7 3 2 2 1 TS 3,5 2022 RD RX 4 ii i X NOR 1 1 111 SRO-l I/C 2,6,8 3,4,8, 7 4 4 2 U 10 SRO-U MAJ 7 6,7 3 2 2 1 TS 0022 RO RX 1 1 110 SRO-l NOR 4 liii I/C -
1,3 2,5,9 5 4 4 2 SRO-U MAJ 7 67 3 2 2 1 Li TS 0022 RD RX 4 1 110 NOR 1 1111 SROI X I/C 2,6,8 2,3,4,5 10 4 4 2 SRO-U 8,9,10 MAJ 7 6,7 3 2 21 TS 2,3,5 3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RD applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRD additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-i basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 Transient and Event Checklist Form ES-301-5
((acuity: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 4 T M L N CREW CREW CREW CREW POSITION N C
I T POSITION POSITION POSITION I M A T S A B S A B S A B S A B L R T 0 R T OR T u
N Y 0 R T M*
0 C P 0 C P0 C P 0 C P T
R lU E
RO RX 5 1170 X
NOR I/C 4
1,2,3, 2,4,6,9 iiiL 9 4 4 2 SRO-U 6,8 MAJ 7 7 2221 TS 3,5 2022 RX 4 RO X NOR 5 1 111 0-l I/C 2,6,8 14, 7 4 4 2 Li 8 SROU MAJ 7 72221 TS 0022 RO RX 5 1110 SROI NOR 4 I/C 1,3 2,4,6,9 6 4 4 2 SRO-U MAJ 7 7 2 2 2 1 Li TS 0022 RO RX 4 1 110 NOR 5 X I/C 2,6,8 1,2,3,4, 10 4 4 2 SRO-U 6,8,9 MAJ 7 7 2 221 TS 1,2,4 3 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-i event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 *6* T M L N CREW CREW CREW CREW I T POSITION T POSITION POSITION POSITION c M A T S A B S A B S A B S A B L N R T 0 R T 0 R T 0 R T 0 u
Y M(*
0 C P 0 C P 0 C P 0 C P T
E R IU RO RX 51110 X
NOR I/C 1
2,3,4, ii 1,2 i 6 4 4 2 SRO-U MAJ 6 6,7 3221 TS 2,3 2022 RO RX 1 ,5a 2 1 1 0
NOR SRO-I I/C 2,43A4 4 42 SRO-U MAJ 6 6,7 3 2 2 1 D TS 0022 RO RX 5 1 110 SRO-l NOR 11111 I/C 3,5 1,2 4 4 4 2 SRO-U MAJ 6 6,7 3 2 2 1 L.._i TS 0 0 22 RO RX 1,5a 2 1 1 0 NOR 2a o-X I/C 2,4 1,2,3, 6 4 4 2 SRO-U MAJ 6 6,7 3 2 2 1 TS 1,2 2022 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 -
Transient and Event Checklist Form ES-301-5 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 09/13/2010 Operating Test No.: 2010302 A E Scenarios 1 2 3 *7* ] M L N CREW CREW CREW CREW POSITION I T T N POSITION POSITION POSITION I c A S A B S A M A T B S AB S A B L R T 0 R u N T 0 R TO R T M(*
,- 0 C P 0 C P 0 C P 0 C P i P R lU E
RO RX 1 1110 o
X NOR I/C 1
2,3,4,5 3,6,7,8 ii 8 i
4 4 2 SRO-U MAJ 6 9 2 2 2 1 TS 2,3 2022 RO X NOR 2a 1,3a,6 i 1 1 Ol I/C 2,4 2,5, 5 4 4 2 U 10 SRO-U MAJ 6 92 221 TS 0022 RO RX 1,6 2 1 1 0 SROI NOR 1 I/C 3,5 3,6,7,8 6 4 4 2 SRO-U MAJ 6 9 2 2 2 1
TS 0022 RO RX 1,5a 2 1 1 0 NOR 2a 1,6 3 1 1 1 o-l X I/C 2,4 2,3,5,6, 9 4 4 2 SRO-U 7,8,10 MAJ 6 9 2221 TS 3,4 2022 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ANAL ES-301 Competencies Checklist Form ES-301-6 Facility: Sequoyah Nuclear Plant I & 2 Date of Examination: 0911312010 Operating Test No.: 2010302 APPLICANTS RO X RO RO X RO SRO-I D SRO-I X SRO-l D SRO-l x SRO-U D SRO-U D SRO-U LI SRO-U LI Competencies - SCENARIO 123 41234 6 7 67 Interpret/Diagnose 2,3, 1,2, 2,3,4, 1,2,3, 2,3 1,2, 2,3,4, 1,2, 1,2,3, 2,3,5,6, 1,2, 2,3,5,
. 4,5, 3,5, 5,6,7 4,6,7, ,4, 3,5, 5,6,7, 3,4, 4,6,7 7,9,10 3,4, E venLs anu .OfluiiiOflS 6,7,8, 6 6,7, 8,9, 8,9 5,6 6,7, 8,9, 6,7, 6,7 9,10 8 10 8 10 8,9 Comply With and 1,2, 1,2, 1,2,3, 1,2,3, 1,2 1,2, 1,2,3, 1,2, 1,2,3, 1,2,3,5, 1,2, 1,2,3, 3,4, 3,4, 4,5,6, 4,5,6, ,3, 3,4, 4,5,6, 3,4, 4,5,6, 6,7,8, 3,4, U se roceuures i,,,., ) 5,6,7, 5,6 5,6, 7,8,9, 7,8,9 4,5 5,6, 7,8,9, 5,6, 7 9,10 5,6, 8,9, 7,8 10 ,6 7,8 10 7,8, 7 10 9
Operate Control 1,2, 1,2, 1,2,3, 1,2,3, 1,2 1,2, 1,2,3, 1,2, 1,2,3, 1,2,3,5, 1,2, 1,2,3, B oarus kU 3,4, 3,4, 4,5,6, 4,5,6, ,3, 3,4, 4,5,6, 3,4, 4,5,6, 6,7,8, 3,4, 5,6,7, 5,6 5,6, 7,8, 7,8,9 4,5 5,6, 7,8, 5,6, 7 9,10 5,6, 8,9, 7,8 10 ,6 7,8 10 7,8, 7 10 9
Communicate 1,2, 1,2, 1,2,3, 1,2,3, 1,2 1,2, 1,2,3, 1,2, 1,2,3, 1,2,3,5, 1,2, 1,2,3, anu interaci
, 3,4, 3,4, 4,5,6, 4,5,6, ,3, 3,4, 4,5,6, 3.4, 4,5,6, 6,7,8, 3,4, 5,6,7, 5,6 5,6, 7,8,9, 7,8,9 4,5 5,6, 7,8,9, 5,6, 7 9,10 5,6, 8,9, 7,8 10 .6 7,8 10 7,8, 7 10 9
Demonstrate 1,2 1,2, 1,2,3, 1,2, 1,2, 1,2,3, 3 34 456 34 34, Supervisory Ability (3) 4,5 5,6, 7,8,9, 5,6, 567 5,6, 8,9,
,6 7,8 10 7,8, 7 10 9
Comply With and 2,3 3,5 2,3,5 2,3, 1,2 3,4 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:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: oys DateofExam: 2)Jo 3i_ -i .\
RO K/A Category Points SRO-Only Points Tier Group KKKKKI<AAAAG G*
A2 Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &
Abnormal Plant 2 7 NIA 2 1 1 9 2 2 4 N/A Evolutions Tier Totals 4 27 5 5 10 1 32333223232 28 2 5 2.
2 1 1 1 11 0 1 11 1 1 10 Plant 2 1 3 Systems Tier Totals 4 3 4 4 4 2 3 4 3 4 3 38 5 3
= = = = = = =
8
=
- 3. GenericKnowledgeandAbilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2
- 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the uTier 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 associa ted outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally import ant, site-specific systems that are not included on the outline should be added. Refer to section D.I .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an import ance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respec tively.
- 6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.
- 7. lhe generic (G) K/As In Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.I.b of ES-401 for the applicable KAs.
- 8. On the following pages, enter the K/A numbers, a brief descrip tion 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 sample d 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 # I 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 thatare linked to 10 CFR 55.43..
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 008AK2.02 Pressurizer Vapor Space Accident / 3 2.7 2.7 H [J H El H H H H i] El Sensors and detectors O11EK2.02 Large Break LOCA/3 2.6 2.7 H fl fl Pumps 022AA2.Ol Loss of Rx Coolant Makeup / 2 3.2 3.8 El E1 H H H H H H H Whether charging line leak exists 025AG2.1.7 Loss of RHR System /4 4.4 4* ( fl H J H H H H Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
026AK3.O1 Loss of Component Cooling Water / 8 3.2 3.5 H Hl H H H H H H H H The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers 027AA1 .05 Pressurizer Pressure Control System 3.3 3.2 Malfunction I 3 H H H H H H H H El 1 Transfer of heaters to backup power supply 029EG2.4.31 ATVVS I 1 4.2 4.1 H H H H H H H H H H Knowledge of annunciators alarms, indations or response procedures 038EA1 .17 Steam Geri. Tube Rupture / 3 3.2 3.2 H H H H H H Li H H H SIG sample isolation vve indicators 054AP2.07 Loss of Main Feedwater / 4 3.4 3.9 H H H H H H H H H H Reactor trip first-out panel indicator 056AA2.56 Loss of Off-site Power/S 3.6 37 H H H H H H H H El H. RCS T-ave 057AK3.Oi Loss of Vital AC Inst. Bus / 6 4.1 4.4 H HEJ H H H H H fl H Actions contained in EOP for loss of vital ac electrical instrument bus Page 1 of 2 01/07/2010 2:20 PM
ES-401, REV 9 T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO 058AK1 .01 Loss of DC Power! 6 2.8 3.1 El [ El El Battery charger equipment and instrumentation 062M1.07 Loss of Nuclear Svc Water/4 2.9 3 El ri H LI El l El El El El Flow rates to the components and systems that are serviced by the SWS; interactions among the components 077AK1 .03 Generator Voltage sad Electric Grid 3.3 3.4 Disturbances / 6 [I LI* El [1 H El El El Under-excitation -.______________
WEO4EK1 I LOCA Outside Containment I 3 3 5 39 El H El [1 El LI LI El Components capacity and function of emergency systems.
WEO5EK3.2 Inadequate Heat Transfer Loss of 3.7 4.1 Secondary Heat Sink / 4 E
1 1 E El LI El El [] Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).
WE11EK2.1 LossofEmergencyCoolantRecirc.14 3.6 3.9 El D[Z Fi, [ LI El LI LI LI Components and functions of control and safety systems, indudiag instrumentation, signals, interlocks, failure modes and automatic and manual features, wel2EG2.4.3 Steam Line Rupture Excessive Heat 3.7 39 Ej El E El, El LI LI Li LI LI Transfer / 4 Abilitytoidentifypost-accidentinstrumentation.
Page 2 of 2 01/0712010 2:20PM
ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME / SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 028AK2.02 Pressurizer Level Malfunction /2 2.6 2.7 jj El L] Sensors and detectors 032AK3.02 Loss of Source Range NI I 7 3.7 4.1 j Li fl j fl j Guidance contained in LOP for loss of source-range nuclear instrumentation 033AG2.4.30 Loss of Intermediate Range NI /7 2.7 4.1 El Li fl fl Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
036AK1 .01 Fuel Handling Accident! 8 3.5 4.1 Li Li Li Li Li Li Li Radiation exposure hazards 068A1.06 Control Room Evac.!8 4.1 4.2 fl ] [j [ j [] [] fl Charging pump 074EA1 .23 mad. Core Cooling / 4 3.9 Li Li Li Li Li Li Li Li E] Li PORV block valve indicators, switches, controls (for both RCS and SIG).
076AK3.06 High Reactor Coolant Activity I 9 3.2 3.8 Li Li Li Li Li Li Li Li Li Actions contained in LOP for high reactor coolant activity WE14EA2.1 Loss of CTMT Integrity! 5 3.3 3.8 Li Li Li Li Li Li Li 1 Li Li Li Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
WEI5EK1.2 Containment Flooding/S 2.7 2.9 LiLiLiLiLiLiLiLiLiLi Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
Page 1 of 01/07/2010 2:20 PM
ES-401, REV9 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:
RO SRO 003A4.03 Reactor Coolant Pump 2.8 2.5 LI J RCP lube oil and lift pump motor controls 004K4.08 Chemical and Volume Control 2.8 3.2 Li El Li Li Li Li Li El [j Hydrogen control in RCS 004K5.29 Chemical and Volume Control 2.6 3.3 fl n Li Li fl Li Li Li fl Reason for sampling for chloride, fluoride, sodium and solids in RCS 005G2.4.46 Residual Heat Removal 4.2 4.2 fl [1 F] Ability to verify that the alarms are consistent with the plant conditions.
006K2.04 Emergency Core Cooling 3.6 3.8 Li Li Li Li Li Li Li Li Li ESFAS-operated valves 007K1 .03 Pressurizer Relief/Quench Tank 3.0 3.2 fl Li Li Li LI Li Li Li Li [J RCS 008A2.08 Component Cooling Water 2.5 2.7 Li El Li Li Li Li Li ] Li LI Li Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler 008K1 .04 Component Cooling Water 3.3 3.3 Li El LI Li LI Li El H Li fl RCS, in order to determine source(s) of RCS leakage into the CCWS 010K4.02 Pressurizer Pressure Control 3.0 3.4 Li Li Li Li LI Li Li Li Li Li Prevention of uncovering PZR heaters 012A1 .01 Reactor Protection 2.9 3.4 LiE] El Li Li Li 1 El Li Li El Trip setpoint adjustment 013K5.02 Engineered Safety Features Actuation 2.9 3.3 El Li Li El Li Li Li Li Li Li Safety system logic and reliability Page 1 of 3 01/07/2010 2:21 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RD SRO 013K6.0l Engineered Safety Features Actuation 2.7 3.1 fl fl El [1 H Sensors and detectors 022K3.0l Containment Cooling 2.9 3.2 El El: fl fl fl fl fl Containment equipment subject to damage by high or low temperature, humidity and pressure 025K5 02 Ice Condenser 2.6 2.8 TZH El El El El El fl fl fl Heat transfer 026A3.01 Containment Spray 4.3 4.5 El H FE El El El El El El Pump starts and correct MDV positioning 026A4.01 Containment Spray 4.5 4.3 H El El H El El El CSS controls 039A3.02 Main and Reheat Steam 3.1 3.5 fl El El El El El El LI El [El Isolation of the MRSS 059K3.02 Main Feedwater 3,6 3.7 H fl ] LI H fl ] El El fl El AFW system 059K3.03 Main Feedwater 3.5 37. El El LI H H El El LI El S/GS 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 H El El El [] H El H Pumps 062G2.4.35 AC Electrical Distribution 3.8 4.0 El H El El El El El El El El Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 063A4.0l DC Electrical Distribution 2.8 3.1 El H El El El El El El l El Major breakers and control power fuses Page 2 of 3 01/07/2010 2:21 PM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 064A2.05 Emergency Diesel Generator 3.1 3.2 fl Loading the ED/G 073A1.Ol Process Radiation Monitoring 3.2 3.5 El fl fl ] fl [] Radiation levels 073K1.Ol Process Radiation Monitoring 3.6 3.9 U El El El U U El E El fl Those systems served by PRMs 076K2.04 Service Water 2.5 2.6 fl fl El El El Reactor building closed cooling water 078K4.02 Instrument Air 3.2 3.5 El El El E El El [] Cross-over to other air systems 103A2.04 Containment 3.5 3.6 El El El El El El El i El El El Containment evacuation (including recognition of the alarm)
Page 3of3 01107/2010 2:21 PM
ES-401, REV9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001K2.03 Control Rod Drive 2.7 3.1 LI Li Li LI Li fl LI Li LI LI One-line diagram of power supplies to logic circuits 002A4.02 Reactor Coolant 4.3 4.5 El [] El El Li [] Li Li Li Indications necessary to verify natural circulation from appropriate level, flow and temperature indications and valve positions upon loss of forced circulation 017K3.01 In-core Temperature Monitor 3.5 3.7 [J i fl U Natural circulation indications 027K5.01 Containment Iodine Removal 3.1 3.4 Li LI E Li j fl U] flElU]. Purpose of charcoal filters 028A1 .02 Hydrogen Recombiner and Purge 3.4 3.7 Control LI Li Li LI Li Li Li LI Li Li Containment pressure 034K4.03 Fuel Handling Equipment 2.6 3.3 LI Li Li Li Li Li Li Li Li Li Overload protection 035G2.2.40 Steam Generator 3.4 4.7 Li Li Li Li Li Ui LI Li Li Li Ability to apply technical specifications for a system.
055K1.06 CondenserAirRemoval 2.6 2.6 LI Li Li Li Li Li LI Li U] Li PRMsystem 071A3.02 Waste Gas Disposal 2.8 2 L I Li Li Li Li LI Li LI LI Li Pressure-regulating system for waste gas vent header 075A2.03 Circulating Water 2.5 2.7 Li Li Li Li Li Li Li Li Li Li Safety features and relationship between condenser vacuum, turbine trip and steam dump Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 (3 TOPIC:
RO SRO (32.1 .38 Conduct of operations 3.7 3.8 LI LI LI LI LI Li LI Li LI Li Knowledge of the stations requirements for verbal communication when implamenting procedures G2.l.7 Conductoperations 4.4 4.7 LI LI LILI LI LI LI LI LI LI Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
(32.2.11 EquipmentControl 2.3 LI El LI LI LILI LI LI LI LI i Knowledge of the process for controlling temporary design changes.
G2.2.19 EquipmentControl 13 3.4 flflLI Knowledge of maintenance work order requirements.
(32.3.13 Radiation Control 3.4 3.8 LI LI LI LI LI LI LI LI LI Lii ii Knowledge of radiological safety procedures pertaining to licensed operator duties (32.3.15 RadiationControl 2.9 3.1 LILILILILILILIflLI Knowledge of radiation monitoring systems (32.3.4 RadiationContrc 3.2 3.7 LILILILILILILILILI11 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.28 Emergency Procedures/Plans 3.2 4.1 LI LI LI LI LI LI LI LI LI LI i Knowledge of procedures relating to emergency response to sabotage.
G2.4.31 Emergency Procedures/Plans 4.2 4.1 LI LI LI LI LI LI LI LI LI LI : Knowledge of annunciators alarms, indications or response procedures (32.4.6 Emergency Procedures/Plans 3.7 4.7 LIELILILILILILILILI Knowledge symptom based EOP mitigation strategies.
Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 SRO T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 029EA2.06 ATWS /1 3.8 3.9 Main turbine trip switch position indication Gen. Tube Rupture / 3 Ability to apply technical specifications for a system.
054AG2.4.30 Loss of Main Feedwater I 4 2.7 4.1 Knowledge of events related to system operations/status that must be reported to intemal orginizations or outside agencies.
055EA2.03 Station Blackout! 6 Actions necessary to restore power 058AG2.4.18 Loss of DC Power /6 3.3 4.0 Knowledge of the specific bases for EOP5.
07L4A2.08 Generator Voltage and Electric Grid Disturbances / 6 Criteria to trip the turbine or reactor Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO OO1AA2.02 Continuous Rod Withdrawal 1 1 4.2 4.2 El fl El. 1 El El El El El Position of emergency boration valve 060AG2.4.l Accidental Gaseous Radwaste Re!. / 9 4.6 4.8 El El El El El El El El El ] Knowledge of EOP entry conditions and immediate action steps.
061AA20l ARM System Alarms / 7 3.5 37 El El El El El El El E?i El El El ARM panel displays 069AG2.4.21 Loss of CTMT Integrity / 5 4.0 4.6 El H El El El El El El El El El Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: JR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 012A2.O1 Reactor Protection 3.1 3.6 Faulty bistable operation 039A2.03 Main and Reheat Steam 3.4 3.7 Li Li Li Li Li Li Li 1 Li Li Indications and alarms for main steam and area radiation monitors (during SGTR) 076G2.4.3 Service Water 3.7 3.9 Li Li Li ri Li Li Li [1 Li Li Ability to identify post-accident instrumentation.
078A2.0l InstrumentAir 2.4 2.9 Li Li Li fl El fl Li [3 [3 Air dryer and filter malfunctions 103(32.4.3 Containment 3.7 3.9 Li Li [3 Li Li Li Li Li LI Li Ability to identify post-accident instrumentation.
Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:
RO SRO 028A2.01 Hydrogen Recombiner and Purge 3.4 3.6 DDflEDflrZ1E1 Hydrogen recombiner power setting, determined by using Control plant data book 068A2.04 Liquid Radwaste 33 33 Failure of automatic isolation 071 G2.2.36 Waste Gas Disposal 3.1 4.2 Ability to analyze the effect of maintenance activities.
such as degraded power sources, on the status of limiting conditions of operations Page 1 of 1 01/07/2010 2:21 PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC RO SRO G2.l .27 Conduct of operations 3.9 4 r El Li Li Li Li Li El Li Knowledge of system purpose and or function.
G2.2.18 Equipment Control 2.6 3.8 fl El El El Li El El fl Knowledge of the process for managing maintenance activities during shutdown operations.
G22 40 Equipment Control 34 47 J ] fl El i Abfity to apply technical specifications for a system G2.3.12 Radiation Control 3.2 3.7 Li El fl [] [] fl Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 EEl El El Li El EEl Li El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.30 Emergency Procedures/Plans 2.7 4.1 El El El El El El El El Li El Knowledge of events related to system operations/sta tus that must be reported to internal orginizations or outside agencies.
G2.4.46 Emergency Procedures/Plans 4.2 4.2 fl El El El El El El Li El El Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of I 01/07/2010 2:21 PM
FINAL ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO T2G1 076 K2.04 SQN does not have a Reactor Building Closed Cooling Water system. (Re-selected 076 K2.08; JR 3.1/3.3)
T3 G 2.2.11 RO importance rating < 2.5 (2.3)
(Re-selected G 2.2.14; IR 3.9/4.3)
T3 G 2.2.19 RO importance rating < 2.5 (2.3)
(Re-selected G 2.2.6; JR 3.0/3.6)
SRO Ti G2 060 AG2.4. 1 Unable to write a question to address EOP entry conditions and immediate action steps for a Gaseous release.
(Re-selected 060 AG2.4.21; JR 4.0/4.6)
T2G1 076 G 2.4.3 Over-sampling of generic K/A and overlap with RO #18 (Re-selected 076 G 2.4.4; JR 4.5/4.7)
T2G1 103 G 2.4.3 Over-sampling of generic K/A and overlap with RO #18 (Re-selected 103 G2.4.21; JR 4.0/4.6)
Ti Gi 077 AA2.08 Unable to write an operational valid question at the SRO level (Re-selected 077 AA2.07; JR 3.6/4.0)
FINAL ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Sequoyah Nuclear Plant 1 & 2 Date of Exam: 0911312010 Exam Level: RO X SRO X Initial Item Description a b* c,#
- 1. Questions and answers are technically accurate and applicable to the facility. 11W
- 2. a. NRC KJAs are referenced for all questions.
- b. Facility learning objectives are referenced as available. i1.O 11
- 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 DL 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 new or modified); enter the actual RO / SRO-only 47/ 11 5/2 23 / 12 question distribution(s) at right.
(/) 63/44 7/8 30/48
- 7. Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 32 / 5 43 / 20 114-the actual RO / SRO question distribution(s) at right. (%) 43/20 57 / 80
- 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.
- 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 Michael Buckner
- b. Facility Reviewer (*) Van Ford 7.c_ ? I
- c. NRC Chief Examiner (#) Richard S. Baldwin 7/27/ia
- d. NRC Regional Supervisor Malcolm T. Widmann 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 Review Worksheet Form ES-401-9 SEQUOYAH 201 0-302 REVIEW PRE ATLANTA Q# ] 1. 2.
J 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
(F/H) (1-5) I Focus Stem Cuesi T/F Cred. P 1 artial Job- Minutia #1 Back- Q= ]SRO B/M/N U/E/S Explanation
__J Dist. Link units ward K/A H 3 N S 008AK2.02, New, Higher KAappearstobeok Question appears to be ok.
2 F 2-3 B E 011 EK2.02, Bank, Lower Add to the stem, the word, operator prior to actions. Added as requested.
Change the distractors A and B to read, the following pumps are put in PTL....
In distractor D, underline or capitalize ALL, to ensure some one does not make a mistake because of reading. Ask licensee if this has been done for other distractors.
KA appears to be Ok.
Otherwise question appears to be Ok.
Should we add the procedure to the stem, Van Ford. RSB agrees with this, added to the stem the ES 1.3, Transfer to RYR containment sump. OK.
3 H 3 N E 022AA2.01, New, Higher In the stem of the question, the procedure that these actions are being done with should be added. This ensures that the question is lock tight with respect to actions to be.
Add to the stem the value of CCP amps initially, added Distractor D does not appear to be plausible, the controller is increasing and demanding more flow. What indications does the operator have listed that would indicate that the controller failed or did not fail? Ask licensee to address concern. Normal action of R 05, would be this action, and is plausible. Remove the very first sentence. This will be Ok In distractors A and B the wording is not consistent with other questions. Need to make clear sentences. B is a clear example of this. Stop and pull to lock 1 B CCP .. Stop and place the 1 B CCP in pull to lock..
KA appears to be Ok. Question is Ok as changed.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1 -5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward KJA Only 4 H 2 B E 025AG2.107, Bank, higher Add to the stem the reference to what procedure these actions are being taken. Is the AOP the appropriate procedure, what Annunciators would be in for this situation? added as requested.
This question identifies that C is the answer, however, the analysis states that D is the answer. Select D as the answer on the questionchanged as requested.
Distractors are not consistent again, need to use additional words to make sentences. Add valves before the listed valves in distractor D. This has changed as requested.
KA appears to match Address above concerns. Question is Ok as changed.
5 H 2-3 N E 026AK3O1, New, Higher For the valves in the stem, add commas where necessary to separate the valve numbers from the valve nomenclature.
Additionally, is open position different from OPEN? Yes there is a difference with the nomenclature.
Place commas in the appropriate positions for the first time the valve and valve numbers in the stem. After the valve number and then again after the noun name and inside the quotes. Done as requested, Ok as it appears..
KA appears to match Otherwise, question appears to be Ok Question is Ok as changed.
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C) CD CO D CO D - Cl) CD 7C. . C) C) CD CD C]. U N 9) D-CD CO <Q C)O (fl(D . C3C) 3 CD CD <DCD_ <C) 3 0 Cl) C) 0 m U) CO D.< CD D . CD Zr (D< -COD 0 CDC)
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- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1 -5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 8 H 2-3 N E 038EA1.17, New, Higher Place in the stem the procedure the operator is expected to do this in accordance with. Changed.
The references provided do not identify the panel or what is necessary to ensure it is open. Had to use Reference material to obtain this information. Understand where these are now.
What is the significance of the M-6 panel, where is it and what valves are you describing when it is used? This is where the operator looks at the valves for blow down.
S Need to add words to make complete sentences. Add the prior to S/G. Verify the red sample valve status light is lit for THE SIG to be sampled on 2-M-6. What panel is this? Have licensee help out to describe what valves they are speaking about.
The Phase A isolated both inside and outside isolation valves and sample valves. While AFW either outside containment isolation valves and sample valves.
What is the significance of the Mode? When you are in mode 3 vs one and two.
Disagree with level of difficulty, its memorization and answering if all you do is apply this. Discuss with licensee.
KA appears to match.
The distractor analysis for C was D and visa versa, chanted.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).
- 3. Check the appropriate box if a psychometric flaw is identified:
- The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
- The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
- The answer choices are a collection of unrelated true/false statements.
- The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
- One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4. Check the appropriate box if a job content error is identified:
- The question is not linked to the lob 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 ciuestions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
- 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD 1 (F/H)
Focus I
(1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-Dist.
Q= SRO B/M/N U/E/S Explanation Link units ward K/A Only 9 H 2-3 N S 054AA2.07, New, Higher KA appears to be ok Question appears to be Ok.
10 H B S 056AA2.56, Bank, Higher KA appears to match Question appears to be Ok.
11 H B S 057AK3.01, Higher, Bank KA appears to match Question appears to be Ok.
12 H B E 058AK1.01, Bank, Higher The second bullet is teaching, is this necessary to answer the question? Can it be said that the 125 VDC power supply is in its normal alignment? I read this incorrectly, this is ok the way it was.
KA appears to be Ok.
Otherwise, question appears to be Ok.
Needed to add assuming no operator action. Wording consistent.
S Changed the stem from greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. To 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Dont use the set point. VF identified that requirements do not need to be in each distractor where it was used. OK as changed.
13 H 2-3 B E 062AA1.07, Bank, Higher Be consistent with how the information that no operator action is taken is standard. This question is different than question #6. Either way is ok, I sort of prefer the way # 6 is done, whatever is easier to accomplish. Changed the stem to Assuming NO operator action.
Used in 6, ok as changed.
KA appears to be Ok.
Otherwise, question appears to be Ok.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD I 1 (F/H) (1-5) Stem Cues T/F Cred. IPartial Job- Minutia #1 j Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. j Link unitsj ward K/A Only 14 H 2-3 M E 077AA1.03, Modified Bank, Higher.
Are there two answers to this question? Why would the manual operation of the Voltage Base Adjuster not be also used to adjust MVARs incoming? As licensee. OK as is, the voltage adjustor is in AUTO and would ONLY be operated in AUTO.
KA appears to match S Is this information concerning the 500 KV line required RO/SRO knowledge? Ask licensee if this is something they expect the operators to know. OK as is.
Otherwise, question appears to be Ok.
15 F 2 N E W/EO4EK1 .1, New, Lower Add to the stem after WOOTF pumps is contributing...NA this is not necessary.
KA appears to be Ok.
Otherwise, question appears to be ok.
RO commented that the 1400 confuses the process and will be hard to determine with the information. SO changes the pressure to 1495 S to ensure the answer will be what we expected.
NEED TO STILL RUN THIS ON THE SIMULATOR.
16 F 2-3 B E W/EO5EK3.2, Bank, Lower KA appears to be Ok.
Change answer to what is said in the analysis. Propose answer to be, To extend the effectiveness of the remaining water inventory in the Steam Generator. Changed as requested.
Otherwise, question appears to be Ok with suggested change.
Q#
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other- 6. 7. 1 8.
(F/H) (1-5) Stem Cues Focus I 1 TIF Cred. IPartial Job- Minutia #/]Back-Link units ward Q=
K/A SRO B/M/N U/E/S Only Explanation 17 H 3 X B U W/E11EK2.1, Bank, Higher.
Put the noun name of valves 72 and 73, in quotes. Also add appropriate words where needed. (i.e. both valves prior to the 1FCV-63-72...)
The reference to the step in the last bullet is not necessary, only refer to what they are doing. The way it is written implies that the applicant should, from memory, know what that step is.
E The question asks wootf will result in the proper alignment of the CSPs under plant conditions. Each distractor puts the applicant at a different part of the procedure. Distractor A puts you in Step 8 to stop pumps if level is below 8%, but then the PTL does not come happen to step 9 b. Made a bad assumption and would not do this, would have to go to step 10. And not do step 9 entirely.
Distractor C is not totally correct, in that, it states to stop one pump (should be in PTL) and cannot allow to swap this is a manual action and only if the sump level is greater than 18% (22%). Ask licensee if this is correct. Added containment sump level of 52% good.
Distractor A does not appear to be plausible.
Add to the stem a value of containment sump level that would be available at that time. Propose that 19%.
Change answer B to read Continue to run both CSPs until RWST level is less than 8%, then swap both CSPs to the RWST. .This suggestion is incorrect should not have done this and did not S
The changed analysis of this question from U to E. Should not have had this. As changed this questions changes were ok.
18 S W/E12 EG2.4.3 New, Higher, This question was NOT in the hard copy.
Question appears to be ok. Capitalize Category and provide a color copy of this to the applicants, if possible.
19 H 3 B 028AK2.02, Bank, Higher KA appears to match Question appears to be ok.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E!S Explanation Focus Dist. Link unitsi ward K/A Only 20 H 2-3 X M U 032AK3.02, Modified Bank, Higher Unmodified question was not provided, could not determine if the question was modified in accordance with the NUREG.
Add to the stem the procedure, it should then read, WOOTF action(s) is required to be taken in accordance with ECA 0.0.
The Answer is the only distractor that has a caveat to it, which provides a clue but not a reason for doing it. KA does not appear to match. In that, there are NO reasons being evaluated.
This question needs to be modified to have two ideas the first being
., stop dumping steam. Add to that, one reason why that is correct and another that is not correct. Then select distractor C and have two
- reasons for those. Thus creating a 2x2 question.
Could not make a 2X2, but added reasons to the distractors.
The sentence concerning the failure of BOTH Source Range Nis does not appear plausible. Need to change this to make it plausible.
Added to the stem to have unit 2 at 100% with N31 out of service.
Now the question will have a loss of SR NIs.
21 H 2-3 N S 033AG2/4/30, New, Higher Question Appears to be ok KA appears to match.
22 F 2-3 B S 036AK1.01, Bank, lower KA appears to match Question appears to be Ok.
A 23 F 2 N S 068AA1 .06, New, Lower, A
KA appears to match Question appears to be ok.
Q# LOK 2.
- 3. Psychometric Flaws 4. Job Content Flaws T5. Other 6. 7. 8.
(F/H) (1-5) Stem Cues Focus T/F I Cred.
Dist.
Partial Job- Minutia #1 Back-Link Q SRO B/M/N U/EiS Explanation units ward K/A Only 24 H 3 X N U 074EA123, New, Higher Change first bullet to read, Unit-2 has experienced a small break LOCA that resulted into entry into FR-Cl, Inadequate Core Cooling.
E While performing FR-Cl, the position of pressurizer PORV block valve KA does not match the question. Are these actions ONLY done in C-1? If not, then it is a generic and has nothing with Cl. If its the only place they occur then it may be Ok. Licensee to discuss.
Question appears to be Ok. The examiner initially diagnosed this as S a U and was incorrect. This question should not have been evaluated as a U but an E. The changes were made as requested.
The KA did match. Not sure why it was initially indentified as a U and not matching the KA.
Question is OK now.
25 L 3 B E 076AK3.06, Bank, Lower KA appears to match Change the numbers each distractor, change from 0.16 and 0.36.
and then change the second part to reflect that the number is now not the first. Just the activity level that would require entry into the
- TS.
Dont like to use set points as the value, this triggers the applicants memory just because of the memory of a familiar number. If the ROs received a chem. Report stating that the value was something S greater than 0.35 then the operator is required to know that entry condition.
Changed this as requested.
26 H 3 N S W/E14EA2.1, New, higher.
KA appears to match Question appears to be ok.
Should the stem have reference to 2-FR-0? Added this i enhancement to the question.
Q# LOK LOD [
- 3. Psychometric Flaws
- 4. Job Content Flaws 1
- 5. Other .6 fE 8.
(1-5)
(F/H) Stem Cues T/F Focus Cred. Partial Job- Minutia #1 Dist. Link I Back-unitsj ward Q= SRO B/M/N U/E/S K/A Only Explanation 27 F 2-3 B E W/E15EK1.2, Bank, Lower, In the stem, the last bullet, does not seem like it should be included.
This short of answers the question incorrectly, remove this from the stem, its not necessary.
KA appears to match, Otherwise, question appears to be Ok. Question was changed, and S added FRZ 2 in the first stem of the question.
28 F 3 N E 003A4.03, New, Lower In stem, first bullet, add the RCP that is being started. The Lift Pump is the pump for #2 RCP. Make this as clear as possible.
Add to each distractors second part, the 1 mm minimum required by the procedure.
S Changed the question as requested. OK 29 F X B U 004K4.08, Bank, Lower, In the stem, it is not necessary to have the nominal pressure of hydrogen in the VCT. Remove this from the stem.
Distractor A, is not plausible, since when does the plant simultaneously start pumps, does not make it plausible just because the NPSH is addressed. Need another distractor.
E Suggestion, Use pressures 15 and 17 and oxygen scavenging and back pressure to the RCP #2 seal and ensure flow to the # 3 seal
Etc.
S Needs work to fix.
OK as changed. Misclassified as a U, should have been an E.
Q#
- 2. 3. Psychometric Flaws 4. Job Content Flaws J 5. Other J 6. 7. 1 8.
(F/H) (1-5) Stem Cues Focus I T/F Dist.
I Cred. Partial Job-] Minutia #/
Link j units Back- Q 1
K/A I
spo B/M/N U/E/S 22L......._
Explanation 30 F 2-3 N EJU 004K5.29, New, Lower, Distractor C does not seem plausible, it ONLY discusses the oxygen concentration and does not address the other limits for chlorides and fluorides because of singling out only oxygen from the stem, why would anyone pick this distractor. Added the other chemicals to the question.
Is distractor B totally incorrect? From the basis of the TS, there is a statement on page B3/4 4-2, that states something similar, in that, it states this for the Reactor Coolant System. Is not the RCP seals part of the RCS? Discuss with licensee to ensure this is entirely incorrect.
VF states this is the basis for sampling not the limits of the chlorides s fluorides and oxygen.
The initial analysis should be an E not a U. OK as changed.
31 H 3 B E 005G2.4.46, Bank, Higher When this phenomenon occurs, where is the temperature indicator?
Cannot find on the procedures/lesson plans. Based on the analysis, it appears that the temperature indicator is some place on the output line on the RHR heat exchanger. Cannot find on simplified drawing.
Have licensee explain how, the isolation of letdown does not stop or reduce leakage. Cannot determine how this would not help or prevent the high temperature alarm.
Have licensee explain how this works and what the applicant has to do to answer this question.
What constitutes the removal of RHR Letdown from service as used in distractors A and B?
KA appears to match.
appears to be ok.
Question CCW side of the alarm, not the RHR side. 1-TI-70-157 is the detector for the temperature of this alarm. OK as is.
32 F 2-3 N 006K2.04, New, Lower Is this something an operator is expected to know from memory? VF and RO stated it is an expected knowledge for applicants. OK.
KA appears to match Question appears to be Ok.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 33 H 2-3 B E/S 007K1.03, Bank, Higher Distractors used in this question appear to have different properties in them, in that, the answer, distractor C states RCP seal leakoff flow is returning to the PRT. While this is true, it should be written as just RCP seal leakoff flow. The part returning to the PRT is not necessary. Or is it? Ask licensee. This part is NOT necessary to provide. Removed as requested.
The same analysis can be applied to distractor D. This distractor is the only distractor that has a reason for the valve opening. Remove this part of the question. D should now read, Valve FCV-68-303, PRT fill valve, fails OPEN. The valve actually fails closed. So VF does not want to put the direction on the distractor.
C should read RCP seal leakoff flow.
S Changed D to Loss of air to the PRT fill valve FCV-68-303.
34 H 2-3 N U 008A2.08. New, Higher.
Place a comma between TS-62-78 and LTD N.
- . In the initial conditions of the question, it states that the ALL other CCS indications are NORMAL. If they are normal, how then in
- distractors A and B, could there be a leak on the CCS header? It appears to me that distractors A and B are not plausible because of this. Discuss with licensee to understand what may be occurring.
Added operator prior to action.
Removed the last bullet, this made this satisfactory question. Does the name of the procedure need to be added? VF leave as it is.
Agree with licensee.
35 H 3 B E 008K1.04, Bank, Higher.
The way this question is worded in the stem is very confusing.
Rewrite this to be less confusing.
KA appears to match.
Question appears to be ok, however, confusing.
Reworded the stem, WOOTF identifies the location of the CCS leak and the resulting plant condition the leak would cause?
OK as changed
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 36 H 2-3 M 01 0K4.02, Modified bank, Not rated for Level of Knowledge. Chief Examiner rated as a higher LOK question.
Original question was not submitted to verity it met the modification requirements. Will not use as a modified question, need to move it back to a bank. This modification does not constitute a modified question.
KA appears to match.
Question appears to be ok.
37 H 3 B S 012A1.O1, Bank, Higher KA appears to match Question appears to be Ok.
38 H 2-3 X B U 013K5.02, Bank, Higher, Distractors A and B are not plausible. When the instrument fails LOW, the instrument opening does not make sense. These need to be fixed.
Ok KA appears to match.
Changed the question to allow for the A and B implausible being S fixed. Added additional words to all distractors see the actual changed question.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 39 L 2 X B U 013K6.01, Bank, Lower, The question as presented has multiple flaws, most of which are plausibility of the distractors. The evaluation of the system is the 214 and this is not really being tested.
Distractor C is NOT plausible, why would a failure of ONE instrument cause BOTH trains to be inoperable, are there any other systems that this type of failure occurs in the entire plant? I would say no.
Suggest to tag out the same instrument then fail another instrument and ask the same questions. This may work then. But have to make sure it does. As it sits now it is not satisfactory.
Low level channel swap over, need 2 of 4 and tagged out the 52.
This made this better, additionally, a failure of an additional instrument made this more relevant.
S Removed the time frame from the test. It really does not matter.
VF states that OPERABLE in the stems are not actually correct. This really mean available. Need to change the words in each distractor.
Changed lots, see changes on the test.
40 H X X B U 022K3.01, Bank, Higher Used on the 2006 Exam WBN The question is NOT specific to the KA, in that, the KA speak about damage, however, this could be stated that the seat leakage or something else that is changing is affected detrimentally.
IN ALL distractors the described conditions have an effect. While they may or may not be significant, they all will have something that is affected. This is the reason why the question as it stands is poor.
There is a fundamental difference on what the statement in the containment means. Examiner believes it is containment equipment, however, the licensee believes it is equipment inside the containment. Discuss with another examiner and the supervisor to see if this is or is not correct.
DISTRACTORS INITALLY WERE NON PLAUSIBLE. A B C AND WAS NOT IMPLAUSIBLE DUE TO THE KA MATCH, s CHANGED THE QUESTION. SEE TEST GOOD AS IS.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD
-j (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 41 L 2 X U 025K5.02, Bank, Lower, KA does not match, The question as written does not address the licensees discussion of the KA match, it does not cover any of the items the licensee identifies in this area. This question only addresss a precaution and Limitation of what is the optimal temperature range.
E THE KA covers the ice condenser and its ability to for heat transfer.
This question tests how this is accomplished, ie for a LOCA and how the system works.
Question is Ok, however, it does not match KA Replace question.
Was the examiners Initial characterization incorrect? This question may be ok, ask other examiners. 18 and 27 (TS limit) and then the heat transfer part. Use, second part, maintain with in ts limits, and or use sublimation. ?? Review to see what to do.
Changed the question to make it 18 or 27 and excessive concrete expansion or outside tech spec limit.
MB stated the questions does meet KA. Mischaracterized initially.
42 H 2-3 B E 026A3.01, Bank, Higher.
In the analysis of this question, the time used is 184 seconds, however, in all the reference material this time is 180 seconds or 3 minutes. It is 180! Changed in this.
In the question the applicant has to assume that the EDGs loaded on their respective buses at time 1205, and about 30 seconds. 10 seconds for the DG to start, and the first 4 steps being completed. Is this something we want the applicant to assume? Discuss with licensee if this needs to be identified more clearly. Also is it important for us to make sure that the position of the CS switches are in standby readiness and in A-Auto, etc. Discuss! MB states that this is not necessary. Examiner agrees. Nothing needs to be done.
KA appears to match.
s Question appears to be Ok. Waiting final outcome of discussions above. Question is sat as it was submitted.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD F
(F/H) (1-5) Stem Cues Focus T/F I Cred.
Dist.
Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EIS Explanation Link units ward K/A Only 43 L 2 X B U 026A4.01,. Bank, Lower, KA appears to match CSS is actuated via the phase B controls.
Questions distractors A and B are NOT plausible. Everyone knows that there has to be two switches manipulated and this will not do.
The licensee took offense to that that, everyone would not know this from memory. Change to have one switch in each of the opposite pairs has to be manipulated to operate.
F This will make this question a little higher level of knowledge.
What was the spread of answers for this question, if any spread at all? From validation. This was validated as 100% correct. Done by requal operators.
S Examiner mischaracterized this question as a U. This should have
, been evaluated as an E not a U.
- The question was rewritten to make distractor A to read, Operation of any one of the 4 handswitches will actuate both trains.
Rewrote distractor to read Operation of either 1 HS30-64A or 1 HS30-68A (M-5) will actuate train A ONLY.
Added handswitches to switches in both C and D, also, stated that distractor D was taken the two switches and to pair.
44 H 3 B EIS 039A3.02, Bank, Higher KA appears to be ok Distractor A, add BOTH to the front of the distractor.
For all the distractors, start with SI and end with MSLI, or visa versa.
It does not matter, just make sure they are in the same order. It makes it harder to read the question when they are different. Did as S suggested.
Otherwise, question appears to be Ok. IS Ok. As changed.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD r (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 I Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link unitsi ward K/A Only 45 H 2-3 X B EJS 059K3.02, Bank, higher.
KA appears to match.
Since the answers are concerning the Unit 1 AFW pumps, how about customizing this question to be unit 1 specific, by changing the information in the stem to Unit 1. Changed as requested, made it a unit 1 question.
Or, just change the answers to be more generic if that can be done.
In other distractors, the word ONLY has been capitalized. So be consistent with whatever convention is used followed this suggestion also.
Otherwise, question appears to be Ok.!
46 H 2 X X B U 059K3.03, Bank, higher.
The stem needs to be made tighter. In that, the word used APPARENT to the operators. This is NOT concise enough, because it means where the operator happens to be looking at the time. Tighten up to insure we are asking the correct question.
Question has many non plausible distractors. Distractor B would take a long time to be seen by the operator. Replace with something more plausible and not requiring the system feedback from secondary to primary.
Change distractor C, to decreases, now the applicant has to determine which comes in first.
Distractor A is the only annunciator, the licensee KA match determine states that the applicants were to determine which indications (alarms) would be generated first. This is incorrect! There is only one annunciator that is provided. Also this distractor is the only one that is ALL Capitalized. Gives it a clue it may be the answer.
Will come up with 4 alarms, and will go over this again, S Changed this question to use the alarms.
Looks good, need to run on simulator to determine if there is an issue with how the applicants have to answer this.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 47 H 2-3 X X B U 061 K6.02, Bank, Higher.
Distractor C is not plausible, change flow to 220 and change D flow to 440. This is at least in keeping of the correct flow from the answer.
The stem talks about AFW alignment, this would be something like the pumps that are running, but we have the generators that are being fed and the flow. The stem does not speak to the flow, so that has to be fixed also.
E WOOTF describes the SIGs that will receive AFW flow and the expected flow rate to those S/Gs. Or something like this! Discuss with licensee. Accepted this comment.
Distractor C does not seem plausible, in that, I dont remember when a flow value of 110 gpm for each SG is provided to the SGs. Discuss with licensee. Will accept this as not credible, changed this distractor to use the 1 and 2 or 3 and 4 SGs and then use 220 or 440 as the second part of the question.
OK as changed.
Initial characterization should have been an E. There was only one S non credible distractor. Upon review with the licensee, this should not have been a U.
48 H 3 N E/S 062G2.4.35, New, Higher.
Teaching in the stem. Remove starr from second bullets. OK no change necessary. Capitalize Safety Injection for consistency.
Third bullet, add comma after EA-82-1, Tighten the stem by referencing the Procedure EA-82-1. Added AT the last sentence of the stem, add words MUST BE found a technical error themselves. Separated this to be more easy to ready.
KA appears to match, Otherwise question appears to be Ok.
49 H 2 B Sj 063A4.01, Bank, Higher, used on audit exam 1/2009 Question used on previous audit KA appears to match, Question appears to be ok.
Q#
1.
LOK 2.
- 3. Psychometric Flaws
[
- 4. Job Content Flaws fi---
[ 5. Other
- 6. 7. 8.
(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 I Back-I Q= SRO B/M/N U/EIS Explanation Focus Dist. j Link unitsi ward K/A Only 50 H X N U 064A2.05, New, Higher, Question doesnt appear to match K/A. Dont see how the question addresses the use of procedures to correct, control or mitigate the consequences REPLACED THIS QUESTION TO MATCH KA. NEW question S appears to be ok.
KA matches.
51 B S 073.A1.01 52 F 1 X X B E 073K1.01, Bank, Fundamental.
(LOD) Should avoid using best. It appears that two of the distractors can be immediately dismissed based on the alarms received what occurs when a hicjh rad alarm is received and why Information for RICK....
Appears that the first two answers/distractors could be discounted because they do not run ever. The answer or control building emergency air pressurization fans start on this signal.
Change A and B to Main Control room Air handling unit. This will make it better.
53 F 2 N S 076K2.08, New Lower, 54 F 1 X X M U LOD as written. The stem appears to ask what must/should have occurred to maintain Air Header Pressure for the given conditions. I would think that based on what is asked, distractors A, B & C are not plausible. Please answer what pressures would be/or could be maintained if actions taken in distractors A, B & D are taken.
E In this question, the distractor s that each of the distractors provide different components compressor is 77 pounds, isolation valve is 69 S pounds, service air receiver, Should have been characterized as an E.
Changed the stem to have should have vice would have
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 55 H X B E Distractor A is not plausible. Not sure of any mechanical equipment malfunction which would require an evacuation of containment.
Provided information if there is.
Changed A second part, to Place Rx Vessel Head on stand.
S Reworded the stem to reflect the way the table is. See question.
56 F 2 B S 57 H 3 B S 58 H 2 X B S?/U 017K3.01, Bank, higher.
The question appears to be OK, however the use of the words several and slightly could be challenged. Several could mean 2 or more and slightly could mean 1-2????? This could result in several correct answers. ES-O.1 for both running and stopped RCP says stable or trending between 547 and 552. Please explain The question appears to be Ok as is.
Question matches the KA.
59 F 2 B S 60 F 2 N S 61 F 2 M S 62 F 2 B S 63 F 2 B S 64 F 2 X N E 071 A3.02, New, Lower, Not sure why one would think that closing the pressure control valve would be plausible as in Distractor A The suction control valve is not credible, when do you throttle the suction of any pump? This will be changed in distractors A and C to S the discharge throttle valve. This makes more sense and does not accomplish the task as discussed in the question.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD I (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EIS Explanation Focus Dist. j Link units ward K/A Only 65 H 3 N S 075A2.03 66 F 1 B S/U G2.138 LOD. Addressed KIA. This area is tested through simulator scenarios. Would suggest replacing the KIA if it is not too late The new KA is G2. 1.32, was used to prevent the overlap of competencies in the question and the simulator scenarios. This new S question covers operation of pumps with successive motor starts.
OK meets ka and question is Ok.
67 H 2 X X B U G.2.1.7 bank, higher.
Should stem state according to plant procedure? Distractor B & D do not appear to be plausible. Do not see why starting the AFW pumps would be acceptable. Even if starting the pumps were acceptable and we make the assumption that parameters are restored, why would one trip the turbine.
AOP Si, Main feed water malfunctions. Added this.
Changed this question significantly. See exam for changes.
68 F 1 B S LOD 2-3 Changed the question that added information to make the level of difficulty higher, KA matches a Question is Ok.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/h) (1-5) Stem Cues Focus T/E Cred. Partial Job- Minutia #1 Dist. Link I Back- Q= SRO B/M/N U/E/S Explanation unitsj ward K/A Only 69 F 1 X M U LCD Not able to identify information in the procedure to support answer. Distractor D is not plausible. Why would one think that a procedure that need a minor editorial change would be placed on hold?
E G.2.2.6, Modified, Higher.
Change distractor D to read Process a Minor Editorial Change.
Did not have the appropriate references but were available during combined review.
S Question was mischaracterized as a U. This should have been
., characterized as an E. Question change is ok.
70 H 2 X B U Distractor A is not plausible. Do not know of any reasons to dispatch radcon to control room. It appears that distractor C may also be correct based on information provided. RM-103 is increasing.
Distractor D, which is the correct answer appears to lead the applicant do the fact that the stem talks about SFP and the answer reads High Radiation in the SFP area 2-3 E G2.3.13, Bank, Higher Changed bullet to have fuel shuffle in progress.
Changed both distractors C and D, Verify the Auxiliary Building General Supply and Exhaust fans are shutdown, manually actuate BOTH A and B train Auxiliary Building Isolation.
And D reads now, similar to the c but only the A train to start manually.
S Mischaracterized the evaluation of the question it should have been an E and not a U. Changed from U to E and changes to S.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1 -5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 71 F 2 B 5? Provide information on each of the monitors identified in distractors A, C & D. Unable to identify them in any procedure G 2.3.15, Bank, Lower, Are expected to know, above the line on TS5. OK for RO knowledge.
Need to change the noun names of what is actually listed on the radiation monitor, this needs to be done to ensure that an applicant does not have an excuse that an incorrect noun name threw them off of the answer because of incorrect nomenclature.
72 H 1 B S LCD 73 F 2 N S 74 H 3 B S 75 F 2 X B U As the question is written it appears there could be two correct answers. A & C. Distractor D is not plausible dont see why applicant consider D.
Distractor D was not totally incorrect, made so that the distractor encompassed the whole procedure by adding anytime making it incorrect.
E Distractors C (the answer) and D could almost be considered correct.
Removed from the stem the statement ECCS flow injecting. This made B almost the same as C. Implausible.
C was not correct.
S This should have been an E not a U.
KA Ok and question now as it appears is Ok.
SRC Only 76 F 2-3 N 029EA2.06, NEW, KA matches While this question is a lower level question, it appears to be ok.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD unitsjI ward (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= Fo B/M/N U/EIS Explanation Focus Dist. Link K/A Only 77 H 2-3 B E 038EG2.2.40, Bank KA matches Distractor D, is not plausiblel The target temperature usually is determined by the associated SG. Since there is NO steam generator pressure to figure out what the target temperature, this could not be credible as a distractor.
Select another Distractor for D.
S Spell out Tech Spec, changed distractor D to add the 100 deg F for cool down in TS. OK as changed.
78 H 3 N E 054AG2.4.30, New, The second bullet in the initial conditions is to long to read. It also does not explicitly allow the reader to determine that the TDAFW pump is out of service and provides an element of teaching. Shorten this and that the TDAFW pump is OOC. Added TDAFW tagged out.
KA appears to match S Remove from stem the yellow path reference.
79 H 3 N S 055EA2.03, New, KA appears to match Appears to be Ok.
80 H 2-3 N E 058AG2.4.18, New KA appears to match Teaching in the third bullet. Remove the word three from the sentence. They should know that there are three other SD boards.
And add to the 2A shutdown board as being the ONLY SDB being powered. Remove the reference to three other SDBs being without power. Did this, appears to be Ok.
In the initial conditions should the word complete be completed?
Why didnt the writer use EA-250-1 in either distractors a or b? This also would be untrue. Will change A to have 250-1, for the 250-2.
Question appears to be Ok.
S
1.
Q# LOK LOD a 3. Psychometric Flaws
- 4. Job Content Flaws J
-if---
- 5. Other 7. 8.
(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 81 H 3 N 077AA2.08, New, higher KA appears to match This question relies upon the use of the ARP for the answer.
Normally, ARPs are NOT used from Memory. It appears that both parts of the answer come from the ARP. It this acceptable to expect the SRO applicants to have to memorize. Discuss with licensee to ensure this is what was expected while answering this question.
VF is concerned that this question will be a high miss question because there is no alarms in the simulator that cover this. VF believes that this question as written is beyond the memory level of what an SRO is expected to know from memory about ARP5. Would like to have another KA to replace this KA.
REPLACE THIS KA What is the significance of having the inter-tie transformer tap in manual? Please explain.
This question was initially characterized as a U incorrectly. This should have been an E and not U.
THE NEW KA is 077AA2.07, Generator Voltage 82 H 2-3 B U 001 AA2.02, Bank, KA appears to match The distractor analysis for distractors C and D, identify that there would be some flow with dual light indication in C but no flow in D.
This does not follow with the premise that this would be true. While the distractors state there is NO flow, why would anyone believe that dual indication would result in no flow?
It appears from the above discussion, both distractors C and D are not plausible. Discuss with licensee.
In slow speed BAT transfer pump to slow all time. If the valve (throttle valve). Changed the first distractors and made the flow control valve open with no flow and the intermediate valve with flow.
S Question appears to be Ok as changed. Look at test to identify changes completely.
Q#
1.
LOK 1I 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. 7. 8.
(F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only j,
83 H 2-3 N U 060AG2.4.21, New, higher Not sure if it is clear that the high Radiation levels are on Unit 1.
Make sure it is clear. Appears to the licensee.
Since the LCD is not a short period LCD, meaning hour or less is it reasonable for the SROs to be required to know this TS? As licensee if this is ok to make sure we test the appropriate items.VF expects the SROs to know this 3.0.3 from memory. ROs do not have to know this.
Is it a true statement that the EGTS system will automatically start on the conditions listed in the initial conditions of the question? If this is true, the operator merely has to identify that the system auto-starts and aligns automatically. If this is the case, there is no analysis of the safety functions listed in the KA. I do not believe the KA is being met because of this. Discuss with licensee to understand system requirements.
KA does not match.
Does it meet the KA. And is it an SRO ONLY This is SRO only, and the KA does meet, met with another examiner s and found this does meet the requirements of both the SRO and KA match.
Question is Ok.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK L0D I (F/H) (1 5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. j Link units ward K/A Only 84 H 3-4 M S 061AA2.01, Modified Bank, Higher Trivial, on third bullet, there are two periods in a row.
In bullet 4, there is a reference to a radiation monitor, 0-RM-90-102, in the third bullet, the same name is used for the rad monitors, however, the rad monitor number is 103. Are they the same or, is this a mistake? Licensee to review. The same name but different trains.
Question is modified bank, in order to determine if it was modified as required by 1021, the bank question needs to be provided which it was not. Provide bank question for review. Or identify what was changed from the original bank question.
This question appears to be complicated and would need references, however, the questions references are not required to answer the question. Is this expected of the SROs to know this detail of the TS without TSs? Yes its complicated the TS 3.9.12, the answer to determine if this is entered is located in the 18 month surveillance requirements. Because this is buried in this it would seem unfair and unreasonable to NOT allow this TS to be used. Will allow this TS to be provided for the exam.
Discuss with licensee to show me how the switch manipulations in I the IC effects or does not affect the answers. Understand what this KA appears to match.
85 H 2-3 N E 069AG2.4.21, New, Higher The question itself states that References are provided, however, on the page that provides the references that developed this question, there is a place that identifies references provided, this states NONE as the references provided. This conflicts each other. Ask licensee which is correct. Clarify what references are being provided. Just the 3.6.1.3 TS will be added and not the basis. This is Ok.
If the basis is provided then the questions second part will become a direct look up.
S KA appears to match.
Question is Ok as is.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 7. 8.
Q# LOK LCD I (F/H) (1-5) Stem Cues TIF Cred. IPartial Job- Minutia #1 Focus Dist. Link I Back-unitsj ward Q= SRO B/M/N U/EIS KJA Only Explanation 86 H 3 X B EJU 012A2.O1, Bank, Higher Distractor D, is NOT plausible, if the function was operable, why would the crew have to do a down power?
The way this question is written is backwards, at least I think. Which part of the distractor, 1 cr2, is being used for the part 2 of the KA.
This is an important distinction concerning the way it is analyzed. OK If the KA is evaluated with the use of TS or the use of the procedure.
This is very close to not being SRO only. In that, the individual can, in fact, could answer this with RO knowledge. See below.
Need to discuss with licensee to see what their idea was when this was written. Not sure this is SRO ONLY. IN the stem the reference to the TS has been removed. This will require the SRO to then have to determine the TS which is being used RO knowledge however, s there are two functions below the line that have to be analyzed which is SRO.
Question was changed to shorten the stem by pulling out common parts. OK Question is OK 87 H 3 B E 039A2.03, Higher, Bank, To answer this question, the operator has to identify the loop with higher radiation level. Why not provide loop 3 as the other answers rather than loop 1? This would make it more plausible and would also increase the level of difficulty.
Since there is really NO information concerning if a saturated recovery was required. What in the stem would make the applicant think this? There was no information that would require the applicant to know this. The RWST level was added to allow the applicant to distinguish this information. OK as Changed.
distractors C and D to Loop 3.
Change Changed the value in C and D Swapped, because these are normal readings. So then the loops being looked are 2 and 4 vice 1 and 2 88 H 2-3 B S I 076G2.4.4, Higher, Bank KA appears to match, Question appears to be ok.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q SPO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A 10n1y 89 H 3 X M U 078A2.O1, Modified Bank, Higher.
Question meets modification requirements.
This question appears to be answerable with ONLY P0 knowledge.
RO knowledge is system knowledge for the system bypass. Based on the information provided in the stem the applicant can use system knowledge to answer the first part.
The answer to the question mislead that answer B was marked as the answer this was not the answer but B, this provided impetus for calling this unsat initially.
The second part can also be answered by system knowledge. If the applicant knows from system knowledge, what will happen with the AFW system on a loss of auxiliary air, then they can determine what TS action to enter. Disagree with SRO only designation.
S A misunderstanding of the Basis of the effect of loss of one train of instrument air, was the basis for making this a Unsat question. The licensee presented information the examiner did not know/understand and this question should have been identified as a S.
90 H 3 B S 103G.2,4,21, Bank, Higher KA appears to be ok Question appears to be Ok.
91 H 3 N S 028A2.01, New, Higher KA appears to be ok 92 H 3 N jS Question appears to be Ok 068A2.04, New, Higher KA appears to be Ok.
Question appears to be Ok.
Q# LOK 2.
- 3. Psychometric Flaws t
F . Job Content Flaws T
- 5. Other I
- 6. 7. 8.
(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= ISRO B/M/N U/EIS Explanation Focus Dist. Link units ward K/A jOnly 93 H 3 X M U 071 G2.2.36, Modified Bank, Higher Add commas to the stem before and after the procedure number and name. Added as suggested.
This question is not SRO only. To answer the first part of the question this requires RO system knowledge. To answer the second part, for distractors basically would be RO knowledge that you need both radiation monitors for the release to be allowed.
If the release was terminated by the system, and both are required for the release one could surmise that only one rad monitor is NOT sufficient to allow the release without doing something. I dont believe that the second part of distractors B and D are plausible.
Discuss with licensee.
This is a chemistry procedure that is administrative and controlled by the SRO. This then is based on the release permission and is expected to be SRO only in nature in accordance with Clarification S for SRO only.
This question should have been designated as an S and not an Unsatisfactory.
94 F 2-3 N S I G2.1.27, New, Lower KA appears to match Question appears to be ok.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD r (F/H) (1 -5) Stem Cues T/F I Cred. Partial Job- Minutia #1 Back- Q= I SRO B/M/N U/E/S Explanation Focus Dist. Link K/A units ward 10n1y 95 H 3 N E G 2.2.18, New Higher, This question is a series of true or false statements that are to be evaluated against the requirements of the procedure appendix that is being used as a reference.
Diving while being High risk, is not listed in the procedure provided.
While this may be the case, the applicant could evaluate this as not the answer because of it not being there. This is considered non-plausible. This distractor needs to be changed.
KA appears to be Ok.
After discussion with licensee, this distractor will be allowed. It could be misunderstood that this will affect the other unit.
S Question as is is Ok.
96 H 3 N E G2.2.40, New, Higher The question proposes a scenario then asks what to do prior to Mode 4 entry. The question uses the statement if any, as if there is NO answer. This should be removed from the question stem. This makes no sense here. Accepted.
Distractor C is non-plausible, in that, the TS 3.4.1.2, requires 2 SG5 and 2 RCPs, however this is for MODE 3. Change this to 2 and it will be more plausible. Accepted.
KA appears to be Ok S
Question appears 97 F 2-3 B EJS G 2.3.12, Bank, Lower Level, Question used on 1/2009 SRO Audit examination.
In the stem, underline the word maximum or capitalize it, whatever is better to get the applicants attention. Accepted.
KA appears to be ok.
Question appears to be Ok.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 98 F 2-3 X X B U G2.3.14, Bank, Lower The procedures operator actions states Stage I at 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and Stage II at 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />. This makes the answer trivial.
Do not believe that the question matches the KA. The KA Is Radiation control, Knowledge of radiation contamination hazards that may arise during normal, abnormal or emergency. This question ONLY asks the time for Stage I to start and what actions.
Asked other examiners and they said this could be used, the KA can be linked that way. Should have been an S to begin with.
S Ok as is.
99 H 2-3 X B U G2.4.30, Bank, Higher While this question appears to be SRO only, it basically is RO knowledge that the first declaration made has to be done in 15 minutes. Since ROs are normally the communicators of this information to the State this is knowledge they have and can be answered with only that knowledge.
KA appears to match Shift Manager only at SQN. Not communications (RSs). They do not support the emergency plan. At Sequoyah. Since the ROs at SQN do not do this, and there is a complication of an ODS. Operations Duty Specialist. In Chattanooga, the RO has nothing to do with this.
Initially mischaracterized this as a U, should be an S.
Question as is, is an S.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 100 H B E G2.4.46, Bank, Higher The question the way it was written is confusing, in that, the second part of the question is asking A basis.. This is confusing in that the basis is NOT linked to anything in the question other than the charging pump is running.
Change the wording of the second part for the actual answer to a paraphrase the TS and not verbatim extraction from TSs.
KA appears to be Ok.
Changed the System from 3.5.2, to 3.5.1 made a better match, all that was necessary to change.
S Question is Ok as changed.
ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Sequoyah Nuclear Plant Date of Exam: 09/29/2010 Exam Level&
Initials Item_Description a b c
- 1. Clean answer sheets copied before grading RSB NA
- 2. Answer key changes and question deletions justified and RSB NA documented
- 3. Applicants scores checked for addition errors RSB NA (reviewers_spot_check>_25%_of_examinations)
- 4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, RSB NA as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail
- 5. All other failing examinations checked to ensure that grades RSB NA are_justified
- 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of RSB NA questions_missed_by_half or more of the_applicants Printed Name/Signature Date
- a. Grader Richard S. Baldwin 12/03/2010
- b. Facility Reviewer(*) NA
- c. NRC Chief Examiner (*) Bruno Caballero / /2-3-jo
- d. NRC Supervisor (*) Malcolm T. Widmann /
(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.