ML13225A166
| ML13225A166 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/08/2013 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-335/12-301, 50-389/12-301 | |
| Download: ML13225A166 (60) | |
Text
ES-201 Examination Preparation Checklist Form ES-201-1 Facility: 2012 St. Lucie Date of Examination: 12/3/12 Facility NRC Examinations Developed by:
Written / Operating Test Written / Operating Test Chief Target Task Description (Reference) Examiners Date*
Initials
-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) PGC
-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) PGC
-120 3. Facility contact briefed on security and other requirements (C.2.c) PGC
-120 4. Corporate notification letter sent (C.2.d) PGC
[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] PGC
{-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-1's, ES-401-1/2, ES-401-3, and ES-401-4, as PGC applicable (C.1.e and f; C.3.d)
{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility PGC 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, PGC 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 398's) due (C.1.l; C.2.g; ES-202) PGC
-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202) PGC
-14 11. Examination approved by NRC supervisor for facility licensee review PGC (C.2.h; C.3.f)
-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) PGC
-7 13. Written examinations and operating tests approved by NRC supervisor PGC (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 PGC (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)
-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee PGC (C.3.k)
-7 16. Approved scenarios, job performance measures, and questions distributed to PGC 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.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: _St. Lucie______________________ Date of Examination: 12/3/12 Examination Level: RO X SRO X Operating Test Number: HLC 21-NRC Administrative Topic Type Describe activity to be performed (see Note) Code*
A1 - Determine Time SDC Entry Conditions Are Required Based Upon Available CST Level Conduct of Operations D, P, R A2R - Manually Calculate Linear Heat Rate Using Excore Detectors.
Conduct of Operations N, R A2S - SROs Will Also Identify T.S. Implications N, R A3 - Develop ECO for 1A AFW Pump Impeller Replacement.
Equipment Control A4 - Determine Stay Time for Workers Radiation Control M, R A5S - Respond to a Tornadic Event Emergency Procedures/Plan N, R 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)
ADM. JPM
SUMMARY
DESCRIPTION A1 - Determine Time SDC Entry Conditions Are Required Based Upon Available CST Level Given Hot standby conditions the Applicant will use 1-EOP-99, Data Sheet 1, Determination Of Condensate Required to remove Decay Heat and RCP Heat to determine the time SDC entry is required.
A2R - Manually Calculate Linear Heat Rate Using Excore Detectors.
A2S - SROs Will Also Identify T.S. Implications Unit 2 is at 100% power when the Incore instrumentation feed to DCS has been determined to be failed and the Incore Instrumentation system has been declared inoperable. Using 0-NOP-100.03, Monitoring Linear Heat Rate the Applicant will manually determine the Linear Heat rate.
SRO(U)(I) will determine the applicable Tech Specs associated with the failure of the DCS to determine linear heat rate.
A3 - Develop ECO for 1A AFW Pump Impeller Replacement.
Unit 1 is at 100% power. The Applicant will be required to develop an Equipment Clearance to repair the 1A Auxiliary Feedwater pump due to a cracked pump shaft.
A4 - Determine Stay Time for Workers Unit 1 is in a Refueling outage. There will be four(4) workers assigned to free CEAs that were caught on the UGS when the UGS was being lifted. The Applicant will be required to determine the dose received, the approvals required and which worker(s) will be allowed to perform the task.
A5S - Respond to a Tornadic Event (SRO)
A Tornado has touched down in the Owner Controlled area. As Shift Manager, they will be required to classify the event and fill out the State of Florida Notification Form. (portions of this JPM are time critical)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __St. Lucie__________________ Date of Examination: 12/3/12 Exam Level: RO X SRO-I X SRO-U X Operating Test No.: HLC 21-NRC 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 All (S-1) Verify MSIS - Unit 2 (0821016A) K/A: 039-A4.01 A, D, EN, S, L 4s (S-2) Respond to Abnormal Pressure Control - PCV-1100E Fails A, E, N, S 3 Open - Unit 2 K/A: 010-A2.02 (S-3) Align the 2A1 SIT to VCT for RCS makeup. K/A: 004-A4.13 E, L, N, S 2 (S-4) Respond to high radiation alarms in the Spent Fuel Pool K/A: A, M, S 7 072 A3.01 (S-5) Perform Reactor Startup Pull CEAs to criticality - Unit 2 (trip A, L, N, S 1 unit when rods continue to withdraw) K/A: 001-A2-18 RO Only All (S-6) Perform a containment mini-purge on Unit 2. K/A 028-A4.01 N, S 5 All (S-7) Perform Appendix J After Inadvertent SIAS - Unit 2 A, D, E, S, L 8 K/A: 008-A4.01 (C-1) Vent Reactor Vessel Head Using RCGVS - UNIT 1 C,D, E 4p K/A 002 K4.03 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
All (P-1) Release 1A Waste Monitor Tank Contents (0821169) D, R 9 K/A: 068-K4.01 (P-2) Disconnect 1B Instrument Inverter from service for preventive D, P 6 maintenance - Unit 1 (0821067)
K/A: 062-K1.03 All (P-3) Align Unit 2 CST to Supply the 1C AFW Pump (0821062) P, E, M 4S K/A: 061-K4.01
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator JPM
SUMMARY
DESCRIPTION S-1 Verify MSIS - Unit 2 Direction is given to perform Table 5 of EOP-99 to verify MSIS during a LOCA. MSIV on the B side, HCV 1B will indicate open and should have closed on the MSIS. Main Feedwater Isolation valve, HCV-09-2B also has failed to close on MSIS. Both of these valves are capable of being closed from the Control room.
S-2 Respond to Abnormal Pressure Control - PCV-1100E Fails Open - Unit 2 The Unit is at power when PCV-1100E, Pressurizer spray valve failed open. The valve cannot be closed from the Control Room. Success path is to trip the Reactor and stop the 2B2 Reactor Coolant pump to terminate the depressurzation.
S-3 Align the 2A1 SIT to VCT for RCS makeup.
Unit 2 is in Mode 3 with RCS pressure less than 1750 psia. The RWT, PWT and BAMTs are unavailable. An RCS cooldown is to be performed. The 2A1 Safety Injection Tank will be aligned and used to makeup to the VCT during the cooldown.
S-4 Respond to high radiation alarms in the Spent Fuel Pool - Unit 2 Refueling operations are in progress. High radiation alarms are received in the Spent Fuel Pool. The applicant will be required to verify proper operations of the Fuel Pool ventilation system for the stated conditions. Various fans and one damper will be out of position. The Applicant is required to identify these mispositioned components and place them in the correct position.
S-5 Perform Reactor Startup Pull CEAs to criticality - Unit 2 (trip unit when rods continue to withdraw)
The Unit is performing a Reactor Startup IAW 2-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2. When Reg. Group 3 reaches the upper group stop Reg Group 4 will continue to move outward. Efforts to stop the movement is not successful. The Applicant should manually trip the reactor.
S-6 Perform a containment mini-purge on Unit 2 The Unit is at power. Direction is given to perform a Containment mini-purge to reduce Containment pressure.
Using 2-NOP-25.02, Continuous Containment / Hydrogen Purge System Operation the Applicant will align the system and start the Purge.
S-7 Perform Appendix J After Inadvertent SIAS - Unit 2 An inadvertent SIAS has occurred. Direction is given to restore CCW to the Reactor Coolant Pumps using Appendix J of EOP-99. The Appendix states to use the lineup for the A CCW header OR the B CCW header (not both). Which ever header the Applicant uses the valve will not open. He will be required to choose the other CCW header to be successful.
C-1 Vent Reactor Vessel Head using RCGVS - Unit 1 A LOCA has occurred on Unit 1, forming a non-condensable bubble in the reactor vessel head. Pressurizer level has been restored to 80% with Pressurizer pressure at 650 psia.
The subsequent actions of 1-AOP-01.12 have been completed up to the point of venting. Calculations show the void size is about 800 cubic feet, and the maximum vent time is 31 minutes.
Direction will be to vent the Reactor Vessel Head P-1 Release 1A Waste Monitor Tank Contents (0821169)
(Radiation Controlled Area JPM)
Applicant will be directed to perform a liquid release IAW 1-NOP-06.01, Controlled Liquid Release to the Circulating Water Discharge.
P-2 Disconnect 1B Instrument Inverter from service for preventive maintenance - Unit 1 (0821067)
The 1B Instrument Inverter is to be removed from service for maintenance. The Instrument bus will be placed on the Maintenance Bypass Bus IAW NOP-49.05B, 120VAC Instrument Bus 1MB (Class 1E) Normal Operations.
P-3 Align Unit 2 CST to Supply the 1C AFW Pump (0821062)
Unit 1 CST is not available due to tornado damage. Direction will be given to align the Unit 2 CST to the suction of the Unit 1, 1C Auxiliary feedwater pump IAW 1-AOP-09.02, Auxiliary Feedwater, Attachment 5.
ES-301 Operating Test Quality Checklist Form ES-301-3 II Facility: I St. Lucie I Date of Exam: I 12/3/2012 I Operating Test No.: 1 II
- 1. General Criteria Initials a b
. c#
NA NA
~
- a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g. 10 CFR 55.45, operational importance, safety function distribution).
! ! ~
- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
! ! ~
- c. The operating test shall not duplicate items from the applicants' audit test(s). (see Section 0.1 .a.)
- d. Overlap with the written examination and between different parts of the operating test is within
! ! -rt acceptable limits.
! ! ~
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
- 2. Walk-Through Criteria -- -- --
! ! ~
- a. Each JPM includes the following, as applicable:
- initial conditions
- initiating cues
- references and tools, including associated procedures
- reasonable and validated time limits (average time allowed for completion) and specific 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
! ! -rt 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 on those forms and Form ES-201-2.
- 3. Simulator Criteria -- -- --
! ! ~
The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
Printed Name I Signature Date NA DDeveloped by NRC (D. Lanyi) NA
- a. Author
- b. Facility Reviewer (*) NA NA
- c. NRC Chief Examiner(#) Phillip G. Capehart I
~(~~ 1010212012
- d. NRC Regional Supervisor &A.4.tf..d.u"'f. WtlUM'/~ 1;¥: - -
1010212012 Note:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column Ac::; chief examiner concurrence required.
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: St. Lucie Date of Exam : 12/03/12 Scenario Numbers: 1 / 2 / 3 / 4 / 5 Operating Test No.: 1 QUALITATIVE ATTRIBUTES Initials a b* c#
- 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out NA NA of service, but it does not cue the operators into expected events.
- 2. The scenarios consist mostly of related events.
- 3. Each event description consists of
- the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position)
- the event termination point (if applicable)
- 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
- 5. The events are valid with regard to physics and thermodynamics.
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints.
Cues are given.
- 8. The simulator modeling is not altered.
- 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator 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.
- 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).
- 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 (5-8) 6/ 5 / 7 / 7 / 7
- 2. Malfunctions after EOP entry (1-2) 3/ 1 / 2 / 2 / 2
- 3. Abnormal events (2-4) 3/ 3 / 2 / 4 / 3
- 4. Major transients (1-2) 1/ 1 / 2 / 1 / 2
- 5. EOPs entered/requiring substantive actions (1-2) 2/ 2 / 2 / 1 / 2
- 6. EOP contingencies requiring substantive actions (0-2) 0/ 0 / 1 / 0 / 0
- 7. Critical tasks (2-3) 3/ 2 / 2 / 3 / 2
ES-301 Transient and Event Checklist Form ES-301-5 Facility: St. Lucie Date of Exam: 12/3/12 Operating Test No.: HLC 21-NRC A E Scenarios p v p E 1(30%) 2( 5x10" 4
) 3(100%) 4(10-12%) T L N 0 I T T MINIMUM c CREW POSITION CREW POSITION CREW POSITION CREW POSITION A
A T L N y p
s A B s A B s A B s A B T R T 0 R T 0 R T 0 R T 0 R I u E 0 c p 0 c p 0 c p 0 c p RX 1 1 1 1 0 NOR 2 1 2 1 1 1 SROI-1 1/C 3,4,6,8, 4,7 2,5, 10 4 4 2 9 8 MAJ 7 6 7 3 2 2 1 TS 1,5 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 2 1 1 1 R0-1 1/C 4,8, 2,5 5,7 7 4 4 2 9
MAJ 7 6 6 3 2 2 1 TS 0 0 2 2 RX 2 1 1 1 0 NOR 1 1 2 1 1 1 2,4, SROI-6 1/C 3,6 5,7 2,3,5, 12 4 4 2 6,8,9 MAJ 7 6 7 3 2 2 1 TS 3,5 3,4 4 0 2 2 RX 1 1 1 1 0 NOR 2 1 2 1 1 1 SROI-2 1/C 3,4,6,8, 5,7 2,5, 10 4 4 2 9 8 MAJ 7 6 7 3 2 2 1 TS 1,5 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 2 1 1 1 R0-2 1/C 4,8, 3,8,9 3,6, 4 4 2 9
9 9 MAJ 7 6 7 3 2 2 1 TS 0 0 2 2 RX 2 1 1 1 0 NOR 1 1 2 1 1 1 SROI-7 1/C 3,6 3,5, 2,3,5, 7,8, 6,8,9 13 4 4 2 9
MAJ 7 6 7 3 2 2 1 TS 2,4 3,4 4 0 2 2 NUREG 1021 Revision 9 1
ES-301 Transient and Event Checklist Form ES-301-5 Facility: St. Lucie Date of Exam: 12/3/12 Operating Test No.: HLC 21-NRC A E Scenarios p v p E 1 (30%) 2( 5x10-4 ) 3 (100%) 4 (10-12%) T L N 0 I T T MINIMUM c CREW POSITION CREW POSITION CREW POSITION CREW POSITION A
A T L N y s A B s A B s A B s A B T p R T 0 R T 0 R T 0 R T 0 R I u E 0 c p 0 c p 0 c p 0 c p RX 0 1 1 0 NOR 2 1 1 1 1 SROU-1 1/C 3,4,6, 5 4 4 2 8,9 MAJ 7 1 2 2 1 TS 1,5 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 2 1 1 1 R0-3 1/C 4,8,9 3,8,9 3,6, 9 4 4 2 9
MAJ 7 6 7 3 2 2 1 TS 0 0 2 2 RX 2 1 1 1 0 NOR 1 1 1 1 1 SROI-3 1/C 3,6 3,5, 7,8, 7 4 4 2 9
MAJ 7 6 2 2 2 1 TS 2,4 2 0 2 2 RX 0 1 1 0 NOR 1 1 1 1 1 SROU-2 1/C 2,4, 4 4 4 2 5,7 MAJ 6 1 2 2 1 TS 3,5 2 0 2 2 RX 1 1 1 1 0 NOR 1 1 2 1 1 1 R0-4 1/C 4,7 3,8,9 3,6, 4 4 2 8
9 MAJ 6 6 7 3 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 NOR 1 2 1 1 1 SROI-4 1/C 2,5 3,5, 7,8, 7 4 4 2 9
MAJ 6 6 2 2 2 1 TS 2,4 2 0 2 2 NUREG 1021 Revision 9 2
~-------
ES-301 Transient and Event Checklist Form ES-301-5 Facility: St. Lucie Date of Exam: 12/3/12 Operating Test No.: HLC 21-NRC A E Scenarios p v p E 2( 5x10' 4
) 3 (100%) 4 (10-12%) SPARE T L N 5(100%) 0 I T T MINIMUM c CREW POSITION CREW POSITION CREW POSITION CREW POSITION A
A T L N y s A B s A B s A B s A B T p R T 0 R T 0 R T 0 R T 0 R I u E 0 c p 0 c p 0 c p 0 c p RX 0 1 1 0 NOR 1 1 1 1 1 SROU-3 2,4,5,7 1/C 4 4 4 2 MAJ 6 1 2 2 1 TS 3,5 2 0 2 2 RX 1 1 1 1 0 NOR 1 1 2 1 1 1 R0-5 1/C 4,7 5,7 2,5,8 7 4 4 2 MAJ 6 6 7 3 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 NOR 1 1 1 1 1 SROI-5 1/C 2,5 2,3,5,6,8, 8 4 4 2 9
MAJ 6 7 2 2 2 1 TS 3,4 2 0 2 2 RX 1 1 0 NOR 4 1 1 1 SRO 1/C 1,2, 5,7, 4 4 2 8
MAJ 6 2 2 1 TS 2,3 0 2 2 RX 4 1 1 0 NOR 1 1 1 ATC 1/C 2,8 4 4 2 MAJ 6 2 2 1 TS 0 2 2 RX 1 1 0 NOR 4 1 1 1 BOP 1/C 1,5, 4 4 2 7
MAJ 6 2 2 1 TS 0 2 2 NUREG 1021 Revision 9 3
ES-301 Transient and Event Checklist Form ES-301-5 Instructions:
- 1. Circle 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 service 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 (1/C) malfunction and one major transient in the ATC position. If an instant SRO additionally serves in the BOP position, one 1/C malfunction can be credited toward the two 1/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-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
NUREG 1021 Revision 9 4
ES-301 Competencies Checklist Form ES-301-6 Facility: St. Lucie Date of Examination: 12/03/2012 Operating Test No.: 1 APPLICANTS RO-1 SROI-1 SROI-5 Competencies BOP RO BOP SRO BOP RO RO RO SRO SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 1 2 4 1 2 4 Interpret/Diagnose 4, 7, 2,5, 5,6, 3,4, 4,6, 3,5, 3,6, 2,5, 2,3, Events 8,9 6 7 5,6, 7 6,8 7 6 4,5, and Conditions 7,8, 6,7, 9 8,9 Comply With and 2,4, 1,2, 1,4, 1-9 1,3, 1,3, 2,6, 1,2, 1-9 Use Procedures (1) 5,7, 5,6 5,6, 4,6, 4,5, 7 5,6 8,9 7 7 6,7, 8
Operate Control 2,4, 1,2, 1,4, 1,4, 1,3, 2,3, 1,2, Boards (2) 7,8, 5,6 5,6, 6,7 5,6, 6,7 5,6 9 7 7,8 Communicate 2-9 1-7 1,4, 1-9 1,3, 1,3, 2-9 1-7 1-9 and Interact 5,6, 4,6, 4,5, 7 7 6,8 Demonstrate 1-9 1-9 Supervisory Ability (3)
Comply With and 1,5 2,4 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.
Page 1 of 5
ES-301 Competencies Checklist Form ES-301-6 Facility: St. Lucie Date of Examination: 12/03/2012 Operating Test No.: 1 APPLICANTS SROU-2 RO-2 SROI-6 Competencies SRO SRO BOP RO BOP RO SRO SCENARIO SCENARIO SCENARIO SCENARIO 1 2 1 3 4 1 4 Interpret/Diagnose 3,4, 2-7 4, 7, 2,3, 2,6, 3,6, 2,3, Events 5,6, 8,9 4,6, 9 7 4,5, and Conditions 7,8, 8,9 6,7, 9 8,9 Comply With and 1-9 1-7 2,4, 1,3, 1,2, 2,6, 1-9 Use Procedures (1) 5,7, 6,8, 4,6, 7 8,9 9 7,9 Operate Control 2,4, 1,2, 1,2, 2,3, Boards (2) 7,8, 3,6, 4,6, 6,7 9 8,9 7,9 Communicate 1-9 1-7 2-9 1,2, 1,2, 2-9 1-9 and Interact 3,4, 4,6, 6,7, 7,9 8,9 Demonstrate 1-9 1-7 1-9 Supervisory Ability (3)
Comply With and 1,5 3,5 2,4 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.
Page 2 of 5
ES-301 Competencies Checklist Form ES-301-6 Facility: St. Lucie Date of Examination: 12/03/2012 Operating Test No.: 1 APPLICANTS RO-3 SROI-3 SROU-1 Competencies BOP RO BOP RO SRO SRO SRO SCENARIO SCENARIO SCENARIO SCENARIO 1 3 4 1 3 1 3 Interpret/Diagnose 4, 7, 2,3, 2,6, 3,6, 1-9 3,4, 1-9 Events 8,9 4,6, 9 7 5,6, and Conditions 8,9 7,8, 9
Comply With and 2,4, 1,3, 1,2, 2,6, 1-9 1-9 1-9 Use Procedures (1) 5,7, 6,8, 4,6, 7 8,9 9 7,9 Operate Control 2,4, 1,2, 1,2, 2,3, Boards (2) 7,8, 3,6, 4,6, 6,7 9 8,9 7,9 Communicate 2-9 1,2, 1,2, 2-9 1-9 1-9 1-9 and Interact 3,4, 4,6, 6,7, 7,9 8,9 Demonstrate 1-9 1-9 1-9 Supervisory Ability (3)
Comply With and 2,4 1,5 2,4 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.
Page 3 of 5
ES-301 Competencies Checklist Form ES-301-6 Facility: St. Lucie Date of Examination: 12/03/2012 Operating Test No.: 1 APPLICANTS SROI-2 SROU-3 SROI-4 Competencies SRO BOP RO SRO SRO RO SRO SCENARIO SCENARIO SCENARIO SCENARIO 2 3 4 2 4 2 3 Interpret/Diagnose 2-7 5,6, 3,5, 2-7 2,3, 2,5, 1-9 Events 7 6,8 4,5, 6 and Conditions 6,7, 8,9 Comply With and 1-7 1,4, 1,3, 1-7 1-9 1,2, 1-9 Use Procedures (1) 5,6, 4,5, 5,6 7 6,7, 8
Operate Control 1,4, 1,3, 1,2, Boards (2) 5,6, 5,6, 5,6 7 7,8 Communicate 1-7 1,4, 1,3, 1-7 1-9 1-7 1-9 and Interact 5,6, 4,5, 7 6,8 Demonstrate 1-7 1-7 1-9 1-9 Supervisory Ability (3)
Comply With and 3,5 3,5 2,4 2,4 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.
Page 4 of 5
ES-301 Competencies Checklist Form ES-301-6 Facility: St. Lucie Date of Examination: 12/03/2012 Operating Test No.: 1 APPLICANTS RO-4 RO-5 Competencies BOP RO BOP BOP BOP RO SCENARIO SCENARIO SCENARIO SCENARIO 2 3 4 2 3 4 Interpret/Diagnose 4,6, 2,3, 2,6, 4,6, 5,6, 3,5, Events 7 4,6, 9 7 7 6,8 and Conditions 8,9 Comply With and 1,3, 1,3, 1,2, 1,3, 1,4, 1,3, Use Procedures (1) 4,6, 6,8, 4,6, 4,6, 5,6, 4,5, 7 9 7,9 7 7 6,7, 8
Operate Control 1,4, 1,2, 1,2, 1,4, 1,4, 1,3, Boards (2) 6,7 3,6, 4,6, 6,7 5,6, 5,6, 8,9 7,9 7 7,8 Communicate 1,3, 1,2, 1,2, 1,3, 1,4, 1,3, and Interact 4,6, 3,4, 4,6, 4,6, 5,6, 4,5, 7 6,7, 7,9 7 7 6,8 8,9 Demonstrate Supervisory Ability (3)
Comply With and 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.
Page 5 of 5
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: St. Lucie Date of Exam: December 2012 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4
- Total 1 3 3 3 3 3 3 18 18 3 3 66 2 2 2 1 1 2 1 99 2 2 44 5 5 4 4 5 4 27 5 5 10 1 2 2 3 2 3 3 3 3 2 3 2 28 3 2 55 2.
Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 2 1 33 Systems Tier Totals 3 3 4 3 3 4 4 4 3 4 3 38 38 5 3 88
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 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 ATier Totals@
in each K/A category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1.b of ES-401 for the applicable KAs.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics=importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 007EG2.4.45 Reactor Trip - Stabilization - Recovery 4.1 4.3 Ability to prioritize and interpret the significance of each
/1 annunciator or alarm.
008AK1.01 Pressurizer Vapor Space Accident / 3 3.2 3.7 Thermodynamics and flow characteristics of open or leak- ing valves 009EK3.28 Small Break LOCA / 3 4.5 4.5 Manual ESFAS initiation requirements 011EG2.4.11 Large Break LOCA / 3 4.0 4.2 Knowledge of abnormal condition procedures.
015AA2.10 RCP Malfunctions / 4 3.7 3.7 When to secure RCPs on loss of cooling or seal injection 022AA1.09 Loss of Rx Coolant Makeup / 2 3.2 3.3 RCP seal flows, temperatures, pressures and vibrations 022AA1.08 VCT Level 025AK2.02 Loss of RHR System / 4 3.2 3.2 LPI or Decay Heat Removal/RHR pumps 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 Controllers and positioners Malfunction / 3 029EG2.1.30 ATWS / 1 4.4 4.0 Ability to locate and operate components, including local controls.
038EK3.09 Steam Gen. Tube Rupture / 3 4.1 4.5 Criteria for securing/throttling ECCS 040AK1.02 Steam Line Rupture - Excessive Heat 3.2 3.6 Leak rate versus pressure change Transfer / 4 Page 1 of 2 2/8/2012 12:25 PM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 055EA1.06 Station Blackout / 6 4.1 4.5 Restoration of power with one ED/G 056AA2.14 Loss of Off-site Power / 6 4.4 4.6 Operational status of ED/Gs (A and B) 057AK3.01 Loss of Vital AC Inst. Bus / 6 4.1 4.4 Actions contained in EOP for loss of vital ac electrical instrument bus 058AK1.01 Loss of DC Power / 6 2.8 3.1 Battery charger equipment and instrumentation 062AA2.01 Loss of Nuclear Svc Water / 4 2.9 3.5 Location of a leak in the SWS 065AA1.04 Loss of Instrument Air / 8 3.5 3.4 Emergency air compressor CE06EK2.1 Loss of Main Feedwater / 4 3.3 3.7 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Page 2 of 2 2/8/2012 12:25 PM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 001AK2.01 Continuous Rod Withdrawal / 1 2.9 3.2 Rod bank step counters 051AG2.4.35 Loss of Condenser Vacuum / 4 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 060AK2.01 Accidental Gaseous Radwaste Rel. / 9 2.6 2.9 ARM system, including the normal radiation-level indications and the operability status 061AK1.01 ARM System Alarms / 7 2.5 2.9 Detector limitations 067AK3.02 Plant Fire On-site / 8 2.5 3.3 Steps called out in the site fire protection plan, FPS manual and fire zone manual 068AA1.12 Control Room Evac. / 8 4.4 4.4 Auxiliary shutdown panel controls and indicators 069AK1.01 Loss of CTMT Integrity / 5 2.6 3.1 Effect of pressure on leak rate 076AA2.03 High Reactor Coolant Activity / 9 2.5 3 RCS radioactivity level meter CE09EA2.2 Functional Recovery / None 3.5 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
Page 1 of 1 2/8/2012 12:27 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003K5.04 Reactor Coolant Pump 3.2 3.5 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow and feed flow 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004K5.26 Chemical and Volume Control 3.1 3.2 Relationship between VCT pressure and NPSH for charging pumps 004K6.12 Chemical and Volume Control 2.6 2.9 Principle of recirculation valve: (permit emergency flow even K6.17 4.4 4.6 if valve is blocked by crystallized boric acid)
Flow paths for emergency boration 005K6.03 Residual Heat Removal 2.5 2.6 RHR heat exchanger 006A2.01 Emergency Core Cooling 2.9 3.1 High bearing temperature A2.06 3.3 3.5 Water hammer 006A2.11 Emergency Core Cooling 4.0 4.4 Rupture of ECCS header 007G2.2.22 Pressurizer Relief/Quench Tank 4.2 4.0 4.7 Knowledge of limiting conditions for operations and safety G2.2.44 Ability to interpret control room indications to verify limits.
the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 007K1.01 Pressurizer Relief/Quench Tank 2.9 3.1 Containment system 008K4.02 Component Cooling Water 2.9 2.7 Operation of the surge tank, including the associated valves and controls 010K1.01 Pressurizer Pressure Control 3.9 4.1 RPS Page 1 of 3 2/8/2012 1:32 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 012A2.07 Reactor Protection 3.2 3.7 Loss of dc control power 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022K2.01 Containment Cooling 3.0 3.1 Containment cooling fans 022K3.01 Containment Cooling 2.9 3.2 Containment equipment subject to damage by high or low temperature, humidity and pressure 026A1.02 Containment Spray 3.6 3.9 Containment temperature 039A4.04 Main and Reheat Steam 3.8 3.9 Emergency feedwater pump turbines 039A4.07 Main and Reheat Steam 2.8 2.9 Steam dump valves.
059K4.13 Main Feedwater 2.9 2.9 Feedwater fill for S/G upon loss of RCPs K4.19 3.2 3.4 Automatic feedwater isolation of MFW 061A1.03 Auxiliary/Emergency Feedwater 3.1 3.6 Interactions when multi unit systems are cross tied 062K3.01 AC Electrical Distribution 3.5 3.9 Major system loads 063K2.01 DC Electrical Distribution 2.9 3.1 Major DC loads Page 2 of 3 2/8/2012 1:32 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 064A1.03 Emergency Diesel Generator 3.2 3.3 Operating voltages, currents and temperatures 064A3.01 Emergency Diesel Generator 4.1 4.0 Automatic start of compressor and ED/G 073G2.4.46 Process Radiation Monitoring 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
076A4.04 Service Water 3.5 3.5 Emergency heat loads 078A3.01 Instrument Air 3.1 3.2 Air pressure 103K3.02 Containment 3.8 4.2 Loss of containment integrity under normal operations Page 3 of 3 2/8/2012 1:32 PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 017A1.01 In-core Temperature Monitor 3.7 3.9 Core exit temperature 029A4.04 Containment Purge 3.5 3.6 Containment evacuation signal 033A2.03 Spent Fuel Pool Cooling 3.1 3.5 Abnormal spent fuel pool water level or loss of water level 035A3.01 Steam Generator 4.0 3.9 S/ G water level control 045K3.01 Main Turbine Generator 2.9 3.2 Remainder of the plant 055K1.06 Condenser Air Removal 2.6 2.6 PRM system 056G2.4.4 Condensate 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
068K6.10 Liquid Radwaste 2.5 2.9 Radiation monitors 075K2.03 Circulating Water 2.6 2.7 Emergency/essential SWS pumps 079K4.01 Station Air 2.9 3.2 Cross-connect with IAS Page 1 of 1 2/8/2012 12:28 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO G2.1.1 Conduct of operations 3.8 4.2 Knowledge of conduct of operations requirements.
G2.1.14 Conduct of operations 3.1 3.1 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
G2.1.26 Conduct of operations 3.4 3.6 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
G2.2.4 Equipment Control 3.6 3.6 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
G2.2.43 Equipment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.14 Emergency Procedures/Plans 3.8 4.5 Knowledge of general guidelines for EOP usage.
G2.4.3 Emergency Procedures/Plans 3.7 3.9 Ability to identify post-accident instrumentation.
Page 1 of 1 2/8/2012 12:29 PM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 025AG2.4.3 Loss of RHR System / 4 3.7 3.9 Ability to identify post-accident instrumentation.
038EA2.16 Steam Gen. Tube Rupture / 3 4.2 4.6 Actions to be taken if S/G goes solid and water enters steam line 040AA2.02 Steam Line Rupture - Excessive Heat 4.6 4.7 Conditions requiring a reactor trip Transfer / 4 055EG2.4.30 Station Blackout / 6 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
056AA2.58 Loss of Off-site Power / 6 2.3 2.6 Air compressors (indicating lights)
AA2.77 4.1 4.4 Auxiliary feed pump (running) 065AG2.1.7 Loss of Instrument Air / 8 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Page 1 of 1 2/8/2012 2:04 PM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 051AG2.1.20 Loss of Condenser Vacuum / 4 4.6 4.6 Ability to execute procedure steps.
059AA2.04 Accidental Liquid RadWaste Rel. / 9 3.2 3.5 The valve lineup for a release of radioactive liquid 060AA2.02 Accidental Gaseous Radwaste Rel. / 9 3.1 4 The possible location of a radioactive-gas leak with the assistance of PEO, health physics and chemistry personnel CA16G2.4.50 Excessive RCS Leakage / 2 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Page 1 of 1 2/8/2012 12:31 PM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003G2.4.6 Reactor Coolant Pump 3.7 4.7 Knowledge symptom based EOP mitigation strategies.
006A2.13 Emergency Core Cooling 3.9 4.2 Inadvertent SIS actuation 061A2.05 Auxiliary/Emergency Feedwater 3.1 3.4 Automatic control malfunction 062G2.2.3 AC Electrical Distribution 3.8 3.9 (multi-unit license) Knowledge of the design, procedural and operational differences between units.
073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure Page 1 of 1 2/8/2012 12:32 PM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 014A2.04 Rod Position Indication 3.4 3.9 Misaligned rod 028A2.01 Hydrogen Recombiner and Purge 3.4 3.6 Hydrogen recombiner power setting, determined by using Control 3.5 3.9 plant data book A2.02 LOCA condition and related concern over hydrogen 071G2.1.27 Waste Gas Disposal 3.9 4 Knowledge of system purpose and or function.
Page 1 of 1 2/8/2012 12:32 PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO G2.1.31 Conduct of operations 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
G2.2.11 Equipment Control 2.3 3.3 Knowledge of the process for controlling temporary design changes.
G2.2.20 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.
G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.15 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems G2.4.12 Emergency Procedures/Plans 4.0 4.3 Knowledge of general operating crew responsibilities during emergency operations.
G2.4.46 Emergency Procedures/Plans 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 1 2/8/2012 12:33 PM
ES-401 Written Examination Quality Checklist Form ES-401 ~
Facitity: St. l ucie Date of Exatn: 1213/12 Exam levet: RO X SROX Initial ttem~n
- b" c!
- 1. Qoe!ttions and a nswers are technically aocurate and applicable to the facility.
1\' ~ ~
- 2. a.
b.
NRC t<./As are referenced fOf an questions.
FaciiiVteaming obiectives are referenced as available. -e ~ ~
SRO questions are api)(OpNte In a<<<fdance with Section D.2.d of E$-401 3.
-e ~ ~
4, The sampling procest w1s ,..ndom and S}'1tem*Ue (If more than 4 RO or 2 SRO ~)~dons were repeated from the last 2 NRC llcensJ*r.a exams. consult the NRR OL program office , ~
Question duplicatjon from the icense screening/audit e)(atn was controlled
-e-
- 5. as indicated below (check the iem that apples) and appears appropriate: ~ ~
_ the audit exam was syst&matieally and randomly developed; or X the au<Jit exam was completed before the lioense exam was started: or
_ the examinations wecre dcwebped independently; or
_ the licensee certifte.s that there Is no duplc.ation: Of
_ Olher (eXPialnj Bank us. meet& limits (no more than 75 percent New
-e-
- 6. Bank Modffied from the bank. at teatt 1o percent new, ancs the rest ~ ~
new Of mOdified): entef the actual RO 1 SR.O-onty 12/2 6/1 57/22 question distribution(s) at right.
- 7. Between 50 and 60 percent of the questions on the RO 6xam are writ't&n at the comprehensioN analysis level; Ule SRO exam may exceed 60 percent it the randorriy Memory CiA
-e ~ ~
36/8 39/17 selected t<JAs support the higher cognitive levers: enter the actual RO I SRO question disbt)ution(s) a1 right.
Referenceslhandouts pr<Mcktd do not give away answers or aid In the elimination of distraclors.
-e-8.
~ ~
- 9. O\ae$tlon content~:;!':$ with $peelfle KIA $\atements In the previously ap~ examination outine and Is aaoro 1 te fof the tier to whktl thev are assigned': deviations are tified, 1\' ~ ~
- 10. Qu.estion psyehomettle quaJily and fon'l'lat meet the guidelines in ES AppendiX 8 .
1\' ~ ~
The uam contains the roquired number of one-point, multiple choice i1ems; the total is correct
-e-11 .
al\d aarees vAih the value on the OOVCI stleet.
~ ~
Date
- a. AuthOf
- b. Fac:iity Reviewer r> f'~7:t~.~~ ~
- c. NRC Chief Examiner (t)
- d. NRC Regk>nal $~rvls0f ~~~~ 14'-- ~
Note;
- The fac::lllty revlewel'$ inltialthlgnature ate not applicable for NRC-develOped ex.rnlnation$.
- lndep_e_~ent NRC re'Viewer Initial Items in Column -(!'* chlef examiner concurrence required.
ES-401 Written Examination Review Worksheet Form ES-401-9
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation N
1 H 2 S K/A 007 G2.4.45, Reactor Trip, Ability to prioritize and interpret the significance of each annunciator or alarm.
K/A met This appears to be a higher level question 2 H 2 N S K/A APE 008 AK1.01, Knowledge of the operational implications of thermodynamics and flow characteristics of open or leaking valves as they apply to a pressurizer vapor space accident.
K/A is met.
3 F 2 N S K/A EPE 009 EK3.28, Knowledge of the reasons for manual ESFAS initiation requirements as they apply to a small break LOCA.
K/A is met This does NOT appear to be a higher order question.
4 H 2 N S K/A 011 EG 2.4.11, Large Break LOCA: Knowledge of abnormal condition procedures.
K/A is met.
5 H 2 X N E K/A APE 015 AA2.10, Ability to determine and interpret when to secure RCPs on loss of cooling or seal injection as they apply to RCP malfunctions.
K/A is met.
Second answer is a subset issue. If AND statement is true then OR statement is true. In this case, B could be argued as correct, Better question 2 could be Subsequent actions per the AOP.
Not certain AND would ever be chosen if question properly written.
S Changes made as noted above.
6 H 2 X N U K/A APE 022 AA1.09, Ability to operate and/or monitor RCP seal flows, temperatures, pressures, and vibrations as they apply to loss of reactor coolant makeup.
K/A is NOT met. This should probably be given a new K/A.
E St. Lucie does not use seal injection, therefore no loss of seal cooling from a loss of makeup.
S New K/A selected APE 022 AA1.08 New question reviewed. SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 7 H 2 M S K/A APE 025 AK2.02, Knowledge of the interrelations between the loss of the RHR system and decay heat removal pumps.
K/A is met.
8 H 2 B S K/A APE 027 AK2.03, Knowledge of interrelations between the pressurizer pressure control malfunctions and controllers and positioners.
K/A is met.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3. Check the appropriate box if a psychometric flaw is identified:
- The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
- The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
- The answer choices are a collection of unrelated true/false statements.
- The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
- One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4. Check the appropriate box if a job content error is identified:
- The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
- The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
- The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
- The question requires reverse logic or application compared to the job requirements.
- 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
- 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 9 H 2 N S K/A 029 EG 2.1.30, ATWAS. Ability to locate and operate components, including local control.
K/A is met.
10 H 2 x x B E K/AEPE 038 EK3.09, Knowledge of the reasons for criteria for securing/throttling ECCS as they apply to a SGTR.
K/A is met.
Rewrite 2nd question to include to maintain RCS Inventory Control and Pressure Control Safety Functions and as part of the stem.
Dont think anyone will chose not met for first part of question based upon second part of question. Perhaps rewrite to state when throttling criteria is met, what is the reason to throttle ECCS?
11/9/12 Need to ensure U2 curves are provided also.
11/21/12 Licensee Response: Incorporated the comment to S begin part 2 of C & D with Once Throttling Criteria is met.
Could not make the change recommended in the first comment because now part 2 of A-D no longer begin with similar statements.
11P H 3 N E K/A APE 040 AK1.02, Knowledge of the operational implications of the leak rate versus pressure change as they apply to a steam line rupture.
K/A is met.
Bold 2B Steam Generator (S/G) and 2A S/G in the stem to make it obvious that you are asking about the non-faulted generator in the question.
S 11/21/12 Licensee Response: Incorporated comments noted above
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 12 H 2 x M E K/A EPE 055 EA1.06, Ability to operate and monitor restoration of power with one EDG as it applies to a SBO.
K/A is met.
Recommend removing CFC from answer B. This gives a condition that is allowable, but does not exceed max load. Otherwise, the other 3 distractors all exceed the loading.
S 11/9/12 Removed reference provided from the question and from all other questions.
13 F 2 M S K/A APE 056 AA2.14, Ability to determine and interpret the operational status of EDGS (A and B) as they apply to LOOP.
K/A is met 14 H 2 x N U K/A 057 AK3.01, Knowledge of the reasons for actions contained in EOP for loss of vital ac electrical bus as it applies to loss of vital ac electrical bus.
K/A is met.
S B and D are not plausible. Why would someone believe that channel checks are required to meet safety functions?
11/9/12 Additional references provided to show plausibility of B & D.
15 H 2 x N E K/A APE 058 AK1.01, Knowledge of the operational implications of Battery Charger equipment and instrumentation as they apply to the loss of DC power.
K/A is met.
First question is awkward. Better to ask if loss of the battery charger would place the unit into TS 3.8.2.3.
11/9/12 Licensee will revise 1st question to make the Q15 a one part question only.
S 11/21/12 Licensee Response: Incorporated comments noted above.
16 H 2 x N E K/A APE 062 AA2.01, Ability to determine and interpret a location of a leak in the SWS as it applies to a loss of Nuclear Service Water.
K/A is met.
Distractor D is poor. Adding the condition that doesnt exist causes the reader to discount that answer.
The D explanation does not match proposed answers.
11/9/12 Licensee to change distractor D.
S 11/21/12 Licensee Response: Incorporated comments noted above
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 17 H 2 B S K/A APE 065 AA1.04, Ability to operate and/or monitor the emergency air compressor as it applies to loss of instrument air.
K/A is met.
18 H 2 N S K/A CE 06 EK2.1, Knowledge of the interrelations between the loss of feedwater and components and functions of control and safety systems including instrumentation, signals, interlocks, failure modes and automatic and manual features.
K/A is met.
19 H 3 N S K/A APE 001 AK2.01, Knowledge of the interrelations between the continuous rod withdrawal and rod bank step counters.
K/A is met.
20 H 2 N E K/A 051 AG 2.4.35, Loss of condenser vacuum. Knowledge of local auxiliary operator tasks and the resultant operational effects.
K/A is met.
Distractor D provides information that makes it obvious that this should improve vacuum. Delete to maximize efficiency.
S 11/21/12 Licensee Response: Incorporated comments noted above 21 F 2 N S K/A APE 060 AK2.01, Knowledge of the interrelations between the accidental gaseous radwaste release and the ARM system, including the normal radiation level indications and the operating status.
K/A is met.
11/9/12 Change A2 & C2 distractor (plausibility).
22 F 3 x N U K/A APE 061 AK1.01, Knowledge of the operational implications of detector limitations as they apply to ARM alarms.
K/A is NOT really met. K/A discuses ARM alarms.
E 11/9/12 This question is a best fit for this K/A. Rewrite in progress.
11/27/12 Moved AND of part 1 question (format change)
S
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 23 F 4 X N E K/A APE 067 AK3.02, Knowledge of the reasons for steps called out of the site Fire Protection Plan, FPS Manual, and Fire Zone Manual as they apply to a plant fire on site.
K/A is met.
Distractor C is NOT instrumentation. This looks like a cut and paste error.
Why would distractor A not be considered possibly correct? The Fire Protection Supervisor could have implemented 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rounds (This is a non-essential area).
Do you expect your ROs to have this level of detail memorized?
S 11/21/12 Licensee Response: Incorporated comments noted above. Verified RO knowledge.
24 F 2 M S K/A 068 AA1.12, Ability to operate/or monitor Auxiliary Shutdown Panel controls and indicators as they apply to Control Room Evacuation.
K/A is met.
25 H 2 N S K/A APE 069 AK1.01, Knowledge of the operational implications of the effect of pressure on leak rate as it applies to Containment Integrity.
K/A is met.
E 11/9/12 Replace Shield Bldg Vent with Containment Coolers.
11/21/12 Licensee Response: Incorporated comments noted S above.
26 F 2 X X B U K/A 076 AA2.03, Ability to determine and interpret the RCS radioactivity level meter as it applies to high reactor coolant activity.
K/A is met.
Distractor C and D would be more plausible if rewritten as Gross Activity with Iodine constant.
Why are B and D really plausible? If the same indication occurred with an up power or at steady state, the steady state answer would always have to be possible.
11/9/12 Change C to crud burst, i.e. Both Gross Activity and Iodine Increase.
S 11/21/12 Licensee Response: Incorporated comments noted above
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 27 F 2 N S K/A CE 09 EA2.2, Functional Recovery. Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
K/A is met.
28 H 2 N S K/A 003 AK5.04, Knowledge of the operational implications of the effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow as they apply to the RCPs.
K/A is met.
29 H 2 N E K/A 003 K6.14, Knowledge of the effect of a loss or malfunction on starting requirements will have on the RCPs K/A is met.
11/9/12 Change C to gpm.
11/21/12 Licensee Response: Incorporated comments noted S
above 30 H 2 N S K/A 004 K5.26, Knowledge of operational implications of relationships between VCT pressure and NPSH for charging pumps.
K/A is met.
31 F 2 X N E K/A 004 K6.17, Knowledge of the effect of a loss or malfunction on flow paths for emergency boration.
K/A is met.
Emergency boration is never by the RWT. Distractor A is not S
plausible.
11/9/12 Not true. RWT meets boration source definition.
32 H 2 N S K/A 005 K6.03, Knowledge of the effect of a loss or malfunction on the RHR HX will have on the RHRS.
K/A is met.
33 H 3 X N U K/A 006 A2.06, Ability to a) predict the impacts of water hammer on the ECCS and b) based on those predictions, use procedures to correct, control, or mitigate the consequences.
K/A is NOT met.
Need to predict the impact of water hammer. Reword to state that water hammer has occurred and tell what procedural steps will be taken t mitigate.
11/9/12 Change in progress to give indications of voiding in stem and determine how to correct.
S 11/21/12 Licensee Response: Incorporated comments noted above
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 34 H 3 N S K/A 006 A2.11, Ability to a) predict the impacts of a rupture in the ECCS header and b) based on those predictions, use procedures to correct, control, or mitigate the consequences.
K/A is met.
35 H 2 N S K/A 007 G2.2.44, Pressurizer Relief Tank/Quench Tank System (PRTS): Ability to interpret Control Room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A is met.
36 F 2 N S K/A 007 K1.01, Knowledge of the physical connections and/or cause effect relationships between PRTS and containment.
K/A is met.
37 H 2 X N E K/A 008 K4.02, Knowledge of CCWS design feature(s) and/or interlock(s) which provide for operation of the surge tank, including the associated valves and controls.
K/A is met.
Modify question to make it an essential header break. Perhaps failing the level switch low (level confirmed OK by NLO) will allow using the same answer.
11/21/12 Licensee Response: No changes have been made to S this question. When discussing this question with the NRC during prep week, further verification (with peer) was required.
38 F 2 N S K/A 010 K1.01, Knowledge of the physical connections and/or cause effect relationships between the PZR PCS and RPS.
K/A is met 39 F 3 N S K/A 012 A 2.07, Ability to a) predict the impacts of loss of dc control power on the RPS and b) based on those predictions, use procedures to correct, control, or mitigate the consequences.
K/A is met.
40 H 4 N E K/A 013 K5.02, Knowledge of the operational implications of safety system logic and reliability as it applies to ESFAS.
K/A is met.
Light not lit indicates that B/S tripped > 5% before setpoint.
Explanation for A is incorrect.
11/9/12 Remove sequence from the 2nd question. Not needed and S confusing.
11/21/12 Licensee Response: Incorporated comments noted above
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 41 F 3 B S 022K2.01 Knowledge of power supplies to the following: Containment cooling fans.
Meets K/A.
42 F 3 N S 022K3.01 Knowledge of the effect that a loss or malfunction of the CCS will have on the following: Containment equipment subject to damage by high or low temperature, humidity, and pressure.
Meets K/A.
C & D plausibility? Why would an RO choose 5 hrs? This is a TS number that has no bearing for an RO to choose.
This is from a Caution statement in the AOP. 11/16/12 SAT 43 H 3 N S 026A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment temperature Meets K/A.
44 H 3 N S 039.A4.04 MRSS Ability to manually operate and/or monitor in the control room: Emergency feedwater pump turbines.
Meets K/A.
45 H 3 B S 039A4.07 MRSS Ability to manually operate and/or monitor in the control room: Steam dump valves.
Meets K/A.
46 F 2 N E 059K4.19 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic feedwater isolation of MFW.
Meets K/A.
Do you need to specify NR water level? Does automatically need to S be in the stem?
11/16/12 Made changes SAT 47 F 3 N U 061.A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: Interactions when multi-unit systems are cross tied.
Meets K/A.
Overlaps with a JPM P-3.
Request new K/A due to overlap.
NEW K/A: 061 A1.04 AFW source tank level S 11/21/12 Licensee Response: Incorporated comments noted above. New question reviewed SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 48 F 2 N E 062k3.01 Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: AC Electrical Distribution System: Major system loads.
Meets K/A.
Distractor D plausibility. This implies that ALL loads would have a breaker input to the DG start logic. This is a new question? Are you sure it is not modified?
11/16/12 New D distractor to replace this.
S 11/21/12 Licensee Response: Modified distracter D.
49 H 3 B E 063K2.01 Knowledge of bus power supplies to the following: Major DC loads.
Meets K/A.
Verb should be pumps.
11/1/12 Add the word lineup instead to the question.
11/21/12 Licensee Response: included the word lineup in the S
stem.
11/27/12 Removed the word lineup 50 H 3 N E 064A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Operating voltages, currents, and temperatures.
Meets K/A.
Distractor D does not meet question context and is therefore not plausible. The emergency p/b is not adjustable manually controlled.
11/16/12 Changed stem of question.
S 11/21/12 Licensee Response: Incorporated comments noted above and reworded all answer selections.
51 H 3 N S 064A3.01 Ability to monitor automatic operation of the ED/G system, including: Automatic start of compressor and ED/G.
Meets K/A.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 52 H 3 B E 073G2.4.46 Process radiation monitoring: Ability to verify that the alarms are consistent with the plant conditions.
Meets K/A.
C Not plausible as written. Change to NOT CHANGE due to the reduction in power level. Also question is nonsensical. If level has increased from ALERT to HIGH how could it have decreased. D distractor is not correct. The procedure states that the reading is NOT VALID. It does not say if the reading stabilizes or decreases.
11/16/12 Replaced with new question.
11/21/12 Licensee Response: Incorporated comments noted S above. Replaced with different question (worded similar).
11/27/12 Reworded distracter B - because of the higher leak rate.
53 H 3 N E 076A4.04 Service Water System Ability to manually operate and/or monitor in the control room: Emergency heat loads.
Meets K/A.
S Dont understand reasoning for distractor B. If ICW flow is minimized by closing the debris valves, how does the 2nd part answer make sense?
11/16/12 Review with licensee, plausibility sat.
54 F 3 N E 078A3.01 Instrument air system Ability to monitor automatic operation of the IAS, including: air pressure.
Meets K/A.
S Need to specify that this is IA High Air Pressure condition. This locks out the standby AC. Verify that the running AC trips on high press?
11/16/12 Changed above as noted.
55 F 2 B S 103K3.02 Containment systems Knowledge of the effect that a loss or malfunction of the containment system will have on the following:
Loss of containment integrity under normal operations.
Meets K/A.
017A1.01 In-Core Temperature Monitor (ITM) System Ability to 56 F N S predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ITM system controls including: Core exit temperature.
Meets K/A.
57 F 3 N S 029A4.04 Containment purge system Ability to manually operate and/or monitor in the control room: Containment evacuation signal.
Meets K/A.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 58 H 4 N S 033A2.03 Spent Fuel Pool Cooling Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.
Meets K/A.
59 H 3 N U 035A3.01 Steam Generator Ability to monitor automatic operation of the S/G including: S/G water level control.
Meets K/A.
C &D plausibility? Implies there is an anticipatory circuit to increase flow from the low power FRV at high power levels?
11/16/12 Agreed to change distractor C to match wording to A &
B.
S 11/21/12 Licensee Response: Replaced LPFRV with 100%
Bypass valve in C and made similar to A & B. Revised distracter analysis for C 60 H 3 B E 045K3.01 Main Turbine Generator Knowledge of the effect that a loss or malfunction of the MT/G system will have on the following:
Remainder of the plant.
C does not fit with other choices and SG lvl is not of immediate concern and can therefore be discarded easily.
11/6/12 Changed C to match D with ADV.
S 11/21/12 Licensee Response: Incorporated comments noted above 61 H 3 N S 055K1.06 Knowledge of the physical connections and/or cause effect relationships between the CARS and the following systems: PRM system (process radiation monitoring).
Meets K/A.
62 H 3 N E 056G2.4.4 Condensate System: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Meets K/A.
Place in order of AOP procedure number. D plausibility. How does this decrease vacuum?
11/6/12 Could rob cooling flow if applicant thought less cooling flow.
S 11/21/12 Licensee Response: Incorporated comments noted above. Refer to system description figure for location of FCV 1 in the condensate system to justify plausibility.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 63 F 3 N E 068K6.10 Knowledge of the effect of a loss or malfunction on the following will have on the Liquid Radwaste System : Radiation monitors:
Meets K/A. In distractor B change upper case Two to two. Is this RO Knowledge?
11/16/12 Verified this is an RO task and is on their qual card.
S 11/21/12 Licensee Response: Incorporated comments noted above.
64 F 4 B E 075K2.03 Knowledge of bus power supplies to the following:
Emergency/essential SWS pumps.
Meets K/A. Is this RO Knowledge.
S 11/16/12 Verified RO.
65 F 3 N U 079K4.01 Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with IAS.
Meets K/A.
S Isnt this an overlap with a scenario event? Will leave as is and verify that this event does not occur during the scenario.
66 F 3 N E G2.1.1 Knowledge of conduct of operations requirements.
Meets K/A. Do you need to state that the other RO is in the OACA area? If the other operator is allowed at times out of the OACA then only one trainee would be authorized.
S 11/21/12 Licensee Response: Incorporated comments noted above.
67 S G2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
Meets K/A.
68 S G2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
Meets K/A.
69 S G2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
Meets K/A.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 70 S G2.2.43 Knowledge of the process used to track inoperable alarms.
Meets K/A.
Distractor C is only one that ends in a period and is the correct answer.
71 E G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entryl requirements, fuel handling responsibilities, access to locked high-radiationl areas, aligning filters, etc Meets K/A.
Isnt C also correct? The order is correct as stated.
11/16/12 Change the question in the stem to add IAW the procedure S 11/21/12 Licensee Response: Put procedure reference in question.
72 U G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Meets K/A.
1st question overlaps with Admin JPM.
S 11/16/12 Different limits are being asked.
73 E 2.3.7 Ability to comply with radiation work permit requirements during normal or l abnormal conditions.
Meets K/A.
Is C plausible? Can these two go together?
11/16/12 Changes made to make C & D more plausible.
11/21/12 Licensee Response: Changed C distracter to look S
similar to D.
74 S 2.4.14 Knowledge of general guidelines for EOP usage.
Meets K/A.
75 S G2.4.3 Emergency procedures/ Plan: Ability to identify post-accident instrumentation.
Meets K/A.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 76 F 3 N E 025AG2.4.3 Loss of RHR System Ability to identify post-accident instrumentation.
Meets K/A.
Why is the LPSI pump stopped during a LOCA? What makes 4 hrs plausible? No 4 hrs Hot Shutdown. Change to be in Hot Shutdown in the NEXT 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
S 11/21/12 Licensee Response: Changed C&D to 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action.
77P F 2 x x N U 038EA2.16 Steam Generator Tube Rupture: Action to be taken if S/G goes solid and water enters steam line.
Does NOT meet K/A and is NOT SRO Only. Also overlaps with scenario.
S 11/9/12 Question accepted as is since it is the closest fit to procedural guidance for high SG water level.
78 H 3 N S 040A2.02 Ability to determine and interpret the following as they apply to the Steam Line Rupture: Conditions requiring a reactor trip.
Meets K/A.
Is having a + MTC following a partial refueling realistic?
11/9/12 Verified that this is possible for this outage due to the number of new fuel assemblies added to the core.
79 H 3 N E 055G2.4.30 Station Blackout: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
Meets K/A.
Modify question to add Which one of the..basis for the HIGEST classification?
11/21/12 Licensee Response: Incorporated comments noted S above.
80 H 3 N E 056AA2.77 Loss of Offsite Power: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Auxiliary feed pump (running)
Meets K/A.
Where did you get the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restoration criteria plausibility?
11/9/12 Add plausibility analysis.
11/21/12 Rearranged question to make 72 hrs.
11/21/12 Licensee Response: Enhanced distracter analysis S discussion for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restoration plausibility and will send reference for 72 hr restoration (Ops Policy guidance).
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 81 H 3 B E 065AG2.1.7 Loss of Instrument Air. Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Meets K/A.
Change to include the words Perform an RCS leak rate in each response since it is the same.
S 11/21/12 Licensee Response: Incorporated comments noted above 82 H 3 N E 051AG2.1.20 Loss of Condenser Vacuum. Ability to execute procedure steps.
Meets K/A.
2nd question poorly written in wrong tense.
11/9/12 Change abbreviation from Hg to HgA S
11/21/12 Licensee Response: Incorporated comments noted above.
11/27/12 added a space betweenin HgA.
83 F 3 M S APE 059AA2.04 Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: The valve lineup for a release of radioactive liquid.
Meets K/A.
84 H 4 N S APE 060AA2.02 Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste: The possible location of a radioactive gas leak with the assistance of PEO, health physics and chemistry personnel.
Meets K/A.
85 F 3 N S CA16 G2.4.50 Excess RCS Leakage: Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Meets K/A.
B distractor analysis in not correct.
86 H 3 N S 003G2.4.6 Reactor Coolant Pump: Knowledge of EOP mitigation strategies.
Meeks KA. Why is >30 minutes needed? If you have a valid SIAS by procedure you isolate CCW to RCP?
11/9/12 Agreed to leave as is.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 87 H 3 N S 006A2.13 ECCS. Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent SIS actuation.
Meets K/A.
061A2.05 Aux/Emergency Feedwater: Ability to (a) predict the 88P H 3 x x B U impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Automatic control malfunction.
Meets K/A.
Can deduce the AOP is correct based on procedure hierarchy. Also is this SRO Only?
11/9/12 Will change so that the NOP is the correct answer.
11/21/12 Could not meet NOP so changed to have 4 AOP choices.
11/21/12 Licensee Response: Was not able to create distracters S that made using the NOP correct. Question was re-written with the only reference being the AOP for all the answer selections.
89 H 3 N E 062 G2.2.3 AC Electrical Distribution. (multi-unit license) Knowledge of the design, procedural and operational differences between units.
Meets KA.
Doesnt appear to have a correct 2nd question. You state the TSAS is U
only stated for U2 not U1?
11/9/12 Overlaps with JPM. Licensee agreed to change to a U2 question so that there is a TSAS..
S 11/21/12 Licensee Response: The question is now a Unit 2 question. T.S. condition expected to be known from memory due to Ops Policy statement 4/8/13 Question was appealed. Two correct answers noted after appeal review by HQ (A & D). No score changes resulted from the appeal. (Appeal requested choice B & D as correct.)
4/24/13 Question re-reviewed by HQ and determined more than two correct answer possible, delete the question. Score change will result from this decision.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 90P H 3 N U 073A2.02 PRM: Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions; use procedure to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
Meets K/A.
Can deduce the AOP is correct based on procedure hierarchy. Also is this SRO Only?
11/9/12 Will revise questions to make another AOP an option instead of the NOP.
S 11/21/12 Licensee Response: Changed part 2 reference in A & B to AOP 26-01, Process Radiation Monitors.
11/27/12 Changed C & D part 2 to match A &B part 2.
91 H 3 N U 014A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Misaligned rod.
Meets K/A.
This malfunction used in a scenario. Overlap.
11/9/12 License will change to ask about a rod slip to the LEL.
S 11/21/12 Licensee Response: Changed rod slip height to LEL.
92 H 3 N S 028A2.02 Hydrogen Recombiner and Purge Control System (HRPS)
Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen.
Meets K/A.
93 F 3 N E 071G2.1.27 Waste gas disposal: Knowledge of system purpose and or function.
Meets K/A.
11/9/12 Licensee agreed to change to protected area to make choices more plausible.
11/21/12 Licensee Response: Incorporated comments noted S above 11/27/12 Fix indents to align with question part numbers 94P H 3 N S G2.1.31 Conduct of Ops: Ability to locate control switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
Meets K/A.
No plausibility given for other distractors besides the correct.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO Link ward (F/H) (1-5) Focus Dist. units K/A Only B/M/N U/E/S Explanation 95P F 3 N S G2.2.11 Equipment Control: Knowledge of the process for controlling temporary design changes.
Meets K/A.
What solenoid vent valve?
96 F 3 N S G2.2.20 Equipment Control: Knowledge of the process for managing troubleshooting activities.
Meets K/A.
Assumption is that an underload is an abnormal condition.
97 F 3 N S G2.3.12 Radiation Control: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Meets K/A.
98 H 3 N E G2.3.15 Radiation Control: Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Meets K/A.
D distractor is not plausible. How can the alternate portable rad monitor meet the original TS requirement and there no LCO is addressed? (nonsensical)
S 11/21/12 Licensee Response: Rewrote distracter D 99 H 3 N E G2.4.12 Emergency Procedures / Plan: Knowledge of general operating crew responsibilities during emergency operations.
Meets K/A.
11/9/12 Get rid of Report to the U1 MCR.
11/21/12 Licensee Response: Incorporated comments noted S
above 100 H 3 N S G2.4.46 Emergency Procedures / Plans: Ability to verify that the alarms are consistent with the plant conditions.
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: St. Lj,cje Date of Exam: j 1 Zj4. 12 Exam Level: RO,SRO Initials Item Description a b c
- 1. Clean answer sheets copied before grading ?J
- 2. Answer key changes and question deletions justified and_documented
- 3. Applicants scores checked for addition errors çjj j (reviewers spot check> 25% of examinations) I U
- 4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, /1 as applicable, +/-4% on the SRO-only) reviewed in detail jU
- 5. All other failing examinations checked to ensure that grades are_justified f.J
- 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date
- a. Grader ( F11Ls a( ( L
- b. Facility Reviewer(*)
- c. NRCChiefExaminer(*) /hi
- d. NRC Supervisor (*) J#L(4AT.
(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6