ML21011A055
| ML21011A055 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/11/2021 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML21011A055 (62) | |
Text
ML21011A055 ES-301 Administrative Topics Outline Form ES-301-1 Facility: NORTH ANNA Date of Examination: 6/2020 Examination Level: RO SRO Operating Test Number: 2020 Administrative Topic (see Note) Type Describe activity to be performed Code*
2.1.43 (4.1) Ability to use procedures to determine effects on reactivity of plant changes Conduct of Operations R, M, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
JPM: Determine the shutdown margin 2.1.43 (4.1) Ability to use procedures to R, N determine effects on reactivity of plant changes Conduct of Operations such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
JPM: Determine Calculate the amount of boron concentration neededBoric Acid required to lower RCS temperature by a specified amount Equipment Control 2.3.7 (3.5) Ability to comply with radiation work R, M, permit requirements under normal or abnormal Radiation Control conditions.
P JPM: Determine correct RWP, Stay Time, Dosimetry, and Dress-Out RequirementsProtective Clothing requirements and calculate maximum Stay Time using RWP and Survey Map R, M, 2.4.43 (3.1) Knowledge of emergency communications systems and techniques.
Emergency Plan JPM: Prepare and transmit an initial EPIP notification to the State and Local Governments as the State and Local Communicator (EPIP-2.01).
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: NORTH ANNA Date of Examination: 6/2020 Examination Level: RO SRO Operating Test Number: 2020 Administrative Topic (see Note) Type Describe activity to be performed Code*
2.1.43 (4.3) Ability to use procedures to determine effects on reactivity of plant changes Conduct of Operations R, M, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
JPM: Review a shutdown margin calculation and identify applicable Technical Specification 2.1..43 26 (4.33.6) Knowledge of industrial safety procedures (such as rotating equipment, Conduct of Operations electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).Ability to use procedures to determine effects on R, N reactivity of plant changes such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
JPM: Complete a Heat Stress Evaluation in accordance with SA-AA-109Review the boron concentration needed to lower RCS temperature by a specified amount R, N 2.2.13 (4.3) Knowledge of tagging and clearance procedures.
Equipment Control JPM: Review a tagout for completeness and accuracy and identify applicable Technical Specification 2.3..7 4 (3.67) Ability to comply with radiation work permit requirements under normal or Radiation Control R, M, abnormal conditions. Knowledge of radiation exposure limits under normal or emergency P conditions JPM: determine if the individuals who volunteered for the emergency exposures are preferred for authorization for the tasks (EPIP-4.04)Determine correct RWP, Stay Time, Dosimetry, and Dress-Out Requirements R, M, 2.4.43 44 (3.84.4) Knowledge of emergency communications systems and techniquesplan Emergency Plan protective action requirements.
JPM: determine Protective Action RecommendationsReview an initial EPIP notification to the State and Local Governments (EPIP-1.06).
ES-301 Administrative Topics Outline Form ES-301-1 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Date of Examination: 6/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: 2020 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function
- a. 006 Emergency Core Cooling System (ECCS) S, M, L, EN 2
[006 A4.07(4.4/4.4)]
Establish Redundant Cold Leg Injection Flow Paths in accordance with 1-E-1, Loss Of of Reactor Or or Secondary Coolant (ALL)
- b. 038 Steam Generator Tube Rupture (SGTR) A, S, M, L, D 3
[038 EA1-05 (4.1/4.3)]
Depressurize the Reactor Coolant System in order to minimize break flow and refill the pressurizer during the response to a Steam Generator Tube Rupture (1-E-3)
(RO and SRO-I)
- c. 005 Residual Heat Removal Systems (RHRS) A, S, M, L 4P
[005 A4.01 (3.6/3.4)]
Restore residual heat removal flow in accordance with 1-AP-11 (ALL)
- d. 041 Steam Dump System (SDS) and Turbine Bypass Control A, S, D 4S
[041 A4.08 (3.0/3.1)]
Transfer the Steam Dumps to the Steam Pressure Mode (RO and SRO-I)
- e. 007 Pressurizer Relief Tank/Quench Tank System (PRTS) S,D 5
[007 A1.01 (2.9/3.1)]
Drain the Pressurizer Relief Tank (RO and SRO-I)
- f. 064 Emergency Diesel Generators (ED/G) A, S, M 6
[064 A4.01 (4.0/4.3)]
Start the 1H EDG and reenergize 1H Bus Re-start a diesel generator with an automatic start signal present (RO and SRO-I)
- g. 015 Nuclear Instrumentation System (NIS) S, D 7
[015 A4.02 (3.9/3.9)]
Respond to a malfunction of the Power-Range Nuclear Instrumentation (ALL)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- h. 075 Circulating Water System S, D 8
[075 A4.02 (2.2*/2.3)]
Place a Circulating Water Pump in service (RO Only)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In-Plant Systems:
- 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. 001 Control Rod Drive System A, D, E 1
[001 A2.13 (4.4/4.6)]
Trip the Main Turbine locally (FR-S.1) (ALL) j.061 Auxiliary / Emergency Feedwater (AFW) System D, E 4S
[061 A2.04 (3.4/3.8)]
Align both Motor-Driven Auxiliary Feedwater Pumps to feed the Steam Generator by way of the Hand Control Valve header (AP-22)
(RO and SRO-I)
- k. 062 AC Electrical Distribution D, E,R 6
[062 A2.01 3.4/3.9)]
Isolate the Reactor Coolant Pump seals locally (ECA-0.0)
(ALL)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /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/ 1/ 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
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: North Anna Exam Date: 6/8/2020 1 2 3 4 5 6 ADMIN Attributes Job Content LOD Admin JPMs Topic U/E/S Explanation (1-5) I/C Critical Scope Perf.
and K/A Job Cues Overlap Key Minutia Focus Steps (N/B) Std. Link RO/SRO COO1
- (RO A1) Inappropriate K/As selected as reference for this JPM (001A4.11 & 005AK1.05). Admin JPMs require K/A selection from section 2.0 of NUREG-1122 (ES-301 pg. 10 of 33 K/As associated with each administrative topic shall be selected from Section 2 of the applicable NRC K/A catalog for pressurized-water reactors (PWRs) or boiling water reactors (BWRs). An appropriate K/A for this task is 2.1.37.
- (RO A1) Wording of second bullet under Initial Conditions is awkward, doesnt read as operationally valid and seems to directly cue performance of 1-PT-10.1, Attachment 1, Step 13. Revise this bullet to provide an actual Control Rod Group Step position (thats inserted at least 18 steps). Example, D Bank rods currently at position 210. Initiating Cue revision required with Step position used above. Control Bank (RO A1) Determine SDM COO 1 3 x E D is at 215 steps is given in the SRO JPM SRO A1.
- (RO A1) There are references missing from JPM package that are designated for use on Attachment 1.
SpecificallySpecifically, 1-SC-8.1 and 8.3. Use of these arent required for successful completion of this JPM but should be in the JPM package if printed versions will be provided to applicants. It may be easier to simply provide 1-PT-10.1 during administration and have all references available digitally (laptop, desktop, iPad, etc.).
- (RO A1) JPM Step 2, Applicant cannot interpret 1-SC-3.4 to a value of -6.44. Minimum acceptance range value should read -6.45.
- (RO A1) JPM Step 4, Minimum acceptance range for using 1-SC-8.5 (@2414 MWD/MTU) should read -
5340 to -5350" for instantaneous shutdown conditions.
- (RO A1) JPM Step 9, Acceptable range for Item 17 calculation should read: -3257 to -3197"
- (SRO A1) Wording of second bullet under Initial Conditions is awkward, doesnt read as operationally valid and seems to directly cue 1-PT-10.1, Attachment 1, Step 13. This bullet can be removedis different than (SRO A1) Review SDM COO 1 3 x x U that of RO A1?.
- (SRO A1) As-written JPM does not meet job level criteria of SRO-only. PT-10.1 procedure review requires no additional skill to perform than that
ES-301 Operating Test Review Worksheet Form ES-301-7 required of an RO. This can be corrected by adding an SRO component to the JPM (e.g. required T.S. entry, administrative requirement for failed surveillance, etc.)
RO/SRO COO2
- (RO A2) This JPM appears to be of a skill-of-the-craft activity performed by board operators. NUREG-1021 requires that tasks used to evaluate applicants for NRC operating licenses be based on procedurally driven, operationally relevant tasks. For additional (RO A2) Determine [B] information, reference NUREG-1021, Appendix C.
needed to lower RCS COO 2 3 x x E - (RO A2) As-written JPM identified CRITICAL STEPS temp have no procedural steps listed for performance basis.
Invalid evaluation instrument.
- (RO A2) Could not locate reactor data book to acquire information needed to determine ITC.Verify this task does not fall under RG 1.33 procedural requirements.
4/23 Discussed including the steps from the OP.
- (SRO A2) Similar to the SRO A1 JPM, as-written JPM does not meet job level criteria of SRO-only. JPM guide activity consists of as-performed calculation review that fails to rise to SRO LOK. This can be corrected by adding an SRO component to the JPM (SRO A2) Review [B] COO 2 3 x U (e.g. required T.S. entry, administrative requirement for failed surveillance, etc.)
4/23 Discussed adding SRO component.
5/7 Will write a new JPM for stay time related to high temperature in an area.
SRO EC
- (No equipment controls JPM for RO?) - Not required per ES-301, D.3.a (RO EP JPM included)
- (SRO A3) Similar to SRO A1 and A2 JPMs, as-written JPM does not meet job level criteria of SRO-only. JPM guide activity consists of OP-AA-200, Attachment 16 completion review that fails to rise to SRO LOK.
- (SRO A3) To correct, some of the items identified in the Initial Conditions as being performed by the WCC (SRO A3) Review a Supervisor could be incorporated to add SRO LOK.
tagout for completeness EC 3 x U - (SRO A3) If retained, ensure JPM guide is updated to and accuracy incorporate OP-AA-200, Attachment 16 as being the source steps identified within each JPM guide step.
Currently these steps state: Check List Item #
- (SRO A3) As-written JPM guide requires identification of failure to include 1-FW-190" as the only CRITICAL STEP of this JPM. Per NUREG-1021, App C, Section B.3, simple one-step JPMs or JPMs that only require directly looking up the correct answer are not appropriate. Addition of SRO-only component to this JPM should correct this.
4/23 Discussed how to add SRO component.
ES-301 Operating Test Review Worksheet Form ES-301-7 RO/SRO RP
- (RO A4) Remove total dose this year is 70 mrem from Initial Conditions as this information is not required to complete this task.
- (RO A4) Initiating Cue bullets 2 through 4 can be answered solely by correctly providing an answer to bullet 1 (I.e. select appropriate RWP task). The answer to bullet 1 is a direct lookup with the provided task information (routine duties vs. filter changeout vs.
BARS operation).
In wording the initiating cue as-written, there is little to no discriminatory value in JPM Steps 2 through 4. Lastly, none of the RWP tasks differ in required dosimetry.
- (RO A4) Remove bullets 1 (select RWP task#), 3 (RO A4) Determine (determine dosimetry) and 4 (determine D/DR alarm RWP, stay time, setpoints) from Initiating Cue. Remove JPM Guide dosimetry, and dress-RC 3 x x E Steps 1, 3. and 4. Revise JPM Guide Step 2 to be out criteria CRITICAL.
- (RO A4) Revise IC bullet 5 to read: Using the map provided and the appropriate allowed dose limit to complete inspection of 1-CH-TCV-100, calculate the MAXIMUM stay time available during this Unit 1 NRHx Cube room entry.
- (RO A4) Remove bullets 6 (assume you avoid...) and 7 (assume no dose...) from Initiating Cue
- (RO A4) Ensure HP/RC procedure that governs stay time calculation is incorporated into standard for JPM Step 5 (none currently listed).
- (RO A4) Revise acceptable range for JPM Step 5 to read: 8 minutes 34 seconds to 8 minutes 36 seconds 4/23 Discussed security related to using a map of the plant.
- (Same wording) How is this SRO Only?
- (SRO A4) Similar to SRO A1, A2 and A3 JPMs, as-written JPM does not meet job level criteria of SRO-only. JPM guide activity consists of HRA room entry that fails to rise to SRO LOK.
- (SRO A4) All comments below are the same as RO A4 comments.
(SRO A4) Determine - (SRO A4) Remove total dose this year is 70 mrem RWP, stay time, from Initial Conditions as this information is not dosimetry, and dress-RC 3 x x x U required to complete this task.
out criteria - (SRO A4) Initiating Cue bullets 2 through 4 can be answered solely by correctly providing an answer to bullet 1 (I.e. select appropriate RWP task). The answer to bullet 1 is a direct lookup with the provided task information (routine duties vs. filter changeout vs.
BARS operation).
In wording the initiating cue as-written, there is little to no
ES-301 Operating Test Review Worksheet Form ES-301-7 discriminatory value in JPM Steps 2 through 4. Lastly, none of the RWP tasks differ in required dosimetry.
- (SRO A4) Remove bullets 1 (select RWP task#), 3 (determine dosimetry) and 4 (determine D/DR alarm setpoints) from Initiating Cue. Remove JPM Guide Steps 1, 3. and 4. Revise JPM Guide Step 2 to be CRITICAL.
- (SRO A4) Revise IC bullet 5 to read: Using the map provided and the appropriate allowed dose limit to complete inspection of 1-CH-TCV-100, calculate the MAXIMUM stay time available during this Unit 1 NRHx Cube room entry.
- (SRO A4) Remove bullets 6 (assume you avoid...)
and 7 (assume no dose...) from Initiating Cue
- (SRO A4) Ensure HP/RC procedure that governs stay time calculation is incorporated into standard for JPM Step 5 (none currently listed).
- (SRO A4) Revise acceptable range for JPM Step 5 to read: 8 minutes 34 seconds to 8 minutes 36 seconds 4/23 Discussed how to make SRO.
5/7 Discussed modifying JPM to ask ED limit calculation.
- (RO A5) Why is JPM Step 9 not marked off as a CRITICAL STEP?
- (RO A5) JPM Step 13 specifies recording of values for EPIP-2.01, Att 2, Item 2. The values required are (RO A5) Prepare and not recorded for completion of JPM Step 13. (There is xmit an initial EPIP EP 3 x E no screen shot included in this JPM to validate notification required values)
- (RO A5) Recommend having a completed ENF added to the JPM guide with steps filled-in as required for use during evaluation grading (I.e. answer key).
4/23 Discussed edits.
- (SRO A5) Similar to other SRO JPMs, as-written JPM does not meet job level criteria of SRO-only. JPM guide activity consists of ENF form review (using given information) and fails to rise to SRO LOK (same activity performed as RO A5 JPM). EAL classification, invoking upgrade criteria, determination of PAR requirements (GE) would all qualify as SRO LOK and (SRO A5) Review initial EPIP notifications EP 3 x U fit for inclusion into this JPM.
- (SRO A5) Recommend having a completed ENF added to the JPM guide with steps filled-in as required for use during evaluation grading (I.e. answer key).
4/23 Discussed how to make SRO.
(Upgrade conditions to a GE and then complete a PAR) Make sure different from last NRC and audit exam.
1 Simulator/In-Plant
ES-301 Operating Test Review Worksheet Form ES-301-7 Safety JPMs Function and K/A (A) Establish redundant Cold Leg injection flow 2 3 S ALL paths IAW 1-E-1 (B) Depress the RCS to RO & SRO-I minimize break flow and refill PZR during SGTR 3 3 S - Verify time interval for Lpzr to reach >69% (JPM Step
- 5) during prep week.
(1-E-3) (AP)
ALL
- Should the applicant be selecting their own RHR flowrate (i.e. use of AP-11 Attachment 3)? How else is control of RHR Core Cooling (SF 4P) being assessed by this JPM? (JPM only mandates restoration of flow)
- Why are bullets 3 and 4 of Initial Conditions included? Are these indications not available in the simulator? These should be removed.
- Add in a bullet in Initial Conditions to state: System Engineer reports no air entrainment issues in the RHR system.
- Modify the Initiating Cue to read: Restore RHR flow to 3500 gpm using 1-AP-11.
- Modify simulator setup for 1-RH-FCV-1605 to fail CLOSED when RHR flow reaches 3500 gpm. Remove evaluator direction cue within JPM Step 12. The guide (C) Restore RHR flow is written to have valve failed close after pump B is IAW 1-AP-11 (AP) 4P 3 x x E placed in START (JPM Step 11). Why would 1605 fail prior to use to comply with Step 12?
- What is the significance of JPM Step 12 failure criteria related to flow band (I.e. >3400 gpm and <
3600 gpm). The failure criteria of this step should simply be not attaining the directed RHR flowrate (of 3500 gpm). Modification requires revision to the Task Standard (pg 2).
- If RHR Pump A (1-RH-P-1A) is started during performance of JPM Step 11, is this step met? R: No, its locked out. Certainly not a good practice (unexpected trip), but would it meet the JPM standard?
- If 1-RH-FCV-1605 has failed closed, how is MANUAL control available to complete JPM Step 13? Are AUTO/MAN functions controlled separately in this simulator? R: Yes, can control in MAN mode.
4/23 Applicant decides where to restore RHR flow to.
RO & SRO-I
- No K/A Referenced.
- Why does the Cue direct him to the RNO? If the cue (D) Xfer SDS to steam press mode (AP) 4S 3 x E states completed through Step 4, and the applicant is told to start at Step 4 RNO, who evaluated Step 4 couldnt be met and RNO required? R: This is operationally valid to start here and is not unusual.
ES-301 Operating Test Review Worksheet Form ES-301-7
- Step 1 of JPM (Step 4 RNO a) states that only one switch is critical to be in OFF/RESET, yet not a Critical Step!! No real CS identified in JPM.
- RNO step is not directed in the procedure in use.
Candidate is to complete his procedure in AP-3, identify it did not work, and then perform IOAs of AP-
- 38. Although it is normal to verify system response the operator could miss this and place the switches in ON in step 4g and consider the JPM complete without missing or misperforming any procedural step.
4/23 Will work on addressing the above.
RO & SRO-I
- Can be a pre-brief JPM (if licensee requested)
- Why are the bullets listed in the Initial Conditions included? The first two indications are readily available (E) Drain the PRT 5 3 x E in the simulator and the third, 70%, can be easily misconstrued by an applicant (Initiating Cue reads 75%). All three ICs can be removed.
-Page 1 and Page 3 of JPM guide dont match.
RO & SRO-I
- Revise Initiating Cue to state: You are directed to start the 1H EDG IAW 1-ECA-0.0, Attachment 10, starting on Step 3. Revise the JPM to remove these first two performance standards.
- Revise the listed Performance Cues for JPM Steps (F) Re-start a DG with 3, 8 and 10 to be examiner cues (providing requested an auto start signal 6 3 x E temps as the OATC).
present (AP)
- Step 12 not marked as Alternate path starts here.
-The JPM on pg. 2 is listed as Alternate Path: 1H EDG trips and 1J EDG must be started. But the JPM is written with the EDG Output Breaker failing to automatically close and the operator must take action to manually close breaker.
ALL
- Remove Initial Condition bullets 1 (AUTO), 3 (OPERABLE), 5 (N-43), and 6 (100% pwr). These conditions can be deduced by the applicant in a simulator environment.
- Revise JPM Step 9 performance cue to read as an (G) Respond to a actual examiner cue.
malfunction of the PRM 7 3 x E
- There are no evaluation steps present after JPM Step NI 9 (Procedure Step 6), when revising this cue, include that another operator will continue from here, to end the JPM. All following JPM steps can be deleted.
- The Performance Standard states that the failed channel will be placed in test. The procedure has you defeat the failed channel.
(H) Place CW Pmp in RO ONLY service 8 3 x E
- Can be a pre-brief JPM (if licensee requested)
ES-301 Operating Test Review Worksheet Form ES-301-7
- Remove Initial Condition bullets 2 (RTS), 3, 4 (initial conditions met), and 5 (HPs)
- Add Initial Condition that operator is stationed at the Intake structure and ready for OP-48.2 performance.
- Revise JPM Guide to start at Procedure step 5.7.7 (currently JPM Step 6).
- Revise Initiating Cue to read: ... IAW 1-OP-48.2 starting on Step 5.7.7
- Initial conditions not clear. How many Circ Water Pumps are running? Is the candidate to perform section 5.5, 5.6 or 5.7 of the procedure. Does it matter?
(I) Trip the main turbine locally (FR-S.1) (AP) 1 3 S ALL (J) Align both MD AFW pumps to feed SG via 4S 3 S RO & SRO-I hand CV hdr (AP-22)
ALL
- (How is this SF 6, Electrical?)
- Agree with comment above, this JPM does not satisfy Safety Function 6. System K/A selected (003) is not (K) Isolate the RCP seals locally (ECA-0.0) 6 x U included on list of systems approved for SF6 per NUREG-1122 and JPM task is not relevant to evaluation of SF6 knowledge.
Will write a new alternate path to replace this for locally starting EDG.
ES-301 8 Form ES-301-7 Instructions for Completing This Table:
Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.
- 1. Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.
(ES-301, D.3 and D.4)
- 2. Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)
- 3. In column 3, Attributes, check the appropriate box when an attribute is not met:
The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)
The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)
All critical steps (elements) are properly identified.
The scope of the task is not too narrow (N) or too broad (B).
Excessive overlap does not occur with other parts of the operating test or written examination. (ES-301, D.1.a, and ES-301, D.2.a)
The task performance standard clearly describes the expected outcome (i.e., end state). Each performance step identifies a standard for successful completion of the step.
A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).
- 4. For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:
Topics are linked to the job content (e.g., not a disguised task, task required in real job).
The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to safely operate the plant. (ES-301, D.2.c)
- 5. Based on the reviewers judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 5.
- 6. In column 6, provide a brief description of any (U)nacceptable or (E)nhancement rating from column 5.
Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a (S)atisfactory resolution on this form.
ES-301 9 Form ES-301-7 Facility: North Anna Scenario: 1 Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
- 1. Synch MG to the grid 1a. Raise pwr to 25%,
control SGWL with MFRV bypasses in MAN
- 2. LCV fails low. Loss of CHG flow
- 4. Running SW pump trips, backup fails to start in Manual or Auto, must X realign another SW Pump in the field
- 5. Letdown leak X 5a Excess Letdown placed in service No credit for anyone, lead into the next event.
A thrown turbine blade will occur which will cause a failure of the condenser boot. A rapid loss of vacuum will occur. 1-AP-14 (loss of vacuum) will require a turbine trip, since reactor power is
- 6. Turbine blade thrown below P-8 a manual reactor trip will be required. This overlaps with a written exam question. Q22
Add: (to match scenario 6)
The unit was shut down 4 days ago to repair G106M Disconnect. Power has been stable at 12% for several days due to a problem with potential Conductor hot spots. This problem has been resolved and all paperwork is complete.
ES-301 10 Form ES-301-7 Facility: North Anna Scenario: 2 Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
2a. Pwr reduction for SG PORV failure. Rods fail to insert auto.
- 3. VCT Lvl Xmtr fails low
- 5. RCS leak outside cntmt in Safeguards X
- 6. LOCA outside cntmt X
- 7. Failure of SI to act auto or man X
- 8. Failure of Train B of Phase A Q44 overlaps with the turnover. 4/27 Will change to CN pump instead. Only two events for BOP prior to major. Sim exam guide missing last two events.
Add: (to match scenario 6)
The unit was shut down 4 days ago to repair G106M Disconnect. Power has been stable at 12% for several days due to a problem with potential Conductor hot spots. This problem has been resolved and all paperwork is complete.
ES-301 11 Form ES-301-7 Facility: North Anna Scenario: 3 Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
- 1. Swap Bearing Clg pumps Block valve must be used due to stuck open. PORV Controller must be used to
- 2. PT-1444 fails high X X close spray valves.
- 3. B SG level Median Select failure low (Median Select)
- 4. RCS Leak X
- 5. Pwr reduction
- 6. MSL leak 6a. Rx trip w/ MS isolation failure 6b. Loss of all Aux FW 6c. Loss of sec. heat sink w/ RCS bleed & feed X Must use RNO due to 1 PORV not available Starting on page 27 to page 30, several Error! Reference source not found. Also, on pg. 34 & 35.
ES-301 12 Form ES-301-7 Facility: North Anna Scenario: 4 Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
- 1. Stby Cond Pmp will HLD for B HPHDT fails partially open and pump trips. Standby Condensate not auto-start X pump will not auto-start.
Running CH Pump Trips (Check Valve Fails Open) and Stby pump will auto
- 2. Restore LD X start - Must restore LD.
- 3. FF channel fails high on B SG X Ramp power to 70% w/i 30 minutes. Crew receives call from system operator directing them to ramp the unit to 70% power with the next 30 minutes. Crew
- 4. Lower power ramps unit down.
4a. Rods fail to move in auto during pwr ramp
- 6. Auto SI will not actuate
- 8. Terry Turbine doesnt start automatically Just like scenario 2, change FW to CN. 5 CTs listed, only 3 marked in the events listing on pg. 1 of the scenario guide. Check the other scenarios.
Please mark the CT in the event listing also.
CT-1 Does not appear critical for this scenario. How does a loss of one CCP lead to degraded safety for this scenario (CT is scenario dependent)?
Event 2 has the CT listed beside it, Must restore letdown. (CT). This does not seem to coincide with CT 1 wording: Crew manually isolates previously running charging pump, to prevent damage to ECCS component.
Is there another TS for this scenario? A minimum of 2 is required per scenario.
On pg. 23 you have a NOTE for TS-3.3.1. Is this correct? If so, it needs to be added to the front page and the body of the scenario.
ES-301 13 Form ES-301-7 Facility: North Anna Scenario: 5 (Removed, not needed due to class size reduction) Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
- 1. Ramp unit down Ramp down for turbine valve freedom test.
- 2. PZR LI 1461 fails high X Must isolate containment IA to reset Containment Air Receiver Relief Valve. 1-
- 3. Loss of IA inside cntmt IA-C-1 will trip upon loss of IA and 1-SA-C-1 will not auto start (BOP will start).
- 4. Running CHG pump trips and stby fails to X auto start 4a. Restore LD
- 5. A Steam flow channel III fails high causing X X MFRV to open.
- 6. A MFRV fails closed with failure of reactor to trip auto or X manually
- 7. Turb will not trip auto or man
- 8. Emergency borate valve wont open.
BIT must be injected.
ES-301 14 Form ES-301-7 Facility: North Anna Scenario: 6 Exam Date: 6/8/2020 1 2 3 4 5 6 7 8 9 10 Required Verifiable Scen.
Event Realism/Cred. LOD TS CTs U/E/S Explanation Actions actions Overlap
- 1. Swap to 1-CH-P-1B in service. Place 1-CH-P-1 A in Auto
- 2. Ramp up using dilution/turbine
- 3. 1RC-PCV-1455A spray valve fails open. RO must take X X manual control and close
- 5. 1-CH-FT-1122 fails high. Must restore charging flow
- 6. C SG FF fails high X X Reactor trip required. Reactor does not trip either auto or an. Crew enter 1 FR-
- 7. Rod ejection occurs S.1
- 8. Turb does not trip auto X
- 9. SI does not auto actuate X Only two BOP events prior to the major. Is LHSI not a TS related item (turnover item)?
Verify no TS items are in any scenario turnover.
ES-301 15 Form ES-301-7 Instructions for Completing This Table:
Use this table for each scenario for evaluation.
2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.
3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f)
- opening, closing, and throttling valves
- starting and stopping equipment
- raising and lowering level, flow, and pressure
- making decisions and giving directions
- acknowledging or verifying key alarms and automatic actions (Uncomplicated events that require no operator action beyond this should not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)
5 Check this box if the level of difficulty is not appropriate.
6 Check this box if the event has a TS.
7 Check this box if the event has a critical task (CT). If the same CT covers more than one event, check the event where the CT started only.
8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.
10 Record any explanations of the events here.
In the shaded boxes, sum the number of check marks in each column.
- In column 1, sum the number of events.
- In columns 2-4, record the total number of check marks for each column.
- In column 5, based on the reviewer's judgement, place a checkmark only if the scenario's LOD is not appropriate.
- In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)
- In column 8, record the number of events not used on the two previous NRC initial licensing exams. A scenario is considered unsatisfactory if there is < 2 new events. (ES-301, D.5.b; Appendix D, C.1.f)
- In column 9, record whether the scenario as written (U)nacceptable, in need of (E)nhancement, or (S)atisfactory from column 11 of the simulator scenario table.
ES-301 16 Form ES-301-7 Facility: Exam Date:
1 2 3 4 5 6 7 8 11 Scenario % Unsat. Explanation Event Events TS TS CT CT Scenario U/E/S Totals Unsat. Total Unsat. Total Unsat.
Elements 1 7 0 3 0 3 0 0 S 2 8 0 2 0 3 0 0 S 3 7 0 2 0 2 0 0 S Only one TS entered on pg. 1 of scenario. One questionable CT related to 4 8 0 1 0 5 1 0 S loss of charging pump.
6 8 0 2 0 6 0 0 S Verify tripping RCPs has safety significance for this scenario.
Instructions for Completing This Table:
Check or mark any item(s) requiring comment and explain the issue in the space provided.
1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).
This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).
2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:
- a. Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the-controls and balance-of-plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column 2.
- b. TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D-2. Enter the total number of unsatisfactory TS entries/actions in column 4. (ES-301, D.5d)
- c. CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D-2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.
2+4+6 7 In column 7, calculate the percentage of unsatisfactory scenario elements: 100%
1+3+5 8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is 20%, annotate with (E)nhancement or (S)atisfactory.
9 In column 9, explain each unsatisfactory event, TS, and CT. Editorial comments can also be added here.
Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario is marked by a (S)atisfactory resolution on this form.
ES-301 17 Form ES-301-7 Site name: North Anna Exam: 2020-301 Date:
OPERATING TEST TOTALS Total Total Total %
Total Explanation Unsat. Edits Sat. Unsat.
- All SRO JPMs (5) did not meet the SRO-only criteria required by NUREG-1021 (ES-301, D.3.c)
- One RO JPM had no procedural tie for task Admin. JPMs 9 6 3 0 66.7 performance (written to a skill-of-the-craft performance standard). As-written JPM is unusable as an examination instrument as required by NUREG-1021 (Appendix C, B.3)
- As-written JPM K task (Isolate the RCP seals Sim./In-Plant locally (ECA-0.0)) has no tie with identified 11 1 5 5 9 JPMs Safety Function 6 (Electrical) as required by NUREG-1021 (ES-301, D.4.a)
Scenarios 5 0 4 5 20 Op. Test 25 6 12 10 24 Totals:
Instructions for Completing This Table:
Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.
- 1. Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs. For scenarios, enter the total number of simulator scenarios.
Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and 2.
simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.
Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous 3.
tables. This task is for tracking only.
- 4. Total each column and enter the amounts in the Op. Test Totals row.
Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test 5.
Total) and place this value in the bolded % Unsat. cell.
Refer to ES-501, E.3.a, to rate the overall operating test as follows:
- satisfactory, if the Op. Test Total % Unsat. is 20%
- unsatisfactory, if Op. Test Total % Unsat. is > 20%
Update this table and the tables above with post-exam changes if the as-administered operating test 6.
required content changes, including the following:
- The JPM performance standards were incorrect.
- The administrative JPM tasks/keys were incorrect.
- CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
- The EOP strategy was incorrect in a scenario(s).
- TS entries/actions were determined to be incorrect in a scenario(s).
ES-401, Rev. 11 PWR Examination Outline Form ES-401-2 Facility: North Anna Date of Exam: June 24, 2020 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. 1 3 3 3 3 3 3 18 18 3 3 66 Emergency &
2 1 1 2 2 1 2 99 2 2 44 Abnormal Plant N/A N/A Evolutions Tier Totals 4 4 5 5 4 5 27 27 5 5 1010 1 3 2 2 2 3 3 3 1 3 3 3 28 28 3 2 55 2.
2 1 1 1 1 1 1 1 0 1 1 1 10 10 2 1 33 Plant Systems Tier Totals 4 3 3 3 4 4 4 1 4 4 4 38 38 5 3 88
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 1 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, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
- 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 11 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 007EK2.02 Reactor Trip - Stabilization - Recovery 2.6 2.8 Breakers, relays and disconnects
/1 008AK2.03 Pressurizer Vapor Space Accident / 3 2.5 2.4 Controllers and positioners 015AK1.04 RCP Malfunctions / 4 2.9 3.1 Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow 025AK3.01 Loss of RHR System / 4 3.1 3.4 Shift to alternate flow path 026AA1.02 Loss of Component Cooling Water / 8 3.2 3.3 Loads on the CCWS in the control room 027AK1.01 Pressurizer Pressure Control System 3.1 3.4 Definition of saturation temperature Malfunction / 3 038EG2.2.40 Steam Gen. Tube Rupture / 3 3.4 4.7 Ability to apply technical specifications for a system.
054AA2.08 Loss of Main Feedwater / 4 2.9 3.3 Steam flow-feed trend recorder 055EA2.06 Station Blackout / 6 3.7 4.1 Faults and lockouts that must be cleared prior to re-energizing buses 056AG2.4.18 Loss of Off-site Power / 6 3.3 4.0 Knowledge of the specific bases for EOPs.
057AA1.04 Loss of Vital AC Inst. Bus / 6 3.5 3.6 RWST and VCT valves Page 1 of 2 06/05/2019 1:04 PM
ES-401, REV 11 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 058AK3.01 Loss of DC Power / 6 3.4 3.7 Use of dc control power by D/Gs 062AA2.03 Loss of Nuclear Svc Water / 4 2.6 2.9 The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3.08 Loss of Instrument Air / 8 3.7 3.9 Actions contained in EOP for loss of instrument air 077AG2.2.42 Generator Voltage and Electric Grid 3.9 4.6 Ability to recognize system parameters that are entry-Disturbances / 6 level conditions for Technical Specifications WE04EK2.2 LOCA Outside Containment / 3 3.8 4.0 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WE05EK1.3 Inadequate Heat Transfer - Loss of 3.9 4.1 Annunciators and conditions indicating signals, and Secondary Heat Sink / 4 remedial actions associated with the (Loss of Secondary Heat Sink).
WE11EA1.3 Loss of Emergency Coolant Recirc. / 4 3.7 4.2 Desired operating results during abnormal and emergency situations.
Page 2 of 2 06/05/2019 1:04 PM
ES-401, REV 11 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 001AG2.2.38 Continuous Rod Withdrawal / 1 3.6 4.5 Knowledge of conditions and limitations in the facility license.
036AA1.04 Fuel Handling Accident / 8 3.1 3.7 Fuel handling equipment during an incident 037AK3.02 Steam Generator Tube Leak / 3 3.2 3.5 Reset and check of Condensate air ejector exhaust monitor 051AA2.02 Loss of Condenser Vacuum / 4 3.9 4.1 Conditions requiring reactor and/or turbine trip 068AK3.03 Control Room Evac. / 8 3.7 4.3 Transfer of AFW flow control valves and pumps to local control 074EG2.4.31 Inad. Core Cooling / 4 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures WE03EK2.2 LOCA Cooldown - Depress. / 4 3.7 4.0 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WE08EA1.1 RCS Overcooling - PTS / 4 3.8 3.8 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE15EK1.1 Containment Flooding / 5 2.8 3.0 Components, capacity, and function of emergency systems.
Page 1 of 1 06/05/2019 1:04 PM
ES-401, REV 11 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 003K6.02 Reactor Coolant Pump 2.7 3.1 RCP seals and seal water supply 004A1.07 Chemical and Volume Control 2.7 3.1 Maximum specified letdown flow 004A4.10 Chemical and Volume Control 3.6 3.2 Boric acid pumps 005K5.09 Residual Heat Removal 3.2 3.4 Dilution and boration considerations 006A4.10 Emergency Core Cooling 3.8 4.2 Safety parameter display system 007A3.01 Pressurizer Relief/Quench Tank 2.7 2.9 Components which discharge to the PRT 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 Method of forming a steam bubble in the PZR 008K3.03 Component Cooling Water 4.1 4.2 RCP 010A4.02 Pressurizer Pressure Control 3.6 3.4 PZR heaters 010K6.04 Pressurizer Pressure Control 2.9 3.2 PRT 012A2.03 Reactor Protection 3.4 3.7 Incorrect channel bypassing Page 1 of 3 06/05/2019 1:04 PM
ES-401, REV 11 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 013K2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control 022A3.01 Containment Cooling 4.1 4.3 Initia tion of safeguards mode of operation 026K1.01 Containment Spray 4.2 4.2 ECCS 026K1.02 Containment Spray 4.1 4.1 Cooling water 039K4.08 Main and Reheat Steam 3.3 3.4 Interlocks on MSIV and bypass valves 059G2.2.42 Main Feedwater 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications 059K3.02 Main Feedwater 3.6 3.7 AFW system 061K5.05 Auxiliary/Emergency Feedwater 2.7 3.2 Feed line voiding and water hammer 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps 062A1.01 AC Electrical Distribution 3.4 3.8 Significance of D/G load limits 063A1.01 DC Electrical Distribution 2.5 3.3 Battery capacity as it is affected by discharge rate Page 2 of 3 06/05/2019 1:04 PM
ES-401, REV 11 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 063G2.4.31 DC Electrical Distribution 4.2 4.1 Knowledge of annunciator alarms, indications, or response procedures.
064G2.1.31 Emergency Diesel Generator 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.
073K4.01 Process Radiation Monitoring 4.0 4.3 Release termination when radiation exceeds setpoint 076K2.08 Service Water 3.1 3.3 ESF-actuated MOVs 078K1.01 Instrument Air 2.8 2.7 Sensor air 103A3.01 Containment 3.9 4.2 Containment isolation Page 3 of 3 06/05/2019 1:04 PM
ES-401, REV 11 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 001A4.11 Control Rod Drive 3.5 4.1 Determination of SDM 011K2.02 Pressurizer Level Control 3.1 3.2 PZR heaters 015K3.06 Nuclear Instrumentation 2.9 3.2 Reactor regulating system 028K6.01 Hydrogen Recombiner and Purge 2.6 3.1 Hydrogen recombiners Control 041A3.05 Steam Dump/Turbine Bypass Control 2.9 2.9 Main steam pressure 045A1.05 Main Turbine Generator 3.8 4.1 Expected response of primary plant parameters (temperature and pressure) following T/G trip 055G2.2.44 Condenser Air Removal 4.2 4.4 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 056K1.03 Condensate 2.6 2.6 MFW 068K5.04 Liquid Radwaste 3.2 3.5 Biological hazards of radiation and the resulting goal of ALARA 075K4.01 Circulating Water 2.5 2.8 Heat sink Page 1 of 1 06/05/2019 1:04 PM
ES-401, REV 11 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 G2.1.26 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).
G2.1.7 Conduct of operations 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
G2.2.6 Equipment Control 3.0 3.6 Knowledge of the process for making changes to procedures G2.2.7 Equipment Control 2.9 3.6 Knowledge of the process for conducting special or infrequent tests G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.11 Radiation Control 3.8 4.3 Ability to control radiation releases G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.2 Emergency Procedures/Plans 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
G2.4.21 Emergency Procedures/Plans 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions G2.4.43 Emergency Procedures/Plans 3.2 3.8 Knowledge of emergency communications systems and techniques.
Page 1 of 1 06/05/2019 1:04 PM
ES-401, REV 11 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 009EG2.2.37 Small Break LOCA / 3 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 011EG2.4.3 Large Break LOCA / 3 3.7 3.9 Ability to identify post-accident instrumentation.
022AA2.01 Loss of Rx Coolant Makeup / 2 3.2 3.8 Whether charging line leak exists 029EA2.02 ATWS / 1 4.2 4.4 Reactor trip alarm 040AG2.4.45 Steam Line Rupture - Excessive Heat 4.1 4.3 Ability to prioritize and interpret the significance of each Transfer / 4 annunciator or alarm.
WE05EA2.1 Inadequate Heat Transfer - Loss of 3.4 4.4 Facility conditions and selection of appropriate procedures Secondary Heat Sink / 4 during abnormal and emergency operations.
Page 1 of 1 06/10/2019 8:54 AM
ES-401, REV 11 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 024AA2.04 Emergency Boration / 1 3.4 4.2 Availability of BWST 076AG2.4.41 High Reactor Coolant Activity / 9 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
WE02EA2.2 SI Termination / 3 3.5 4.0 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
we14EG2.2.37 Loss of CTMT Integrity / 5 3.6 4.6 Ability to determine operability and/or availability of safety related equipment Page 1 of 1 06/10/2019 8:57 AM
ES-401, REV 11 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 006A2.02 Emergency Core Cooling 3.9 4.3 Loss of flow path 010G2.4.9 Pressurizer Pressure Control 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
013A2.04 Engineered Safety Features Actuation 3.6 4.2 Loss of instrument bus 022A2.05 Containment Cooling 3.1 3.5 Major leak in CCS 073G2.4.21 Process Radiation Monitoring 4.0 4.6 Knowledge of parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control.
Page 1 of 1 06/10/2019 8:58 AM
ES-401, REV 11 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 034G2.4.31 Fuel Handling Equipment 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures.
072A2.03 Area Radiation Monitoring 2.7 2.9 Blown power-supply fuses 079A2.01 Station Air 2.9 3.2 Cross-connection with IAS Page 1 of 1 06/10/2019 9:00 AM
ES-401, REV 11 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 G2.1.32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.
G2.1.4 Conduct of operations 3.3 3.8 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license statur, 10CFR55 etc.
G2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.16 Emergency Procedures/Plans 3.5 4.4 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
G2.4.30 Emergency Procedures/Plans 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
Page 1 of 1 06/10/2019 8:59 AM
ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO T1/G1 025AK3.03 There are no Immediate Actions in the Loss of RHR procedures. Replaced with 025AK3.01 RO T2/G1 063G2.4.11 Selected generic KA is not listed in ES-401D.1.b. Replaced with 063G2.4.31 RO T2/G2 055G2.2.42 No Technical Specification criteria for condenser air removal. Replaced with 055G2.2.44 RO T3 G2.3.13 Same KA as on SRO section. Replaced with G2.3.11 SRO T2/G2 034G2.4.8 No EOPS for fuel handling accidents. Replaced with 034G2.4.31
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal General Comments:
- 1. The objective of Tier 1 written examination questions is demonstrated knowledge and proficiency of how to safety operate the plant during emergency or abnormal conditions. These facility evolutions are a significant aspect of operating a nuclear power plant safely, and knowledge of these evolutions, including the use of abnormal and emergency procedures as appropriate, must be robustly understood by each licensed operator.
- 2. All Tier 1 questions must meet this objective.
Satisfactory ways of meeting this objective include, but are not limited to, the following: (1) information contained in the sites procedures, including alarm response procedures, AOPs, EOPs, and their associated bases documents; (2) diagnosis that leads to selection of the procedures that should be used to respond to the evolution, (3) the progression of an event, and (4)assessment of the integrated plant response to emergency or abnormal situations crossing several plant systems and/or safety functions.
- 3. Licensee failed to use logic trees given in NUREG-1021 to justify RO/SRO plausibility or knowledge statements.
- 4. Correct answer statements not given on most questions and supporting documentation from procedures and lesson material not provided in the question.
Doesn't meet the Tier 1 criteria as written.
4/22/2020 Will look at revising question to add the RNO actions for BOTH SI not being 1 EPE007EK2.02 H 3 M E/S B 41.7, 45.7 resetable.
5/7 Question rewritten to ask RNO column criteria for 1-E-0 for breaker G-12 not auto opening. Sat Doesn't meet the Tier 1 criteria as written.
Should not tell the applicant what the event is.
Should give the indicators and diagnose the event and procedure to be in.
2 APE008AK2.03 H 2 N E/S A 41.7, 45.7 4/4/2020 New question submitted. Tier 1 met.
Still need analysis information for the new question. Analysis info provided. Sat Doesn't meet the Tier 1 criteria as written.
41.8, 10 /
4/4/2020 New question submitted. Tier 1 met.
3 APE015AK1.04 H 2 B E/S D 45.3 SAT. Still need analysis information for the new question. Analysis info provided. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal A' & 'C' Distractor is not plausible. What does 'A' mean by "removing a PZR safety valve"? The definition of Natural Circulation is: The difference of density being the only driving force. Why would you then need an SI pump operating? Doesn't meet "modified" criteria based on original question (ID # 2607) change. Additional stem info added, but not needed to answer the question. Question 4 X APE025AK3.01 F 3 X M U/E/S B 41.5,10 is exactly the same as the bank question otherwise. New Questioned Created to replace this question.
New question reviewed. Meets KA and is Tier 1. Don't see how you arrived at this answer using this procedure?
Reference is incorrect, should be 1-GOP-13.1. Change to 1-GOP-13.1, add the word GUIDELINES.
5/7 Updated changes noted above. Sat Doesn't meet the Tier 1 criteria as written. P&ID should be provided with supporting information 41.7 / 45.5 so the answer can be accessed.
5 APE026AA1.02 F 3 B E/S C / 45.6 4/22/2020 New question written. Appears to meet Tier 1 & KA.
Doesn't meet the Tier 1 criteria as written. Why give PRT pressure in units "PSI"? Why give containment pressure if not used for as a choice in the answer? R: Needed to add to PRT pressure.
6 APE027AK1.01 H 3 N E/S D 41.8 /
4/4/2020 New question submitted. Tier 1 met.
SAT. Still need analysis information for the new question.
5/6 Analysis info added. Sat Is an RO expected to know this from memory?
This is below the line in the TS. This KA is for TS application. AP-24 contains the same information but you should have this listed in your references also. i.e. TS 3.4.4. Procedure selection is not used for this question therefore why not list AP-24 in the stem and remove it from distractor D. B should say "If sustained for 1 41.10 / hour,...". Choice D doesn't seem very plausible.
7 EPE038EG2.2.40 F 4 B E/S A 45.3 Why not change it to "Action Level 1"?
4/20/2020 Licensee rewrote question to include AP-24 in stem. Still need to access other points noted above.
4/22/2020 D distractor changed to "maintain current power level". Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't meet the Tier 1 criteria as written.
4/4/2020 New question submitted. Tier 1 met.
SAT. Still need analysis information for the new 41.10 / question.
8 APE054AA2.08 F 2 N E/S A 43.2 / 43.5 4/22/2020 Will change direction of failure and
/ 45.3 resubmit so as to not overlap with a scenario event.
5/7 Changes made as noted above. Sat.
Doesn't meet the Tier 1 criteria as written. The correct answer is led by having the stem have the same identifier "1J Emgergency Bus" in the answer "EMER BUS 1J". Drawings were not included in the reference package nor as a supplement for this question. Should part of the dwg be given as a reference or do you expect the applicant to know where and what these switches are from memory?
4/20/2020 Question rewrote to meet Tier 1 43.5 /
9 EPE055EA2.06 F 4 B E/S C 45.13 criteria. Answer choice has changed because question has been changed. Still need anlalysis information. Is dwg provided?
4/22/2020 This is an SBO event, correct procedure referenced and correct answer is still D.
5/7 Corrections made. Sat.
Plausibility for C distractor is for distractor B and 41.10 /
vice versa?
10 APE056AG2.4.18 F 2 B E/S A 43.1 /
45.13 4/22/2020 Reviewed w licensee. Sat Doesn't meet the Tier 1 criteria as written. If C is true, isn't D true also? Subset issue.
Question rewritten to change choice selection 41.7 / 45.5 and removed subset issuse. Appear to meet 11 APE057AA1.04 H 3 X N E/S B / 45.6 Tier 1. Still need analysis info.
5/7 Corrections made and analysis updated.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't meet the Tier 1 criteria as written.
Drawing 11715-ESK-11C Sheet 1 Drawing 11715-FE-21AG listed as a reference not provided with question or in the reference package. "when conditions are satisfied is ambiguous". I could always answer this as yes as one of the conditions could be Vital DC and therefore argue that choice D is also correct.
Not enough information provided to determine the correct answer.
4/20/2020 Rewrote question to ask procedure 41.5,41.10 attachment guideline. Need to verify. Above 12 APE058AK3.01 F 3 M E/S C / 45.6 /
concern is still present however. Sill need 45.1 analysis information provided for both correct answer and distractors.
4/22 Manually means from the MCR, locally means from the field. Will remove "when conditions are satisfied".
5/18 Made correction above and removed "locally" from distractor A & B as it is not needed and is confusing. Sat Could not locate the objective for LP given in developmental reference.
4/22 Will add LP to references. Verify again 43.5 / once received.
13 APE062AA2.03 H 3 N S B 45.13 4/27 Overlaps with Scenario 1 event 6.
Licensee will change to remove C-9 bullet from question to eliminate overlap Doesn't meet the Tier 1 criteria as written. First question has nothing to do with loss of IA.
NOTE: Not marked as unsat due to balance of coverage.
4/20/2020 Question rewritten. Not sure if 41.5,41.10 procedure is needed to answer the question.
14 APE065AK3.08 H 3 B E/S D / 45.6 /
4/22 Will readress to try and make it Tier 1 w/o 45.13 using a basis reasoning.
5/7 New question written to address above concerns. Sat.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Reference doesn't contain TS LCO that are 41.7 / affected. This should be listed to match the KA 41.10 / even if the LCOs are listed as a step in the 15 APE077AG2.2.42 F 3 B E/S C 43.2 / 43.3 procedure.
/ 45.3 5/7 LCO added as requested. Sat Doesn't meet Tier 1 criteria as written. How is "C" plausible if the leak is in the LHSI system?
4/22 Agreed need to change "C". Not plausible.
Upon discussion with licensee, the flowpath via 16 WE04EK2.2 H 3 X B E/S B 41.7 / 45.7 LHSI is still available. Will verify from the print sent via licensee. Verified. Sat "C" is a correct statement. Therefore two choices are correct.
41.8 /
4/22 Licensee response is that C isn't correct 17 WE05EK1.3 H 3 X X B US B 41.10, because both are needed, i.e. "AND" vs. "OR".
45.3 Nowhere do you explain how you arrive at the other choices. Also, it appears you arrive at the answer using only the graph and time after trip.
No other informattion in the stem is required.
LOD 1. The numbers should be low to high or 41.7 / 45.5 18 R WE11EA1.3 H 1 B U/S C / 45.6 high to low.
4/22 Will look at revising to increase LOD.
5/7 Question revised to be a two part question with plausible analysis for distractors given. Sat SAT based on first look. Meets KA. RCS press.is much greater than the COLR minimum limit (2205 #), not very plausiblie unless they think there is a high limit. Would pressure increase this much for a pulled rod?
19 X APE001AG2.2.38 H 2 B E/S A 41.7, 10 4/20/2020 Slight change to add "IAW 1-AP1.1
" No other change.
4/22 Will change distractor C to 2225#.
Completed Sat.
41.7 / 45.5 Sat 20 APE036AA1.04 F 2 M S C / 45.6
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Question source not identified. Doesn't meet KA. Question is not related to a SGTR event.
4/20/2020 Question rewritten to include 41.5,41.10 procedure. Above concern is still there.
21 APE037AK3.02 F 3 B U/S B / 45.6 /
4/22 Will rewrite IAW with E3.
45.13 5/7 Rewritten to address above. Sat Could not locate the objective for LP given in developmental reference.
4/22 Will add LP to references. Verify again once received.
4/27 Overlaps with Scenario 1 event 6.
Licensee will change to remove C-9 bullet from question to eliminate overlap with Scenario 1 43.5 / concern.
22 APE051AA2.02 H 3 B E/S A 45.13 5/7 Change made as noted above.
6/1 Answer A discussion appears to be irrelavant. AP13 is not the correct procedure and it does not appear to be addressed to choose an incorrect answer?
6/5 Discussion changed as noted above. Sat 41.5,41.10 Initial check looks SAT.
23 APE068AK3.03 H 3 N S D / 45.6 / 4/22 Reviewed SAT.
45.13 KA not met. No annunciator or ARP response.
4/22 Will write a question based on PCS input 41.10 /
24 EPE074EG2.4.31 F 3 B U/S D 45.3 and indications.
SAT based on first look. Meets KA.
25 X WE03EK2.2 F 2 B S B 41.7 41.7 / 45.5 SAT based on first look. Meets KA.
26 WE08EA1.1 F 3 N S D / 45.6)
Not sure what this question is asking? Choices A,B, & D which are incorrect all receive containment isolation signals. C (SW) does not receive a CI signal. Is the answer based on this or that that service water has molybdates? Revised Does this require any procedure knowledge? Change wording away from Unexpected water. With a LBLOCA much water is expected.
27 X WE15EK1.1 F 3 C E/S B 41.8, 10 Perhaps instead: What other source of water is affecting the sump sample results. Can you get a sample result without unisolating the containment isolation valve for the sump sample path? New Questioned Created to replace this question.
New question asks for entry criteria to FRP and a system knowledge question. Meets KA. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Add IAW procedure being referenced. Could not locate objective number in either RO or SRO AP lesson plan. The correct answer plausibility does not state why this is a correct answer. D not very plausible especially if you add the IAW AP-33.1, you wouldn't be in this procedure otherwise. Could change D to trip RCP, continue operating? Do you have a lower power 28 SYS003K6.02 H 2 B E/S C 41.7 / 45/5 level where this is feasible?
4/22 Will revise to change the power level to address the other concerns.
5/7 Power level lowered to change distractor D to make plausible. Other comments incorporated as noted above. Sat Tier 2. Meets KA.
29 004A1.07 H 3 B S A 41.5 / 45.5 Meets KA, written as if this is a Tier 1 criteria vs Tier 2. In 1-OP-8.3.5, the BATP is started AFTER the valve alignment? Procedure(s) 41/7 / 45.5 and/or dwg is not referenced for the distractor 30 004A4.10 F 3 N E/S D to 45.8 choices.
4/22 Reviewed w/ licensee. Licensee states it's correct in the GOP procedure for distractor C.
31 005K5.09 F 3 B S A 41.5 / 45.7 SAT based on first look. Meets KA.
Verify this is an SPDS display curve that is referenced. The licensee does not show how the answer is derived or how the distractors could have been mistakenly derived.
41.7 / 45.5 32 R 006A4.10 H 3 B E/S B to 45.8 4/22 Licensee stated this is an SPDS curve and will provide justification for other distractors. sat 33 007A3.01 F 3 B S D 41.7 / 45.5 SAT based on first look. Meets KA.
Written as if this is a Tier 1 criteria vs Tier 2. Is the procedure numbers necessary.
34 007K5.02 F 3 N E/S C 41.5 / 45.7 4/22 Reviewed with licensee. Sat.
None Initial check looks SAT 35 008K3.03 H 2 B S B given SAT based on first look. Meets KA. Dwg's not 41.7 / 45.5 provided to show the logic for this answer.
36 010A4.02 H 3 B S A to 45.8
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal SAT based on first look. Meets KA.
37 010K6.04 H 2 B S C 41.7 / 45.7 41.5 / 43.5 SAT based on first look. Meets KA. No content in 38 012A2.03 H 2 B S D / 45.3 / reference to the LP Objective stated for this 45.5 question. The relevant information is contained in the SI LP (pg 67) 39 013K2.01 F 2 B S C 41.7 SAT based on first look. Meets KA.
40 022A3.01 F 2 B S A 41.7 / 45.5 SAT based on first look. Meets KA.
41.2 to SAT based on first look. Meets KA.
41 026K1.01 F 3 N S C 41.9 / 45.7 to 45.8 SAT based on first look. Meets KA.
41.2 to 6/1 Correct grammar on A distractor, not plural.
42 026K1.02 H 2 N S D 41.9 / 45.7 6/5 Corrected grammar on A distractor. Sat to 45.8 43 039K4.08 H 2 N S B 41.7 SAT based on first look. Meets KA.
SAT based on first look. Meets KA.
41.7 / 4/27 Scenario 2 turnover given with FW-P-B 41.10 / OOS and no TS LCO entry. Overlap with this 44 059G2.2.42 F 3 N S C 43.2 / 43.3 question. Licensee changed turnover to CN
/ 45.3 pump.
SAT based on first look. Meets KA. Correct answer supporting information given however 45 059K3.02 H 3 N S D 41.7 / 45.6 dwgs listed not provided. Also objective 6035 not located in LP referenced.
SAT based on first look. Meets KA.
6/1 Is this to prevent or detect steam binding? If 46 061K5.05 F 3 N S B 41.5 / 45.7 it's to prevent, then it doesn't meet the KA. R:
Licensee stated this is to prevent therefore rewrite to meet KA.
6/5 Question was rewritten to better meet the KA SAT based on first look. Meets KA. Shouldn't 2-FW-PCV-259 be labeled? Is "lost" the correct word based on your system description or is "limited" the more appropriate word?
47 061K6.02 H 3 N S E 41.7 / 45.7 4/22 Will revise description to inform that the valve will completely close and therefore no flow to C SG.
SAT based on first look. Meets KA. Could not 48 062A1.01 F 2 B S D 41.5 / 45.5 locate objective 18009 in the AP LP.
49 063A1.01 F 2 N S A 41.5 / 45.5 SAT based on first look. Meets KA.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't meet the KA. No alarm or ARP addressed.
41.10 / 5/19 Question revised to add annunciators that 50 063G2.4.31 F 2 B U/S D 45.3 correspond to conditions that occur that also affect the DC electrical system.
41.10 / SAT based on first look. Meets KA. Left off here 51 064G2.1.31 H 3 B S A 45.12 Not sure about plausibility of "C" distractor.
52 073K4.01 F 3 B E/S A 41.7 4/22 Will add the word "directly" in the stem to ensure C is NOT a correct answer. Sat Is this minutia?
53 076K2.08 F 3 X N E/S C 41.7 4/22 Licensee stated this is not minutia. Sat No T.S. reference listed in distractor analysis to verify correct answer or to ensure this is above 41.2 to the line informaton appropriate for RO question.
54 078K1.01 H 3 B E/S D 41.9 / 45.7 to 45.8 4/22 Accepted question to meet the KA as IA is not used for sensor air. Sat SAT based on first look. Meets KA. Make sure it 55 103A3.01 H 3 B S B 41.7 / 45.5 does not overlap with Q43.
4/22 Verified no overlap issues.
41.7/45.5 Doesn't meet KA. Does meet KA. Justification to 56 001A4.11 F 2 X B U/S A to 45.8 be added.
57 011K2.02 H 3 B S A 41.7 SAT based on first look. Meets KA.
Meets KA. Not sure how plausible rods withdrawing would be for power failing high?
58 015K3.06 H 3 B E/S B 41.7 / 45.6 4/23 Will change to eliminate "withdraw" and have to choose insert rate in effect for the conditions given. Sat Insert LOCA conditions and remove 1st 59 028K6.01 F 3 B E/S C 41.7 / 45.7 statement. Meets KA. Sat 6/1 Unsat, this is strickly a math problem.
Doesn't test the KA.
6/2 Will look at modifying or changing question.
60 041A3.05 H 3 N U/S B 41.7 / 45.5 6/5 Question rewritten to meet the KA. Sat Explain the sequence of operation. Not sure I understand why RC pressure lowers immediately after the trip? Meets KA. Could not locate LP objective 1192.
61 045A1.05 H 3 N S D 41.5 / 45.5 4/23 Will change 1st question to ask what power will be at some time later.
6/1 Verify per the simulator or LP material. R:
Verified on simulator.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal SAT based on first look. Meets KA.
41.5 / 43.5 62 055G2.2.44 H 3 B S B / 45.12 Make this into a timeline that shows the pressure drop to eliminate the (20 psig lower than before) in the stem. Is any aditional information required to prevent someone arguing one of the other 63 X 056K1.03 H 3 B E/S B 41.2, .9 distractors is correct? Does a final power level need to be given, etc.?
4/23 Will add timeline. Sat 64 068K5.04 H 2 B S C 41.5 / 45.7 SAT based on first look. Meets KA.
65 075K4.01 H 3 B S D 41.7 SAT based on first look. Meets KA.
SAT based on first look. Meets KA. Per ES-401, D.2.a, Ensure that the questions selected for 41.10 / Tier 3 maintain their focus on plantwide 66 G2.1.26 F 2 B S A 45.12 generic K/As and do not become an extension of Tier 2.
41.5 / 43.5 SAT based on first look. Meets KA.
67 G2.1.7 H 3 B S B / 45.12 /
45.13 41.10 / SAT based on first look. Meets KA.
68 G2.2.6 F 2 B S C 43.3 /
45.13 41.10 / SAT based on first look. Meets KA.
69 G2.2.7 F 2 B S D 43.3 /
45.13 This is GET level.
4/23 Suggested rewriting for "waiving IV criteria for hanging tags".
5/19 Need to change 1st question to give the rad 41.12 / levels and ask if its a LOCKED HIGH RAD or a 70 G2.3.12 F 2 B U/E/S D 45.9 / HIGH RAD and the 2nd question to ask "Based 45.10 on the above rad level, ask if the "IV can OR can not be wavied for a LOCKED HIGH RAD AREA" IAW the IV procedure.
Changes made as noted above. Sat 41.11 / SAT based on first look. Meets KA.
71 G2.3.11 F 3 B S A 43.4 /
45.10 This is GET level.
41.12 / 4/23 Will look at providing an example or change 72 G2.3.4 F 1 B U/S D 43.4 / KA.
45.10 5/19 Revised question better meets the KA and be operationally oriented
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Seems A & D are the same and B encompasses C. If you think you should disagree but not sure of the specific response given in B then choose 41.7 / 45.7 C as it captures B also.
73 G2.4.2 H 3 X B U/S C / 45.8 4/23 Wide open KA. Will look at it .
5/7 Question revised to correct issues noted above. Sat 41.7 / 43.5 SAT based on first look. Meets KA.
74 G2.4.21 F 2 B S A / 45.12 Not sure if this meets KA.
41.10 / 4/23 Licensee will add justification for this 75 G2.4.43 F 2 B E/S C 45.13 meeting the KA criteria for an RO. Justification added. Sat Why is A incorrect? To evaluate the CSFST on containment, it is necessary to know the status of the quench spray system, which is not given in the stem. But, as the applicant must assume, one quench spray pump is running with discharge valve open (the expected condition),
containment is YELLOW when containment pressure is 31 psig, or 46 psia. ECA-1.1 only 41.7 / 43.5 preempts FR use when containment sump 76 X 009EG2.2.37 F 3 X N E/S D / 45.12 blockage has occurred, which has not (Note prior to step 1).
4/20/20 1-F-0 shows this is a yellow path therefore this is a correct question. Need to update devlopemental references.
5/7 References added. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal K/A mismatch. How does this test the ability to identify post-accident instrumentation? The K/A clearly means to distinguish between instruments that are post-accident qualified and those that are not. If North Anna uses some distinct marking to identify PAMS instruments test that here.
Distractors A and D are subsets of other answers (if B is true, A is also true, if C is true, D is also true).
Dont diagnose in stem. Give symptoms, not diagnoses. i.e. don't say a LOCA has occurred, give parameters for LOCA occurring.
77 EPE011EG2.4.3 H 3 X N U/S A 41.6 / 45.4 4/20/20 Licensee stated that RWLIS is PAMS related. Licensee agreed to change wording to correct subset issues.
Add the word ONLY. Add Dont trip RCPs to A and D Dont say LBLOCA - give conditions for LBLOCA 5/7 Does RVLIS lvl need to be addressed for this question? Response: Yes it does and is an associated PAMS instrument. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal The review was difficult because the explanation is inadequate. The reason that the break is on the charging line and not the seal injection line is that the fluid passing through FT-1122 goes to charging, but not seal injection. Since FI-1122 shows an increase in flow and flow is clearly not getting to the regenerative heat exchanger, the break must be between FT-1122 and the RHX.
Including a simplified P&ID would help.
The learning objective listed under general discussion shows that determining break location is an application of an RO learning objective. Given the break location, it is also RO 43.5/ knowledge that this break location does not 78 EPE022AA2.01 H 3 X B E/S A 45.13) affect the ECCS flowpath. This is not an SRO only question.
Perhaps there is an SRO only question on how this condition affects TRM 3.1.1.
4/20/20 Licensee stated they would change the break location to upstream of 1-CH_MOV-1289B, therefore; make it inoperable and therefore SRO.
5/7 Verified changes made as noted. Sat It seems that SS2.1 is not met because reactor power is < 5%. The same could be said for SS2.1. The stem says that power is now 10-6 amps and going down, but does not say how the power reduction was accomplished. If it was accomplished at the main control room (rod insertion and boration), SA2.1 would be correct.
Was something done locally? If so, what was it?
It would be more operationally valid to include a 43.5 / sequence of events leading up to this situation.
79 R EPE029EA2.02 H 2 X N U /S A 45.13 4/21/2020 Answer is correct as given. Power had to be above 5% prior to AMSAC working, a separate system after the timeout of the system.
When adding why answer is correct add information on AMSAC to explain that it is not taken credit for in the EAL Basis
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal In my experience, a double-ended steam line break inside containment causes the unaffected SGs to have a momentary high steam flow condition, which causes a momentary hi stm flow, lo stm pressure actuation. It seems to me that there is not enough information in the stem to exclude this possibility. The momentary nature of annunciator 1D-E3 only means that there is not currently a high steam flow condition on two or more SGs but does not exclude the possibility of a faulted SG.
Also, is knowing which procedure contains certain mitigation steps synonymous with selection of a procedure?
The knowledge being tested here is that when SI termination criteria are met in E-0. E-0 contains the steps to secure HHSI flow prior to transition 80 X APE040AG2.4.45 F 3 N E/S C 43.5 to ES-1.1, even though ES-1.1 also contains these steps. This seems trivial to me and not selection of procedure, since both E-0 and ES-1.1 will be used, and both contain these steps.
4/21/2020 Delta p comes in and not on the other SGs. WIll verify in the simulator. Confirmed isolation steps should be performed first in E0.
SAT. Ensure to describe that if fault was in containment then Delta P SI would occur and D-E3 woud not be in. 5/18/20 Added new bullet #4 "all 3 S/G pressures are 1000 psig and slowly increasing. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Subset issues. If A is true, B is true. If C is true, D is true. I question the operational validity of this sequence. It seems unlikely that bleed and feed can be avoided with all SGs faulted and no AFW. If bleed and feed is required, the crew stays in FR-H.1 until one SG level is restored to
> 11% NR, then goes to ES-1.1, step 9.
Perhaps specify that AFW is restored prior to bleed-and-feed conditions were met.
4/21/2020 Licensee will rewrite to remove two 43.5 /
81 WE05EA2.1 H 3 X N U/S A 45.13 bullets at the bottom of the stem and add WR level indication.
Change all NR levels are off scale low to WR levels are 29%.
Also get rid of E-2 to ECA-2.1, change to the next procedure entered would be E-2 or ECA-2.1.
5/6/ Made corrections above as noted. Sat This looks like this could be answered based on RO knowledge only. 1 hr criteria is RO knowledge. This is not the answer therefore using logic you can determine that C or D contains the correct answer for the 2nd half answer.
43.5 /
82 APE024AA2.04 F 3 X N U/S C 45.13 4/21/2020 Licensee will change distractor of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and add to plausibility that 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> pertains to the RWST (TS 3.5.4A) for concentration/temperature not in spec then 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore operability.
5/6 Made corrections as noted above. Sat Where is coolant activity given in this question?
Typo - Nobel should be Noble. I cannot validate the classification. Add an explanation of why the correct answer is correct (the process in the matrix used to explain how you obtained the 41.10 / correct answer).
83 R APE076AG2.4.41 H 3 X N U/S B 43.5 / 4/21/2020 Reviewed with licensee and agrees 45.11 SAT based on increased in coolant activity causing letdown high rad condition.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't appear to meet the KA. The answer is NOT for SI termination which is the KA. Dont diagnose in the stem. Give things that operators can see. B.(2) RCS pressure decreasing is not a credible distractor and lacks symmetry (A.(2) and C.(2) are opposites. Perhaps, RCS pressure is above some operationally significant threshold.
4/21/2020 Will rewrite question to correct above.
Re-write question where you are have terminated SI, and are now determining after securing SI if it 43.5 / needs to be reinitiated.
84 WE02EA2.2 H 3 X N U/S D 45.13 5/7 Corrections made for above notes. 5/18 Revised question to loss of subclooing the correct answer by changing the Cont pressure to 21 PSIA (Adverse Conditon).
Revised so pressurizer level is stable with 1-CH-FCV-1122 full open. Sat Doesn't appear to meet the KA. The answer is NOT related to high containment pressure.
4/21/2020 Licensee provided additional info.
This LCO is related to performance for High 41.7 / 43.5 Cont. pressure condition.
85 we14EG2.2.37 F 3 X N U/S B / 45.12 Show K/A tie from 1-CH-MOV-1381 to containment integrity - add citing of T.S basis document 3.6.3 .
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Typo "indicate" should be removed from 4th bullet. No procedure is selected. The method of accomplishing mitigation is not SRO only.
4/21/2020 Licensee explained this is in Att. 6 of E0 via CAP 2 and the BIT bypass is listed 1st and there is a 10 minute time limit (TCA) based on GOP-17. WIll add a timeline.
Describe condition for LOCA - I.e. RCS Pressure is 1500 PSIG and decreasing. Add time of 3 minutes at that step (use 0200 then 0203 etc..). Add GOP 17 to correct U/ distractor/answer analysis - this would clearly 86 SYS006A2.02 H 3 X N E/S B 41.5 / 45.5 explain why they cant open the valve locally within the 10 minutes TCA also add that the valve is opened manually later for the normal flow path procedurally. 5/18 removed times from bullets, deleted bullet infront of the loss of power and made the existing bullets a subset. By using the time the validators stated that this would have allowed the 1867 valve to come open.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't appear to meet the KA. The K/A is knowledge of low power/ shutdown implications in accident mitigation strategies, i.e. how does beginning at a shutdown condition change the mitigation strategy of an accident like LOCA or loss of RHR? For example, ECCS pumps are locked out for LTOP concerns or accumulators are isolated.
4/21/2020 Rewrite question (too close to 98) -
ensure K/A is met - must have a low power condition that would require actions - i.e. a normal cooldown/depress is in progress and an 41.10 / SI occurs - what actions are taken.
U/
87 010G2.4.9 H X N E/S D 43.5 /
5/6 KA is met. Not sure if all distractors are 45.13 plausible? Would the PZR PORV be opened with the SG PORV opened simultaneously, i.e. is choice B plausible?
5/19 Reviewed with licensee. Sat 6/1 RCPs are referred to in the plausibility analysis. Do we need to add the RCPs operating as a bullet?
6/5 R: Added two RCPs running to the stem.
Doesn't appear to meet the KA. The answer is 41.5 / 43.5 related to RPS not ESFAS.
88 013A2.04 H X N U/S A / 45.3 / 4/21/2020 Will change instrument to an ESFAS 45.13 instrument.
5/6 Appears to meet KA criteria now.
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Split operation is given in the stem conditions.
This implies dual unit operation therefore two of the choices are not plausible. KA match issue, KA is for Containment Cooling NOT Component Cooling Water (CCW). Also concern whether this meets SRO-only criteria. It is not choosing a procedure. New question written to match K/A.
Inadequate documentation. Basis for meeting the KA is blank.
41.5 / 43.5 KA match issue, KA is for Containment Cooling U/
89 X 022A2.05 F 2 X X N E/S C / 45.3 / NOT RCS coolant system.
45.13 4/21/2020 Will reexamine the "major leak of CCS" portion and if a new KA is required? Look at SW LP pg. 8 for a question. You could ask how you isolate a unit with a inadvertent CDA that has a major SW leak.
4/27 Make sure doesn't overlap with Q40.
5/6 New question hits the KA appropriately.
5/18, based on validators revised second part of question to address tech vs non tech spec. See step 2 of 1-AP-35. Sat It is not credible that subcooling is 50°F with a core exit temperature of 800°F. The saturation pressure for 800°F is 6437 psig. This CET reading should produce a large value of 41.5 / 43.5 superheat at any credible RCS pressure.
90 R 073G2.4.21 H 3 X N E/S B / 45.3 / 4/21/2020 Will look at simulator to get an 45.13 appropriate number.
5/7 Removed subcooling number from stem to correct above. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal Doesn't meet the KA. Added new K/A supplied by NRC.
I believe the procedure is 0-AP-30, not 1-AP-30.
The structure is clumsy, at best. 2) begins with If required. If the applicant chose for the first part that it is not required, the second question is N/A and implies that it really must be required.
Perhaps, when required. Please supply the reference for the time critical action of part 2.
UFSAR 15.4.5 Fuel Handling Accident (FHA)
U/ does not mention a 2 minute requirement.
41.10 /
91 X 034G2.4.31 F 2 X N E/S D 45.3 4/21/2020 Will revise, change to recently irradiated fuel.
Delete bullets, make 2) the first part, make second part the background for what Recently Irradiated Fuel is use the 300 hour0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (protect MCR) vs 100 Hour (protect public).
5/7 Reviewed rewritten question with changes noted above completed. Sat 41.5 / 43.5 Appears SAT. There is no explanation of 92 072A2.03 H 3 N S B / 43.3 / why the answer is correct.
45.13 This appears to be RO knowledge. Need to explain how this meets SRO knowledge.
41.5 / 43.5 4/21/2020 Reviewed w/ licensee. Basis 93 079A2.01 F X N U/S C / 45.3 / knowledge required for 2nd half of question.
45.13
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal K/A mismatch. Which system limit or precaution is this testing?
Two correct answers. The second part apparently intends to test the basis for the power reduction of LCO 3.1.4 Action A.1, which corresponds to the 61% of the stem.
The basis for Action A.1 says With the QPTR exceeding its limit, a power level reduction of 3% from RTP for each 1% by which the QPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power. I cant make this 41.10 / eliminate either of the two possible 94 G2.1.32 H 2 X B U/S A 43.2 / answers. Peak linear power affects both 45.12 core power distribution and DNBR (peak linear power is the denominator in DNBR)..
The General Discussion seems to be talking about another question, i.e. TS 3.12.B.6, 2% for each percent of tilt within 30 minutes. ???
4/21/2020 Will rewrite, generic P&L like pump start stops etc 5/7 Rewritten to incorporate notes above.
Sat If the RO is responsible for his own license activities, this is not SRO only. Revised Question to No-Solo type question.
New question. Do you have a learning U/ 41.10 /
objective to place in the Basis for SRO 95 X G2.1.4 F 2 X B E /S C 43.2 only section?
4/21/2020 Add the details discussed that SROs do not perform RO functions due to union plant restrictions. Sat First part is RO knowledge. Is 2nd part SRO?
4/21/2020 Reviewed w/licensee SAT.
41.5 / 43.2 6/1 Look at safety limit wording to see if it should 96 G2.2.22 F 2 B S B / 45.2) say "the consequence of exceeding this limit is more severe in MODE ____".
6/5 Reworded as noted above. Sat
ES-401 ST-2016-05 Written Examination Review Worksheet Form ES-401-9
- 1. 2. Ans 8 KA 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6 7 CFR LOK LOD Letter Referenc e stem job back- A/B/C/ 55.41x55.4 Explanation Q# (F/H) (1-5) cueing T/F cred dist partial minutia # / units K/A SRO-only B/M/N U/E/S Pre- focus link ward D 3y submittal 41.12 / Appears SAT. There is no explanation of 97 G2.3.13 F 2 N S C 43.4 / 45.9 why the answer is correct.
/ 45.10 Not sure if this meets KA.
Double jeopardy with question 87. Both 41.12 / require the applicant to choose between 98 G2.3.14 H 3 N S A 43.4 / ECA-3.1 and ECA-3.3.
45.10 4/21/2020 agreed to change Q87, this question SAT.
Appears SAT. There is no explanation of why the answer is correct.
5/7 Need to reword, grammatically the 2nd 41.10 / half of answer states "then", this implies the 99 G2.4.16 H 3 N E/S D 43.5 /
1st half has to be true. Remove the word 45.13 "then" from the sentence.
Change made. Sat 41.10 / Appears SAT. There is no explanation of 100 R G2.4.30 H 3 B S B 43.5 / why the answer is correct.
45.11