ML19093B000
| ML19093B000 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/15/2019 |
| From: | Jenkins T Entergy Nuclear Indian Point 2 |
| To: | Peter Presby Operations Branch I |
| Shared Package | |
| ML18130A647 | List: |
| References | |
| CAC 00500, EPID L-2019-OLL-0012 | |
| Download: ML19093B000 (32) | |
Text
~Entergx NL-18-068 September 5, 2018 Mr. David Lew Regional Administrator Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd Suite 100 King of Prussia, Pennsylvania 19406-2713 Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, N.Y. 10511-0249 Tel (914) 254-2611 Clifford Chapin Manager, Training & Development
Subject:
Indian Point Unit 2 Initial Licensed Operator Examination Outline Indian Point Unit 2 Docket No. 50-247 DPR-26 Dear Sir; In preparation for the Indian Point Unit 2 Reactor Operator and Senior Reactor Operator initial licensing examinations, scheduled to start on February 4, 2019, Entergy Nuclear Operations, Inc. (Entergy) is providing the enclosed Reactor Operator and Senior Reactor Operator Written Examination Outlines to Mr. Peter Presby of your staff. The examination outlines are being provided in accordance with the instructions of NUREG-1021, "Operator Licensing Examination Standards for Nuclear Power Reactors," Rev 11.
In accordance with 10 CFR 55.49 and the Examination Security and Integrity Considerations in Examiner Standard ES-201, Attachment 1, the attached materials should be withheld from public disclosure until after the examinations are complete.
Entergy is making no commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Charles Kocsis, Superintendent, ILO Operations Training (914) 254-2065, Mr. Tim Jenkins, Senior Instructor Examination author at (914) 254-2995 or Mr. Robert Suneson, Senior Instructor Examination author at (914) 254-2635.
Sincerely,
~zj~.,
F.,tt..
Clifford S. Chapin Manager, Training and Development Signed per NUREG 1021, ES-201, C.1.g
Docket No. 50-247 NL-18-068 Page 2 of 2
Enclosures:
NUREG-1021, Rev. 11, Form ES-201-2, "Examination Security Agreement" NUREG-1021, Rev. 11, Form ES-201-2, "Examination Outline Quality Checklist" NUREG-1021, Rev. 11, Form ES-301-1, "RO Administrative Topics Outline" NUREG-1021, Rev. 11, Form ES-301-1, "SRO Administrative Topics Outline" NUREG-1021, Rev. 11, Form ES-301-2, "RO Control Room/In-Plant Systems Outline" NUREG-1021, Rev. 11, Form ES-301-2, "SRO-I Control Room/In-Plant Systems Outline" NUREG-1021, Rev. 11, Form ES-301-5, "Transient and Event Checklist" NUREG-1021, Rev. 11, Form ES-D-1, "Scenario 1 Outline" NUREG-1021, Rev. 11, Form ES-D-1, "Scenario 2 Outline" NUREG-1021, Rev.11, Form ES-D-1, "Scenario 3 Outline" NUREG-1021, Rev. 11, Form ES-D-1, "Scenario 4 Outline" NUREG-1021, Rev. 11, Form ES-D-1, "Scenario 5 Outline" NUREG-1021, Rev. 11, Form ES-401-2, "PWR Examination Outline" - RO/SRO NUREG-1021, Rev. 11, Form ES-401-3, "Generic Knowledge and Abilities Outline"-
RO/SRO NUREG-1021, Rev. 11, Form ES-401-4, "Record of Rejected K/As" - RO/SRO Operating Test Schedule (Preliminary) cc:
Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Mr. Donald Jackson.
Chief, Operational Safety Branch Division of Reactor Safety Region I U.S. Nuclear Regulatory Commission 21 00 Renaissance Blvd Suite 100 King of Prussia, Pennsylvania 19406-2713 Mr. Peter Presby Chief Examiner Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd Suite 100 King of Prussia, Pennsylvania 19406-2713 Resident Inspector's Office U.S. Nuclear Regulatory Commission Indian Point Unit 2 P.O. Box 59 Buchanan, N.Y. 10511-0059 w/o Enclosures w/o Enclosures with Enclosures w/o Enclosures
Operating test schedule 7 SRO-I candidates 5 RO candidates
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
IPEC Unit 2 Date of Examination:
2/4/2019 Examination Level: RO
~ SRO D Operating Test Number:
1 Administrative Topic (see Note)
Type Describe activity to be performed Code*
Conduct of Operations M
NAROs Prepare Reactivity Balance Load Change Conduct of Operations N
1940012125 RO 3.9 SRO 4.2 Review a Check Off List Equipment Control N
1940012214 RO - 3.9 SRO - 4.3 Prepare a Gaseous Waste Release Permit Radiation Control M
1940012311 RO - 3.8 SRO - 4.3 Perform initial NUE Notifications Emergency Plan MS 1940012443 RO - 3.2 SRO - 3.8 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 (2! 1)
(P)revious 2 exams (::; 1, randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
IPEC Unit 2 Date of Examination:
2/4/2019 Examination Level: RO D SRO
~
Operating Test Number:
1 Administrative Topic (see Note)
Type Describe activity to be performed Code*
Spent Fuel Pit Loading Conduct of Operations M
1940012142 RO - 2.5 SRO - 3.4 Review Reactivity Balance Load Change Conduct of Operations N
1940012125 RO 3.9 SRO 4.2 Review a Check Off List Equipment Control N
1940012214 RO - 3.9 SRO - 4.3 Review a Gaseous Waste Release Permit Radiation Control M
1940012311 RO - 3.8 SRO - 4.3 Classify Event and Complete Form EP-1, Part 1 Emergency Plan M
1940012441 RO - 2.9 SRO - 4.6 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 (:s; 3 for ROs; :s; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (e=: 1)
(P)revious 2 exams (:s; 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
IPEC Unit 2 Date of Examination:
2-4-2019 Exam Level: RO
[X]
SRO-I D SRO-U D Operating Test Number:
1 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. Retrieve A Dropped Rod SAN 1
001 OOOA408 RO - 3.7 SRO - 3.4
- b. Place Excess Letdown In Service SD 2
- c. Depressurize the RCS to Refill the Pressurizer SAEN 3
- e. Manually Actuate Containment Spray SAD 5
- f. Swap 6.9 Bus 6 from 138kV to 13.8 kV SN 6
- g. PT 404 Failure at the point of adding heat SALN 7
- h. Terminate Containment Pressure Relief SM 8
029000A301 RO - 3.8 SRO - 4.0 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- j. Lineup Backup Cooling to Charging Pumps RED 8
- k. Swap Gas Decay Tanks NAR 9
071 OOOA405 RO - 2.6 SRO - 2.6 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 I
Criteria for R /SR0-1/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room
{D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature
( L )ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 s 9/:5 8/:5 4
- ?
- 1/;?:1/;?:1
- ,
- 1/;?: 1/;?: 1 (control room system)
- ?
- 1/;?:1/;?:1
- ,
- 2/;?: 2/;?: 1 s 3/S 3/:5 2 (randomly selected)
- ?
- 1/;?:1/;?:1
ES-301 Control Room/In-Plant systems Outline Form ES-301-2 Facility:
IPEC Unit 2 Date of Examination:
2-4-2019 Exam Level: RO D SRO-I
~ SRO-U D Operating Test Number:
1 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. Retrieve A Dropped Rod SAN 1
001 OOOA408 RO - 3.7 SRO - 3.4 b.NA SRO
- e. Manually Actuate Containment Spray SAD 5
- f. Swap 6.9 Bus 6 from 138kV to 13.8 kV SN 6
- g. PT 404 Failure at the point of adding heat SALN 7
- h. Terminate Containment Pressure Relief SN 8
029000A301 RO - 3.8 SRO - 4.0 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- j. Lineup Backup Cooling to Charging Pumps RED 8
- k. Swap Gas Decay Tanks NAR 9
071 OOOA405 RO - 2.6 SRO - 2.6 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.
I
- Type Codes I
Criteria for R /SR0-1/SRO-U I
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 s; 9/s; 8/s; 4
.::1/.::1/.::1
.:: 1/.:: 1/.:: 1 (control room system)
.::1/.::1/.::1
.:: 2/.:: 2/.:: 1 s; 3/s; 3/s; 2 (randomly selected)
.::1/.::1/.::1
Appendix D Scenario Outline Form ES-D-1 Facility: _IPEC Unit 2. __ _
Scenario No.:
Op-Test No.: _1 __ _
Examiners: ____________ Operators:
Initial Conditions: Reset simulator to 100% power IC Load Simulator Schedule-Scenario1 Turnover # 22 ABFP has been out-of-service for bearing oil line r within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (ITS 3.7.5 - 72 hr AOT). 21 and 23 ABF Critical Tasks:
WOG E-0-A: Manually trip reactor from the CCR before WOG E-0-P: Manually actuate Main Steam isolation be Manually start SI system pumps before transition out of Event No.
2 3
4 5
6 7
8 9
Malf. No.
LOA-EPS182 RLY-PPL426-461 MAL-SGN005 RLY-PPL501 RLY-PPL502 SWI-SGS002 AOV-RCS003A Auto closure MSIVs blocked C (CRS)
Phase A reset failure C BOP C (ATC)
C (CRS)
PRZR PORV Fails open (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor ir for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is expected back rotected equipment.
Appendix D Scenario Outline Form ES-D-1 The scenario begins with the plant at 100% power with 22 Auxiliary Feedwater pump out of service expected to return in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The team will assume the watch and 24 Instrument bus will be deenergized. The team will enter and perform the actions of 2-AOP-IB-1 "Loss of Instrument Bus". When the BOP initiates attachment 5, N-41 will fail low. The instrument bus will not be recovered during the scenario With the failure of Nl-41 the team may enter 2-AOP-INST-1 or 2-AOP-Nl-1 and determine that the channel cannot be removed from service and requires a Tech Spec shutdown.
The team will then commence shutdown using 2-POP-2.1. T e ATC will borate and drive rods in manual (or at least monitor automatic insertion). The BOP wil er turbine power using the manual governor When the team has demonstrated enough of the sh generator trip open. An automatic trip will not occur, turbine overpeeds, a steam line in the turbine buildi will not actuate. The team will manually close the M The team will progress through 2-E-O, E-2, E-1 to ES-key switches to reset Phase A. Whe inated wn evolution, the output breakers on the nual trip will be successful. When the ill break. Automatic steam line isolation to stop the steam leak.
ase A will not reset re uiring the CV-456 will fail ope nd its associated block valve will blow a ing. The ill restart the Sat Injection system pumps and transition b
Appendix D Scenario Outline Facility: Indian Point 2 Scenario No.: g Op-Test No.: _J_
Examiners: ____________ Operators:
Turnover: After takin the watch the team will be direct accordance with AOP-RSD-1 due to steam leak on 21 Critical Tasks:
WOG E-0-D: Manually actuate at least one train of SIS-a following: Transition to any E-1 series, E-2 WOG E-2-A: Isolate the faulted SG WOG ECA-3.1-B: Cool down th 1 OOF/hr Event No.
2 Malf. No.
Form ES-D-1 yFRP.
o exceeding 3
tchets in due to malfunctioning movable gripper.
4 MAL-SGN004A Steam line rupture with failure of 23 MSIV to close.
5 RLY-PPL487/488 ailure of SI to actuate automatically.
6 MOC-AFW001 Failure of 21 AFW to autostart.
7 MAL-RCS014C 23 SGTR (N)ormal, (R)eactivity, (l}nstrument, (C)omponent, (M)ajor IPEC Unit 2 2019 Scenario 2
Scenario 2 Summary The scenario begins with the plant at 100% power with 21 Charging Pump and 21 CCW Pump out of service. The team will assume the watch and be directed to remove the unit from service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> using 2-AOP-RSD-1 (Rapid Shutdown) due to 21 SG non-return check valve having a steam leak.
While the team is preparing to shut down, LT-460 (controlling PZR level transmitter) will fail low.
This will cause charging pump speed to increase and letdown to isolate. The team will respond by placing the running charging pump in manual. AOP-INST-1 (Instrument and Controller Failures) will be entered. The failed channel will be defeated letdown restored.
The team will then commence shutdown using 2-AOP-rods in manual (or at least monitor automatic insertio using the manual governor.
Control Rod P-6 will ratchet into the core during rod This will require the load reduction to be stopped an (Rod Control Malfunctions).
After load reduction is resumed a requiring a reactor trip and clos close. SI will not automaticall SG. 21 AFW pump will not AFP or start 22 AFP.
IPEC Unit 2 2019 C will borate and drive nd the BOP will lower turbine power
- on due to a movable gripper failure.
condition evaluated per -AOP-ROD-1 occur will not uncontrolled manner, ruptured and transition to
-1, AOP-UC-1, E-0, E-2, E-3, ECA-Scenario 2
Appendix D Scenario Outline Facility: _IPEC Unit 2 __ _ Scenario No.:
3 __
Examiners: ____________ Operators:
Initial Conditions: Initialize to 100% power IC Turnover: No equipment OOS Critical Tasks:
WOG FR-H.1 A: Establish RCS bleed and feed when th 20%WR.
WOG FR-H.1 E: Establish greater than 400 gpm flow to Event Malf. No.
Event No.
Type*
XMT-CFW005 A
XMT-2 FHW015 A
3 NA Form ES-D-1 Op-Test No.: _1 __ _
4 FP Building (Effects ALL SG)
MOC-5 AFWOO tor driven AFW pumps fail to operate, 22 AFP is MOC-AFW002 6
CVH-22 AFW pump trips on overspeed after flow is established ATS019B MOC-7 SIS002 C(BOP) 21 and 22 SIP fail to auto start MOC-SIS003 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 The scenario begins with the plant at 100% power no equipment out of service. The team will assume the watch and 21 SG controlling feed flow channel (B) will fail low. The ATC will transfer Steam flow and Feed Flow channels to A to restore feedwater flow. The team will progress through 2-AOP-INST-1 and remove the channel from service (If evaluator requires). Once the channel is removed from service both heater drain tank pumps will trip due to a level failure on the heater drain tank.
The team will take actions in accordance with 2-AOP-FW-1 and reduce power to restore feedwater flow greater than steam flow. Once the plant is stable the team will determine a power reduction to approx. 400MW is required to close the 1 O" heater drain tank dumps. The team will commence a power reduction per 2-POP-2.1.
Once the power reduction is commenced a feed line b affecting all SG's. The ATC will recognize the reducti and close the MBFP discharge valves in accordanc auxiliary feedwater pumps will not function requiring pump to be aligned to feed all steam generators. W pump will trip.
The team will transition to 2-FR-H.1 SG's average wide range level de 21 and 22 Safety injection pum After the bleed path has bee required SG(s). Once feed in the Building will occur in feedwater flow and trip the reactor
'th 2-AOP-FW-1. Both motor driven turbine driven (22) auxiliary feedwater he 22 AFP turbine speed is raised the 3 lowest and bleed.
ally started.
II feed the
Appendix D Scenario Outline Facility: _IPEC Unit 2 __ _ Scenario No.: __ 5 __
Examiners: ____________ Operators:
Initial Conditions: Initialize to 100% power IC Turnover 21 EOG OOS LCO 3.8.1.b, day 6 of 7 day LCO. 21 ED tied to bus 5a and fully loaded.
Critical Tasks:
Establish at least 400 gpm AFW flow to the SGs before Manually start ESW pump(s) such that the EOG does n Event No.
2 3
Malf. No.
Event XMT-MSS053A Type*
Form ES-D-1 Op-Test No.:
1 __ _
4 inoperable EOG and FCU 5
6 7
8 XM CFW03 MAL-EPS006E BKR-DSG004 SST-DSG037A MOC-SWS008 6.9kv bus 5 faults when the Unit trips, 23 EDGs output breaker does not automatically close 23 Service Water pump does not autostart on powering 6a from 23 EOG (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 The team will assume the watch with 21 EOG in the progress of testing to exit the 7 day LCO 3.8.1.b. PT-412a will fail low, rods will auto insert and be subsequently stopped by the ATC. The team will perform the actions of 2-AOP-INST-1 and restore rods to their position prior to the malfunction, and remove the channel from service.
Once the channel is removed from service 25 CRF will trip on overcurrent, the team will take ARP/SOP actions to secure 25 CRF. When 25 CRF is removed from service 21 EOG will trip on low oil pressure. The NPO will notify the control room of the low oil pressure trip on 21 EOG and that there is oil in the sump under 21 EOG. The CRS will determine that with the EOG and CRF out of service they do not meet LCO 3.6.6 and that they requi e a 3.0.3 shutdown.
ode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. When the fail low, ucing the speed on MBFP The team will commence a 2-POP-2.1 shutdown to plac required reactivity manipulation is completed PT-408 and the team take actions in accordance with 2-AOP When the reactor trips 6.9kv bus 5 faults, deenergizi ST-1 and manually trip the reactor.
6.9Kv Buses 5, 1 and 2 and 480v bus 5a, none of which can have power restored. 22 ED deenergizes busses 2a and 3a. 23 EOG output brea
- 1s to start due to overcrank, this The team will perform the immediate actions of 2-E-O may be restored by ARP action or st A-0.0 an return to 2-E-O and transition to E oes not close in auto.
step 3 enter ECA-0.0. 80v bus 6a ervice water pump i tarted and terminated.
ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:
IPEC Printed: 0910412018 Date Of Exam:
0210412019 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
Total
- 1.
1 0
0 0
0 0
0 0
3 3
6
- Emergenc, 2
0 0
0 0
0 0
0 2
2 4
NIA NIA Abnormal Tier Plant Evolutions Totals 0
0 0
0 0
0 0
5 5
10
- 2.
1 0
0 0
0 0
0 0
0 0
0 0
0 3
2 5
Plant 2
0 0
0 0
0 0
0 0
0 0
0 0
0 I 2
I 3
Systems Tier 0
0 0
0 0
0 Totals 0
0 0
0 0
0 5
3 8
- 3. Generic Knowledge And 1
2 3
4 1
2 3
4 0
7 Abilities Categories 0
0 0
0 I
2 2
2 Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions 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 KIA 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 KIAs 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 KIA categories.
7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3.
Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
0910412018 7:45:23 am
PWR SRO Examination Outline Printed: 09/04/2018 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000015/000017 RCP Malfunctions / 4 X 2.1.20 - Ability to interpret and execute 4.6 1
procedure steps.
000026 Loss of Component Cooling Water/
X 2.1.19 - Ability to use plant computers 3.9 I
8 to evaluate system or component status.
000056 Loss of Off-site Power/ 6 X
AA2.45 - Indicators to assess status of 3.9 1
ESF breakers (tripped/not-tripped) and validity of alarms (false/not-false) 000062 Loss of Nuclear Svc Water/ 4 X
AA2.04 - The normal values and upper 2.9*
1 limits for the temperatures of the components cooled by SWS 000065 Loss of Instrument Air/ 8 X
AA2.06 - When to trip reactor if 4.2 I
instrument air pressure is decreasing 000077 Generator Voltage and Electric Grid X 2.1.32 - Ability to explain and apply 4.6 1
Disturbances / 6 system limits and precautions.
Kl A Category Totals:
0 0
0 0
3 3
Group Point Total:
6 09/04/2018 7:44:57 am
PWR SRO Examination Outline Printed: 09/04/2018 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000061 ARM System Alarms / 7 X
AA2.03 - Setpoints for alert and high 3.3 1
alarms 000069 Loss of CTMT Integrity I 5 X 2.2.36 - Ability to analyze the effect of 4.2 1
maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
W/E02 SI Termination/ 3 X
EA2.2 - Adherence to appropriate 4.0 1
procedures and operation within the limitations in the facility's license and amendments W /E 13 Steam Generator Over-pressure I 4 X
2.4.35 - Knowledge of local auxiliary 4.0 1
operator tasks during an emergency and the resultant operational effects.
Kl A Category Totals:
0 0
0 0
2 2
Group Point Total:
4 09/04/2018 7:45:02 am
Facility:
IPEC ES - 401 Sys/Evol #/Name 006 Emergency Core Cooling 012 Reactor Protection 039 Main and Reheat Stearn 062 AC Electrical Distribution I 03 Containment Kl A Category Totals:
09/04/2018 7:45:07 am Kl 0
PWR SRO Examination Outline Plant Systems - Tier 2 I Group I K2 K3 K4 K5 K6 Al A2 A3 A4 X
X X
0 0
0 0
0 0
3 0
0 Printed:
09/04/2018 Form ES-401-2 G KA Topic Imp.
Points X 2.4.45 - Ability to prioritize 4.3 1
and interpret the significance of each annunciator or alarm.
A2.01-Faulty bistable 3.6 1
operation A2.03 - Indications and 3.7 1
alarms for main steam and area radiation monitors (during SGTR)
A2.12 - Restoration of 3.6 1
power to a system with a fault on it X 2.2.44 - Ability to interpret 4.4 I
control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
2 Group Point Total:
5
Facility:
IPEC ES - 401 Sys/Evol #/Name 034 Fuel Handling Equipment 068 Liquid Radwaste 071 Waste Gas Disposal Kl A Category Totals:
09/04/2018 7:45:13 am Kl 0
PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 K2 K3 K4 KS K6 Al A2 A3 A4 X
X 0
0 0
0 0
0 2
0 0
Printed:
09/04/2018 Form ES-401-2 G KA Topic Imp.
Points A2.0l - Dropped fuel 4.4 I
element A2.04 - Failure of automatic 3.3 I
isolation X 2.2.38 - Knowledge of 4.5 I
conditions and limitations in the facility license.
I Group Point Total:
3
Facility:
IPEC Generic Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 09/04/2018 7:45:18 am Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline KA Topic 2.1.41 Knowledge of the refueling process.
Category Total:
2.2.13 Knowledge of tagging and clearance procedures.
2.2.40 Ability to apply Technical Specifications for a system.
Category Total:
2.3.11 Ability to control radiation releases.
2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Category Total:
2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
Category Total:
Generic Total:
Printed: 09/04/2018 Form ES-401-3 3.7 I
I 4.3 I
4.7 I
2 4.3 I
3.7 I
2 4.5 I
4.1 I
2 7
ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:
IPEC Printed: 08/16/2018 Date Of Exam:
02/04/2019 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
Total
- 1.
1 3
3 3
3 3
3 18 0
0 0
- Emergenc, 2
I I
2 2
2 I
9 0
0 0
N/A N/A Abnormal Tier Plant Evolutions Totals 4
4 5
5 5
4 27 0
0 0
- 2.
1 3
2 3
3 2
3 3
2 2
3 2
28 0
0 0
Plant 2
I I
I I
I I
I I
I I
0 10 0 I 0 0
0 Systems Tier 4
3 4
4 3
4 4
3 3
4 2
38 0
0 0
Totals
- 3. Generic Knowledge And 1
2 3
4 1
2 3
4 10 0
Abilities Categories 2
2 3
3 0
0 0
0 Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions 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 KIA 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 Kl 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 KIA categories.
7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 KIA catalog, and enter the KIA numbers, descriptions,
!Rs, and point totals(#) on Form ES-401-3.
Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
08/16/2018 11 :45:52 am
PWR RO Examination Outline Printed: 08/16/2018 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group I Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000007 Reactor Trip - Stabilization -
X EA2.0 I - Decreasing power level, from 4.1 I
Recovery/ I available indications 000008 Pressurizer Vapor Space Accident/
X AK 1.01 - Thermodynamics and flow 3.2 I
3 characteristics of open or leaking valves 000009 Small Break LOCA / 3 X 2.1.7 - Ability to evaluate plant 4.4 I
performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
000011 Large Break LOCA / 3 X
EA 1.15 - RCS temperature and pressure 4.2 I
000022 Loss of Rx Coolant Makeup/ 2 X
AA2.0l - Whether charging line leak 3.2 I
exists 000025 Loss of RHR System / 4 X
AK 1.01 - Loss of RHRS during all 3.9 I
modes of operation 000027 Pressurizer Pressure Control System X
AK2.03 - Controllers and positioners 2.6 I
Malfunction / 3 000029 A TWS I I X
EK3.06 - Verifying a main turbine trip; 4.2 I
methods 000038 Steam Gen. Tube Rupture/ 3 X
EK3.08 - Criteria for securing RCP 4.1 I
000040 Steam Line Rupture - Excessive X
AK2.0l - Valves 2.6*
I Heat Transfer/ 4 000054 Loss of Main Feedwater / 4 X 2.4.18 - Knowledge of the specific 3.3 I
bases for EOPs.
000055 Station Blackout/ 6 X
EA 1.02 - Manual ED/G start 4.3 I
000056 Loss of Off-site Power/ 6 X
AK3.0I - Order and time to initiation of 3.5 I
power for the load sequencer 000057 Loss of Vital AC Inst. Bus/ 6 X
AA2.06 - AC instrument bus alarms for 3.2 I
the inverter and alternate power source 000058 Loss of DC Power/ 6 X 2.4.20 - Knowledge of operational 3.8 1
implications of EOP warnings, cautions, and notes.
W /E04 LOCA Outside Containment/ 3 X
EK I. I - Components, capacity, and 3.5 I
function of emergency systems W /E05 Inadequate Heat Transfer - Loss of X
EA 1.3 - Desired operating results 3.8 I
Secondary Heat Sink/ 4 during abnormal and emergency situations W /E 11 Loss of Emergency Coolant Recirc. /
X EK2.2 - Facility's heat removal systems, 3.9 I
4 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 08/16/2018 11:45:24 am
PWR RO Examination Outline Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G
KA Topic Kl A Category Totals:
3 3
3 3
3 3
08/16/2018 11 :45:24 am Printed: 08/16/2018 Form ES-401-2 Imp.
Points Group Point Total:
18 2
PWR RO Examination Outline Printed:
08/16/2018 Facility:
IPEC ES-401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 003 Reactor Coolant Pump X
KS.OS - The dependency of 2.8*
I RCS flow rates upon the number of operating RCPs 004 Chemical and Volume Control X
KS.09 - Thermal shock:
3.7 I
high component stress due to rapid temperature change 004 Chemical and Volume Control X
K3.04-RCPS 3.7 I
005 Residual Heat Removal X
K4.12 - Lineup for 3.1 I
piggyback mode with CSS 006 Emergency Core Cooling X
K2.02 - Valve operators for 2.5*
I accumulators 007 Pressurizer Relief/Quench X
K4.0 I - Quench tank 2.6 I
Tank cooling 008 Component Cooling Water X
A 1.02 - CCW temperature 2.9 I
0 IO Pressurizer Pressure Contro I X
K2.02 - Controller for PZR 2.5 I
spray valve 012 Reactor Protection X
K3.0l - CRDS 3.9 I
013 Engineered Safety Features X
K6.0 I - Sensors and 2.7*
I Actuation detectors 022 Containment Cooling X
K 1.0 I - SWS/cooling 3.5 I
system 022 Containment Cooling X
A 1.02 - Containment 3.6 I
pressure 026 Containment Spray X
A4.05 - Containment spray 3.5 I
reset switches 039 Main and Reheat Steam X
A3.02 - Isolation of the 3.1 1
MRSS 059 Main Feedwater X
A3.02 - Programmed levels 2.9 1
ofthe SIG 059 Main Feedwater X 2.1.23 - Ability to perform 4.3 I
specific system and integrated plant procedures during all modes of plant operation.
061 Auxiliary/Emergency X
K6.02 - Pumps 2.6 I
Feedwater 061 Auxiliary/Emergency X
K6.01 - Controllers and 2.5 I
Feedwater positioners 062 AC Electrical Distribution X 2.4.4 7 - Ability to diagnose 4.2 1
and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
063 DC Electrical Distribution X
K4.02 - Breaker interlocks, 2.9*
1 permissives, bypasses and cross-ties 08/16/2018 11:45:35 am
PWR RO Examination Outline Printed: 08/16/2018 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000005 Inoperable/Stuck Control Rod/ 1 X
AK3.05 - Power limits on rod 3.4 I
misalignment 000028 Pressurizer Level Malfunction I 2 X
AK3.03 - False indication of PZR level 3.5 1
when PORV or spray valve is open and RCS saturated 000032 Loss of Source Range NI/ 7 X
2.4.2 - Knowledge of system set points, 4.5 1
interlocks and automatic actions associated with EOP entry conditions.
000060 Accidental Gaseous Radwaste Rel. /
X AA 1.0 I - Area radiation monitors 2.8 I
9 000068 Control Room Evac. / 8 X
AA2.05 -Availability of heat sink 4.2 I
000076 High Reactor Coolant Activity/ 9 X
AK2.0l - Process radiation monitors 2.6 1
W /E08 RCS Overcooling - PTS / 4 X
EK 1.2 - Normal, abnormal and 3.4 1
emergency operating procedures associated with Pressurized Thermal Shock W /EI O Natural Circ. I 4 X
EA2.2 - Adherence to appropriate 3.4 I
procedures and operation within the limitations in the facility's license and amendments W /E 15 Containment Flooding / 5 X
EA 1.3 - Desired operating results 2.8 I
during abnormal and emergency situations Kl A Category Totals:
1 1
2 2
2 1
Group Point Total:
9 08/16/2018 11:45:30 am
Facility:
IPEC ES - 401 Sys/Evol #/Name 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 073 Process Radiation Monitoring 076 Service Water 076 Service Water 078 Instrument Air I 03 Containment Kl A Category Totals:
08/16/2018 11 :45:35 am Kl X
X 3
PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 K2 K3 K4 KS K6 Al A2 A3 A4 X
X X
X X
X
- 2.
3 3
i 3
3 2
2 3
Printed:
08/16/2018 Form ES-401-2 G KA Topic Imp.
Points K 1.03 - Battery charger and 2.9 I
battery K 1.02 - ED/G cooling water 3.1 I
system A4.0 I - Effluent release 3.9 I
A2.02 - Detector failure 2.7 I
A 1.02 - Reactor and turbine 2.6*
I building closed cooling water temperatures K3.07 - ESF loads 3.7 I
A4.0 I - Pressure gauges 3.1 I
A2.03 - Phase A and B 3.5 I
isolation 2
Group Point Total:
28 2
PWR RO Examination Outline Printed:
08/16/2018 Facility:
IPEC ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 00 I Control Rod Drive X
K4.07 - Rod stops 3.7 I
011 Pressurizer Level Control X
K6.03 - Relationship 2.9 I
between PZR level and PZR heater control circuit 017 In-core Temperature Monitor X
Al.OJ-Core exit 3.7 I
temperature 029 Containment Purge X
A4.04 - Containment 3.5 I
evacuation signal 033 Spent Fuel Pool Cooling X
Kl.05 - RWST 2.7*
I 035 Steam Generator X
K5.03 - Shrink and swell 2.8 I
concept 041 Steam Dump/Turbine Bypass X
K2.02 - ICS inverter 2.8 I
Control breakers 045 Main Turbine Generator X
K3.01-Remainder of the 2.9 I
plant 055 Condenser Air Removal X
A3.03 - Automatic diversion 2.5*
I of CARS exhaust 056 Condensate X
A2.04 - Loss of condensate 2.6 I
pumps Kl A Category Totals:
1 1
I 1
1 1
1 1
1 1
0 Group Point Total:
10 08/16/2018 11:45:41 am
Facility:
IPEC Generic Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 08/16/2018 11 :45:46 am Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline KA Topic 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.
2.1.27 Knowledge of system purpose and/or function.
Category Total:
2.2.35 Ability to determine Technical Specification Mode of Operation.
2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.
Category Total:
2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Category Total:
2.4.28 Knowledge of procedures relating to a security event (non-safeguards information).
2.4.42 Knowledge of emergency response facilities.
2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Category Total:
Generic Total:
Printed: 08/16/2018 Form ES-401-3 2.5 1
3.9 I
2 3.6 1
3.5 I
2 3.5 I
3.4 1
2.9 I
3 3.2 I
2.6 1
4.6 1
3 to
ES-401 Record of Rejected K/ As Form ES-401-4 Tier/
Randomly Reason for Rejection Group Selected K/ A RO 1/1 009 2.2.12 Knowledge of surveillance testing NA to SBLOCA. Replaced with 000009 2.1.07 RO 2/1 022 K1.04 Chilled water is not used for Containment Cooling. Replaced with 022000 K1.01 RO 2/1 076 K3.02 Oversample topic with 076000A 1.02. Replaced with 076000 K3.07 RO 2/1 103 A2.04 Oversample topic with 029000 A4.04. Replaced with 103000 A2.03 RO 2/1 004 K5.40 IPEC does not use this method to draw a bubble in the PRT.
Replaced with 004000 K5.09 RO 2/2 028 KS.04 IPEC Unit 2 has passive Hydrogen Recombiners. There are no procedure actions associated with Hydrogen Recombiners. Replaced with 035000 KS.03 SRO 001 AA2.02 Cannot write an SRO question; the procedure is too simple (place rods in manual or trip the reactor). Replaced with OOWE02 AA2.02 SRO 2.3.14 Oversample KA. Exact same KA is on RO Tier 3 outline.
Replaced with 2.3.11.