ML21327A355
| ML21327A355 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/16/2021 |
| From: | Joseph Demarshall NRC/RGN-III/DRS/OLB |
| To: | DTE Energy |
| Demarshall J | |
| Shared Package | |
| ML20055D900 | List: |
| References | |
| NRC-21-0039 | |
| Download: ML21327A355 (25) | |
Text
ES-301 Operating Test Review Worksheet Form ES-301-7
Facility: FERMI NUCLEAR POWER PLANT Exam Date: May 24 - June 2, 2021 1 2 3 4 5 6 Admin Attributes Job Content JPMs ADMIN Topic and K/A LOD (1-5) U/E/S Explanation I/C Critical Scope Perf.
Focus Steps (N/B) Std. Cues Overlap Key Minutia Job Link
SRO-A1.a Conduct of N/A - RO Only Exam Operations SRO-A1.b Conduct of N/A - RO Only Exam Operations SRO-A2 Equipment N/A - RO Only Exam Control SRO-A3 Radiation Control N/A - RO Only Exam
SRO-A4 Emergency N/A - RO Only Exam Procedures/Plan ES-301 Operating Test Review Worksheet Form ES-301-7
NRC:
- JPM is coded as Modified.
Identify the original JPM and explain how this this JPM has been Modified from the original version. Chief Examiners understanding, based on previous discussions, was that the Initial Conditions would specify that an SRV had actuated, requiring the inoperable instrument point to be replaced with the highest reading temperature of the operable instrument points plus 45°F, to make the JPM Modified.
- JPM Task Standard is deficient (see previous comment, i.e., not written for out-of-spec condition).
- Evaluator Key is correct for the condition described in the first comment above (i.e., SRV Conduct of actuated), which is NOT the Operations condition described in the 2.1.45 submitted version of the JPM.
RO-A1.a 3 X X X U
- Initial Conditions under the JPM 802-3006-402 Perform Torus S Information Section state that Water Average Torus Water Level is 140 inches.
Temperature Calculation Initial Conditions on the Cue Sheet state that Torus Water Level is 0 inches. Resolve this discrepancy.
- Initial Conditions under the JPM Information Section do not include information on the status of the SRVs. Initial Conditions on the Cue Sheet provide SRV status. Information should be identical in both locations.
- Revise the Cue prior to JPM Step
- 1 to provide the applicants with procedure 29.ESP.01 in its entirety. Delete the reference to Section 15.0
- Task Standard, in addition to referencing 29.ESP.01 Section 15.0, should also identify the calculated Average Torus Water Temperature Value of 84.59°F and the associated evaluation strategy (i.e., Temperature point inoperable and SRV not ES-301 Operating Test Review Worksheet Form ES-301-7
actuated).
- A range of values has not been specified for the calculation. A range of 0 to +.04 ( 84.59 to
- 84. 63) would seem appropriate.
FERMI:
- Corrected initial conditions to indicate Low-Low set is controlling pressure implying an SRV has actuated.
- Corrected the performance steps to include the appropriate actions and standards for this condition.
- Corrected the Torus water level initial condition to 0.
- Corrected the task standard to include sufficient detail and procedural references.
- Added an appropriate data range for the calculation based on the comment above.
- Corrected cue prior to step 1 to provide entire ESP procedure as instructed.
- Provided copy of JP-OP-802-3006-401, original unmodified version.
NRC:
- Individual JPM Elements, in addition to listing the JPM Steps, should also specify the associated procedure steps in Enclosure C. See convention used in Equipment Control JPM Conduct of RO-A2.
Operations
- Differences exist between (a) the 2.1.25 Initial Conditions (Condition N in the 3rd bullet) and Initiating Cue RO-A1.b Determine 3 X X E information on the JPM 802-4101-211 RHR Reservoir S Information Section, AND (b) the and RHR Cue Sheet. Also, the Cue Sheet Cooling Tower Initiating Cue does not need to Operation include the Enclosures B and C information. Information should be identical in both locations.
- Revise the Cue prior to JPM Step
- 1 to also provide the applicants with procedure 20.000.28 (in its entirety).
- Performance Standard for JPM Step #1 needs to specify how the ES-301 Operating Test Review Worksheet Form ES-301-7
RHRSW HX Return Temperature is determined (i.e., by interpolation using the guidance in the Note prior to Step 2.1.1.3 of Enclosure C, OR using the RHR Reservoir Temperature vs Instrument Milliamp Readings Graph on Enclosure B; if appropriate to use the graph for RHRSW Return Temperature ).
- Provide a marked up evaluator key of the Enclosure B Graph for the RHR Reservoir Temperature.
- Provide a marked up evaluator key of the Enclosure B Graph for the RHRSW Return Temperature if appropriate to use the graph for this application.
- JPM Step 6 should specify 90°F in accordance with Step 2.2.1.4 of Enclosure C.
- Remove the check boxes below the Initiating Cue on the Cue Sheet. Use of the check boxes can potentially cue the applicants.
Sufficient information is provided in the Initiating Cue for the applicants to provide all of the required information.
- JPM page numbering is incorrect.
FERMI:
- Corrected the initiating condition and cue discrepancies.
- Corrected page numbering
- Deleted cue sheet check boxes
- Corrected step 6 as directed
- Added procedure step numbers as directed
- Corrected cue prior to step 1
- Added performance standards for steps 1 and 2 as directed.
- Added enclosure B plot for evaluator key Equipment NRC:
RO-A2 Control U
- JPM is coded as Modified.
315- 0004-101 2.2.12 3 X X S Identify the original JPM and explain how this this JPM has been Modified from the original ES-301 Operating Test Review Worksheet Form ES-301-7
Perform version. Chief Examiners 24.138.06, Jet understanding, based on Pump previous discussions, was that an Operability out-of-spec condition would be Test - Two introduced in the Jet Pump Loop section of the surveillance to make the JPM Modified.
- JPM Task Standard is deficient (see previous comment, i.e., not written for out-of-spec condition).
- Provide a marked up evaluator key for the Jet Pump calculations, including a copy of the out -of-spec plot(s).
- JPM Step 6 (procedure 24.138.06, Step 5.1.6) incorrectly references Steps 5.1.1 and 5.1.2.
The correct procedural steps are 5.1.3 and 5.1.4.
FERMI:
- Original unmodified JPM and evaluator key are now provided.
- Added an out of spec data point for one JP as requested. Modified performance standard for that step appropriately
- Corrected JPM standard as directed
- Corrected JPM step 6 as directed.
NRC:
- The Examiner Cue prior to JPM Step #1 states Provide Examinee with Cue Sheets and copy of 20.000.07. As previously discussed, the JPM is to be performed in the simulator.
Radiation Accordingly, applicants will be Control 2.3.5 required to first locate the RO-A3 E procedure in the simulator, at 802-4101-454 Calculate 3 S which point the Examiner will Offgas provide a copy of the AOP.
Radioactivity Applicants will also be required to Release use simulator instrumentation and the OFFGAS LOG RADIATION MONITORS CONVERSION FACTORS FOR TECHNICAL SPECIFICATION 3.7.5 sheet posted on the rear of panel H11-P601.
ES-301 Operating Test Review Worksheet Form ES-301-7
Revise the Examiner Cue prior to JPM Step #1 to reflect the fact that the Examiner is only to provide the Cue Sheet.
- Recommend using calculated values that are closer to the TS required value of 340 mCi/sec.
Calculated values are both less than 1 mCi/sec.
- A range of values has not been provided for the calculated Offgas Release Rates. Provide an appropriate range of values for each Rad Monitor.
- The Conversion Factors on the OFFGAS LOG RADIATION MONITORS CONVERSION FACTORS FOR TECHNICAL SPECIFICATION 3.7.5 sheet provided with the JPM package are missing the Factor of 10 value
FERMI:
- Corrected the initial first examiner cue and added cue prior to step 2 for the conversion factor sheet
- Changed indicated values to result in calculated value just below TS limit as directed
- Added range of acceptable values to step 4.
- Corrected conversion factor sheet.
ES-301 Operating Test Review Worksheet Form ES-301-7
1 Simulator/In-Plant Safety Function JPMs and K/A
NRC:
- Initiating Cue under the Job Information Section does not match the Initiating Cue on the Cue Sheet with respect to Procedure steps that have been completed. Information should be identical in both locations.
- The Examiner Cue prior to Step #1 of the JPM states that place-keeping is complete thru Step 8.2.9. The Initiating Cue in the Job Information Section states that Steps 8.2.1 through 8.2.8 are complete.
Sim A 1 E
- Include Noun Name for Annunciator 315- 0004- 002 202001 A4.01 3 S 3D138 in JPM Step 20. Noun Name is RECIRC PUMP A MOTOR VIBRATION HIGH.
- Noun Name for Annunciator 3D138 is missing under References in the JPM Information Section. Provide the Noun Name.
FERMI:
- Corrected initiating cue as directed.
- Corrected examiner cue prior to step 1 as directed
- Added noun name for 3D138 as directed NRC:
- The ES-301-2 Outline submitted by the Chief Examiner (CE) for the SRO-I position selected Sim JPM B to be excluded. The ES-301-2 that was included as part of the 75-Day submittal, had instead excluded Sim JPM H. Sim JPM B was specifically Sim B 2 selected by the CE so that all applicants 315- 0108- 001 204000 A4.08 3 S could be tested on Safety Function 9 (Sim JPM H). Note that Safety Function 2 is tested both in the simulator and in the plant, whereas Safety Function 9 is only tested in the simulator. Revise the ES-301-2 for the SRO-I position to exclude Sim JPM B only.
CE NOTE: ES-301-2 Outline for the SRO-I position corrected. Note however, that only ES-301 Operating Test Review Worksheet Form ES-301-7
the RO version of the exam was administered based on the final selection of applicants.
FERMI:
- CrtRO -Ilis directe NRC:
- Remove the Critical Step designation from Step #4 of the JPM. Step #4 is a Verify step, the performance of which is not required to meet the Task Standard. Ensure the JPM Cover Sheet is updated to reflect the change S C 3 E in designation.
315- - 202 3 X S
FERMI:
- Corrected step 4 to non-critical as directed.
- Corrected step 1 AOP reference as directed.
NRC:
- Specify Safety Function (SF) 4 under the Licensed Operator Exam Information Section of the JPM. SF 2 is currently specified. Within the context of the ES-Sim D 4 E 301-2 developed for this exam, SF 4 has 315- 0140- 410 209001 A4.03 3 S been appropriately applied to this JPM to meet the SF criteria delineated in ES-301 of NUREG-1021.
FERMI:
- CrtF as direct NRC:
- Initiating Cue is incorrect. Cue currently directs the applicant to reduce pressure to less than 1.68 psig. Initial Conditions state that Primary Containment Pressure CANNOT be kept below the PCPL. JPM Step 6 (29.ESP.07, Step 2.5) requires the S E 5 E applicant to stop venting the Torus 802- - 502 A 3 X S between 32 to 39 psig if venting to lower pressure below the PCPL Curve.
Revise the Initiating Cue accordingly on both the Cue Sheet and in the JPM Information Section of the JPM.
- The Licensed Operator Exam Information Section of the JPM incorrectly lists 10 - Emergency Plant Evolutions, under Safety Function.
ES-301 Operating Test Review Worksheet Form ES-301-7
Remove this reference.
- Revise First Examiner Cue prior to Step #1 of the JPM to also provide a copy of 29.ESP.07 after the applicant locates the procedure.
- JPM Step 12 ELEMENT incorrectly references 23.404 SGTS Hard Card Step 1.1.a. Should reference Step 1.2.a.
Should reference Step 2.16.
- Examiner Cue between JPM Steps 12 and 13 does not appear to be applicable and should therefore be removed. JPM is for venting the Torus (Section 2.0), not the Drywell (Section 1.0). If the applicant performs the procedure as written, then there would be no need to cue the applicant as indicated.
- JPM page numbering is incorrect.
FERMI:
- Corrected initiating cue as directed
- Removed reference to SF 10
- Corrected first examiner cue as directed
- Corrected step 12 procedure step as directed.
- Corrected step 18 procedure step as directed.
- Removed step 12/13 examiner cue as directed.
- Crted page numberin g.
S F 6 3 S 315 - -004 NRC:
- Editorial: Third bullet of the Initial Conditions on both the Cue Sheet and the JPM Information Section contain an extra S in the title of AOP 20.000.19.
- Revise First Examiner Cue prior to S G 7 E Step #1 of the JPM to also provide a 802- - 217 A 3 S copy of AOP 20.000.19 after the applicant locates the procedure.
- Specify only Safety Function (SF) 7 under the Licensed Operator Exam Information Section of the JPM. SFs 2, 3, and 7 are currently specified. Within the context of the ES-301-2 developed for this exam, SF 7 has been ES-301 Operating Test Review Worksheet Form ES-301-7
appropriately applied to this JPM to meet the SF criteria delineated in ES-301 of NUREG-1021.
FERMI:
- Removed extra S from cues
- Added cue to provide procedure in first cue as directed.
- Removed reference to SF 2 and 3 as directed.
NRC:
- Second bullet of the Initial Conditions under the JPM Information Section does not match that of the Initial Conditions on the Cue Sheet.
Information should be identical in both locations.
- Initiating Cue does not direct the applicants to shutdown SGTS. At Fermi, is it understood that the direction to return RB HVAC to service under the given conditions (i.e.,
following automatic start of SGTS and isolation of RB HVAC), includes shutdown of SGTS?
- Revise First Examiner Cue prior to Step #1 of the JPM to also provide a copy of 23.426 after the applicant locates the procedure.
- Move the second Examiner Cue to Sim H 9 X E after Step 1 of the JPM for consistency 315- 0166- 003 288000 A4.01 3 S with the convention utilized in other JPMs.
- The performance standard for 23.426, Step 5.1.2.2.a (Verify initiating logic has been reset) is missing from Step 2 of the JPM. Step 5.1.2.2.a is scripted in the ELEMENT Section of JPM Step 2.
- Designate JPM Step 3 as a Critical Step. Step 3 is necessary to ensure proper Exhaust/Supply Fan configuration and operation. Ensure the Cover Sheet is update to reflect this information.
- Is Critical Step 5.1.2.5.c (located within Step 5 of the JPM), accurate as written? The version of 23.426 that is being used to review the JPM is Rev
- 66. The Rev 66 version specifies a 5-second (versus 7-second) delay for the selected Supply Fan start and does not ES-301 Operating Test Review Worksheet Form ES-301-7
provide any information or make a distinction between the first and remaining Supply Fan starts, unlike Step 5.1.2.5.c in the JPM Step 5 ELEMENT section which talks about a 2-second delay for the remaining Exhaust Fans starts. Need to confirm the accuracy of the Step 5.1.2.5.c information.
CE NOTE: Actions to perform shutdown of SGTS removed from JPM during Onsite Validation. JPM Type Code on ES-301-2 changed from Modified to Direct F rom Bank based on this revision.
FERMI:
- Corrected Initial Conditions as directed.
- Revised Initiating cue to include shutdown of SGTS div 1.
- Corrected first examiner cue as directed.
- Moved second examiner cue to after step 1 as directed.
- Added bullet for verifying logic reset to step 2 performance std as directed.
- Fermi recommends leaving step 3 as non-critical since the switches will already be in the correct position as a matter of normal system alignment.
The applicant must verify this, however, if not verified the task could still be completed satisfactorily.
- Corrected step 5 element regarding procedure step 5.1.2.5.c as directed.
NRC:
- Task Standard, as written, also needs to IP-I 2 E state the RCIC Low RPV Pressure Isolation 802-3006-301 295031 EA1.05 3 X S has been reset.
FERMI:
- Crtask standard as directe NRC:
- Initial Conditions, second bullet, should state that the RPS MG Set A(B) is in STANDBY, ready for start. Second I P - J 7 E bullet presently states that the RPS 315- - 001 3 X S MG Set is in STANDBY, ready to be placed in service. The words ready to be placed in service are also used in the Task Standard. Conditions following successful completion of the ES-301 Operating Test Review Worksheet Form ES-301-7
Task Standard should be different than those specified in the Initial Conditions.
Ensure that any changes made to the Initial Conditions are made in both the Job Information Section of the JPM and the on the Cue Sheet.
- Clearly specify within the JPM which RPS MG Set is to be started, whether it be A or B. Ensure that all affected steps within the JPM are revised accordingly. Remove all references to the other RPS MG Set.
FERMI:
- Corrected initial conditions as directed
- The JPM has been corrected to exclude the alternate division option as directed.
IP-K 8 3 S 315-0167-404 400000 A1.03
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 c orresponding 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. (Appendi x C, B.4)
- The JPMontns oprie cstlearly indice wnheyhould be ovid tthi Cs aretive aeading. (A ppendi*
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)
- Taskfmaetandard clearly descrishe e*ctcome (i., endtat.Eh pfmcstep identif i a stad fuccessf cion he step.
- Aimkp kas provid (, ierionitialed stes).
FolumJob Content,heck appropribo*fob content fl does not meet the following elements:
- Topics are linked to the job content (e.g., not a disguised task, task required in real job).
x The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to saf ely 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.
Facility: FERMI NUCLEAR POWER PLANT Scenario: 1 Exam Date: May 24 - June 2, 2021 1 2 3 4 5 6 7 8 9 10
Event Realism Required Verifiable
/Cred. Actions actions LOD TS CTs Scenario Overlap U/E/S Explanation
1 - Transfer TWMS from Bypass Mode S Normal Event to Cleanup Mode 2 - RPV Water Level 3 Instrument TS S Failure (B21-N080C) 3 - HPCI Logic Bus B Power TS S Failure 4 - East CRD Pump Breaker TS X S 2019 NRC Exam; Scenario 7, Event 6 (Previous 2 NRC Exams)
Fault/Trip 5 - SJAE Trip S 6 - FWH Level Reactivity Manipulation Instrument S Failure 7 - Lightening Strike Causes S Major Event Loss of Offsite Power NRC:
- Clearly identify the Critical Task action in the D2 so that it stands out from the 8 - EDG 12 Fails other action items (i.e., bold, highlight, different color, etc.).
to Auto Start (Recoverable). CT1 E FERMI:
Start Failure S
- Critical Task font bolded and underlined.
Trips on EDG
- CT updated to provide bounding conditions.
13 & 14
- During development and later in phone conversation with Chief Examiner, noted that this event was credited on D1 to BOP. ATC performs actions. Updated D1 and ES-301-5/6 to reflect this.
Major Event 9 - SBLOCA with E NRC:
RCIC Trip on CT2 S
- Clearly identify the Critical Task action in the D2 so that it stands out from the other Overspeed action items (i.e., bold, highlight, different color, etc.).
FERMI:
- Critical Task font bolded and underlined.
- CT update d t i ctions.
9 0 0 0 0 3 2 8 E Form ES-D-1 Prepared by NRC S
Facility: FERMI NUCLEAR POWER PLANT Scenario: 3 Exam Date: May 24 - June 2, 2021 1 2 3 4 5 6 7 8 9 10
Event Realism/ Required Verifiable Cred. Actions actions LOD TS CTs Scenario Overlap U/E/S Explanation
1 - Perform SDV Vent & Drain Valve S Normal Event Operability Test Reactivity Manipulation 2** - Degrading **ATC applicant actions in response to the Event 2 malfunction, resulted in a trip of the Condition on North RRMG Set and subsequent entry into Single Loop Operation, requiring insertion In-Service S of the CRAM Array to lower Reactor Power < 66.1%. Accordingly, the reactivity North RRMG manipulation originally scripted for Event 3 was invalidated and the Event 6 malfunction Set Lube Oil nullified. The ATC applicant was credited with (1) a reactivity manipulation in Event 2 for Pump actions taken in response to the North RRMG Set trip, and (2) a component failure in Event 3 for action taken in response to the #3 TCV unitized actuator fault. ES -301-5 appropriately updated.
Reactivity Manipulation
- ATC applicant actions in response to the Event 2 malfunction, resulted in a trip of the 3** - #3 TCV North RRMG Set and subsequent entry into Single Loop Operation, requiring insertion Unitized S of the CRAM Array to lower Reactor Power < 66.1%. Accordingly, the reactivity Actuator manipulation originally scripted for Event 3 was invalidated and the Event 6 malfunction Fault nullified. The ATC applicant was credited with (1) a reactivity manipulation in Event 2 for actions taken in response to the North RRMG Set trip, and (2) a component failure in Event 3 for action taken in response to the #3 TCV unitized actuator fault. ES-301-5 appropriately updated.
4 - Leading Edge Flow Meter TS S CE NOTE: Event deleted during Onsite Validation.
(LEFM)
System Failure 4 - RWCU Leak with Auto TS S Isolation Failure 5 - Turbine First Stage Pressure TS S Instrument Failure (C71-N052A)
6** - Gland Steam Normal CE NOTE: Event replaced during Onsite Validation.
Regulating Valve F433 2019 NRC Exam; Scenario 2, Event 5 (Previous 2 NRC Exams)
Controller **ATC applicant actions in response to the Event 2 malfunction, resulted in a trip of the Failure North RRMG Set and subsequent entry into Single Loop Operation, requiring insertion South Heater X S of the CRAM Array to lower Reactor Power < 66.1%. Accordingly, the reactivity Drain Pump manipulation originally scripted for Event 3 was invalidated and the Event 6 malfunction Trip with nullified. The ATC applicant was credited with (1) a reactivity manipulation in Event 2 for Failure of actions taken in response to the North RRMG Set trip, and (2) a component failure in Manual Event 3 for action taken in response to the #3 TCV unitized actuator fault. ES-301-5 Runback PB appropriately updated.
to Lower Power Major Event 7 - Neutron Flux NRC:
Instabilities /
- Critical Tasks CT-1 and CT-3 not flagged in the D2 with a parenthetical Hydraulic reference.
- Clearly identify the Critical Task actions in the D2 so that they stand out from the Common CT3 S other action items (i.e., bold, highlight, different color, etc.).
Discharge Header FERMI:
Rupture
- Critical Task font bolded and underlined; parenthetical reference added.
- s update d t i ctis.
NRC:
- Critical Task CT-2 not flagged in the D2 with parenthetical references.
- Clearly identify the Critical Task action in the D2 so that it stands out from the 8 Mnne other action items (i.e., bold, highlight, different color, etc.).
Trip /ypass 2 E Vaesr S FERMI:
- Critical Task font bolded and underlined; parenthetical reference added.
- CT updated to provide bounding conditions.
- AriticetonitinsiatitCT boundionditions.
9 Div W S Pp Tri Form ES-D-1 Prepared by NRC
- ATC applicant actions in response to the Event 2 malfunction, resulted in a trip of the 9 0 0 0 0 2 3 8 E North RRMG Set and subsequent entry into Single Loop Operation, requiring insertion 8** S of the CRAM Array to lower Reactor Power < 66.1%. Accordingly, the reactivity manipulation originally scripted for Event 3 was invalidated and the Event 6 malfunction nullified. The ATC applicant was credited with (1) a reactivity manipulation in Event 2 for actions taken in response to the North RRMG Set trip, and (2) a component failure in ES-301 18 Form ES-301-7
Event 3 for action taken in response to the #3 TCV unitized actuator fault. ES-301-5 appropriately updated.
Facility: FERMI NUCLEAR POWER PLANT Scenario: 4 (SPARE) INFORMATION REDACTED Exam Date: May 24 - June 2, 2021 1 2 3 4 5 6 7 8 9 10
Event Realism/ Required Verifiable Cred. Actions actions LOD TS CTs Scenario Overlap U/E/S Explanation
Form ES-D-1 Prepared by NRC
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,losing, and throttlia
- sttind stnpme
- rsind liel,l, and se
- ming decisis anviirtions
- knowledginifyie y msomic actis (Uicvtshatequirperctioyond ts shoul not be included on the operating test unless they are necessary to set th e 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 columumhe nb events.
- In lus 2 d t number of cck mks f eachol
- In colum based evi'sudgement, plcckmk onlyfcis LODs appropri
- In column 6, TS are required to be 2 for each sci (bp -.5.
- In columd tber ofventssed wevisRCnitiiceing ems. A scenario isonsid uatisftyf there is 2 new es. (ES -.ppen* D, C.f)
- In columd whher the scio asrittU)nceabled ofE)ancent, orS)isfacty frolu timat scenario tl
Facility: FERMI NUCLEAR POWER PLANT Exam Date: May 24 - June 2, 2021 1 2 3 4 5 6 7 8 11
Scenario Event Events TS TS CT CT % Unsat.
Totals Unsat. Total Unsat. Total Unsat. Scenario U/E/S Explanation Elements 1 9 0 3 0 2 0 0% E S
- ATC applicant actions in response to the Event 2 malfunction, resulted in a trip of the North RRMG Set and subsequent entry into Single Loop Operation, requiring insertion of the CRAM 9 E Array to lower Reactor Power < 66.1%. Accordingly, the reactivity manipulation originally 3** 8 0 2 0 3 0 0% S scripted for Event 3 was invalidated and the Event 6 malfunction nullified. The ATC applicant was credited with (1) a reactivity manipulation in Event 2 for actions taken in response to the North RRMG Set trip, and (2) a component failure in Event 3 for action taken in response to the
4 SPARE SCENARIO - INFORMATION REDACTED
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 column2.
- 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.
7 In column 7, calculate the percentage of unsatisfactory scenario elements: 2 + 4 + 6 p 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 e withb)cent p)isftory.
9 In column 11, 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.
Facility: FERMI NUCLEAR POWER PLANT Exam Date: May 24 - June 2, 20 21
OPERATING TEST TOTALS Total Total Total Total %
Unsat. Edits Sat. Unsat. Explanation
Admin. 2 2 0 JPMs 4 0 0 4
Sim/In-Plant 8 3 JPMs 11 0 0 11
Scenarios 3 0 3 0 0 3
Op. Test 2 13 3 11.11 All Enhancement items appropriately Totals: 18 0 0 18 0.0 addressed a nd al l UNSAT i tems c orrected post exam submittal.
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.
- 2. Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 andsimulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.
- 3. Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previoustables. This task is for tracking only.
- 4. Total each column and enter the amounts in the Op. Test Totals row.
- 5. Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. TestTotal) 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 O0%
- unsatisfactory, if Op. Test Total % Unsat. is > 20%
- 6. Update this table and the tables above with post-exam changes if the as -administered operating testrequired content changes, including the following:
- The JPM performance standards were incorrect.
x The administrative JPM tasks/keys were incorrect.
x CTs were incorrect in the scenarios (not including post scenario critical tasks defined in Appendix D).
x The EOP strategy was incorrect in a scenario(s).
x TS entries/actions were determined to be incorrect in a scenario(s).