ML17047A599

From kanterella
Revision as of 04:06, 28 January 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Draft - Outlines (Folder 2) (Facility Letter Dtd - 07/18/2016)
ML17047A599
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 07/18/2016
From: Lizzo N S
Entergy Nuclear Indian Point 2
To: Bill Dean
Operations Branch I
Shared Package
ML16076A436 List:
References
U01926
Download: ML17047A599 (31)
v • d • e


Text

NL-16-080 July 18, 2016 Mr. William Dean 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. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-2611 Nicholas Lizzo 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 October 31, 2016, Entergy Nuclear Operations, Inc. (Entergy) is providing the enclosed Reactor Operator and Senior Reactor Operator Written Examination Outlines to Mr. Joseph D'Antonio 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 10. 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. Javier Herrera, Superintendent, ILO Operations Training at (914) 254-2937, Mr. Brian Sullivan, Superintendent, LRQ Operations Training, at (914) 254-2942, Mr. Charles Kocsis, Senior Staff Instructor Examination author at (914) 254-2065, or Mr. Tim Jenkins, Senior Instructor Examination author at (914) 254-2995.

Sincerely, Signed p

Enclosures:

  • Certification of systematic and random selection Docket No. 50-247 NL-16-080 Page 2 of 2
  • NUREG-1021, Rev. 10, Form ES-401-4, "Record of Rejected K/As" -RO/SRO 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 2100 Renaissance Blvd Suite 100 King of Prussia, Pennsylvania 19406-2713 Mr. Joseph D'Antonio 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. Box59 Buchanan, N.Y. 10511-0059 w/o Enclosures w/o Enclosures with Enclosures w/o Enclosures ES-401 PWR Examination Outline Form ES-401-2 Facility:

IPEC Unit 2 Date of Exam October 31 , 2016 Tier 1. Emergency

& Abnormal Plant Evolutions

2. Plant Systems Group K 1 K 2 K 3 1 0 0 0 2 0 0 0 Tier Totals 0 0 0 1 0 0 0 2 0 0 0 Tier Totals O O 0 RO KIA Cate::iorv Points K 4 K 5 N/A 0 0 0 0 0 0 K A 6 1 A A A 2 3 4 G* 0 0 0 0 0 0 0 N/A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SRO-Only Points A2 G* Total Total 0 3 3 6 0 2 2 4 0 5 5 10 0 3 2 5 0 o I 2 3 0 5 3 8 3. Generic Knowledge and Abilities Categories 0 2 3 0 0 4 0 7 0 Note: 1. 2. 3. 4. 5. 6. 7. 8. 9. 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 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 KIA from another Tier 3 Category).

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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

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.

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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

The generic (G) K/As 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 0.1.b of ES-401 for the applicable K/As. 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 a category 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. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, I Rs, and point totals(#)

on Form ES-401-3.

Limit SRO selections to K/As that are linked to 10 CFR 55.43. G* Generic K/As PWR SRO Examination Outline Printed: 07/25/2016 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions

-Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip -Stabilization

-x EA2.06 -Occurrence of a reactor trip 4.5 I Recovery I 1 000015/000017 RCP Malfunctions I 4 x 2.1.45 -Ability to identify and interpret 4.3 1 diverse indications to validate the response of another indication.

000040 Steam Line Rupture -Excessive x 2.4.29-Knowledge of the emergency 4.4 1 Heat Transfer I 4 plan. 000058 Loss of DC Power I 6 x AA2.01 -That a loss of de power has 4.1 I occurred; verification that substitute power sources have come on line 000077 Generator Voltage and Electric Grid x 2.2.25 -Knowledge of the bases in 4.2 1 Disturbances I 6 Technical Specifications for limiting conditions for operations and safety limits. W/E05 Inadequate Heat Transfer -Loss of x EA2.2 -Adherence to appropriate 4.3 1 Secondary Heat Sink I 4 procedures and operation within the limitations in the facility's license and amendments KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6 07/25/2016 2:19:38 pm PWR SRO Examination Outline Printed: 07/25/2016 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions

-Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000024 Emergency Boration I 1 x 2.2.36 -Ability to analyze the effect of 4.2 I maintenance activities, such as degraded power sources, on the status oflimiting conditions for operations.

000032 Loss of Source Range NI I 7 x AA2.0 I -Normal/abnormal power 2.9 1 supply operation 000033 Loss of Intermediate Range NI I 7 x 2.4.23 -Knowledge of the bases for 4.4 1 prioritizing emergency procedure implementation during emergency operations.

000076 High Reactor Coolant Activity I 9 x AA2.06-Response of PZR LCS to 2.5 I changes in the letdown flow rate KIA Category Totals: 0 0 0 0 2 z Group Point Total: 4 07/25/2016 2:19:43 pm PWR SRO Examination Outline Printed: 0712512016 Facility:

IPEC ES-401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 006 Emergency Core Cooling x A2.08 -Effect of electric 3.3 1 power loss on valve position 012 Reactor Protection x A2.0 I -Faulty bistable 3.6 I operation 013 Engineered Safety Features x 2.3.15 -Knowledge of 3.1 I Actuation radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. 061 Auxiliary/Emergency x A2.08 -Flow rates expected 2.9* I Feed water from various combinations of AFW pump discharge valves 076 Service Water x 2.2.22 -Knowledge of 4.7 I limiting conditions for operations and safety limits. Kl A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 07/25/2016 2:19:48 pm PWR SRO Examination Outline Printed: 07/25/2016 Facility:

IPEC ES-401 Plant Systems -Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 034 Fuel Handling Equipment x A2.03 -Mispositioned fuel 4.0 1 element 056 Condensate x 2.1.45 -Ability to identify 4.3 1 and interpret diverse indications to validate the response of another indication.

071 Waste Gas Disposal x A2.03 -Rupture disk 3.3* 1 failures KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 l Group Point Total: 3 07/25/2016 2:19:53 pm Facility:

IPEC Generic Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 07/25/2016 2:19:58 pm Generic Knowledge and Abilities Outline (Tier 3) PWR SRO Examination Outline Printed: 07/25/2016 Form ES-401-3 KA Topic 2.1.5 Ability to use procedures related to shift staffing, 3.9 l such as minimum crew complement, overtime limitations, etc. 2.1.14 Knowledge of criteria or conditions that require 3.1 1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. Category Total: 2 2.2.17 Knowledge of the process for managing 3.8 l maintenance activities during power operations, such as risk assessments, work prioritization, and coordination woth the transmission system operator.

2.2.40 Ability to apply Technical Specifications for a 4.7 1 system. Category Total: 2 2.3.11 Ability to control radiation releases.

4.3 l 2.3.14 Knowledge of radiation or contamination hazards 3.8 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 2.4.6 Knowledge of EOP mitigation strategies.

4.7 1 Category Total: 1 Generic Total: 7 Description of program used to generate IPEC Unit 2 October 2016 Written Exam K/As Generated the RO and SRO sample plan using the "NKEG" Database Program, version 1.1, developed by Westinghouse Electric Company. This program will automatically produce a Random Sample Plan based on NUREG 1122, Rev. 2, Supplement 1 K/As. K/As were suppressed prior to the outline generation process as provided for in the examiner standard, the list of suppressed K/As is provided as required by the examiners standard.

Inappropriate and inapplicable K/As were discarded during the outline development process and are included in the record of rejected K/As. The replacement K/As were replaced using the random sample function of the NKEG database program.

ES-401 PWR Examination Outline Form ES-401-2 Facility:

IPEC Unit 2 Date of Exam October 31, 2016 RO KIA Cate:iorv 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 0 0 0 Emergency

& 2 2 Abnormal 2 1 N/A 1 2 N/A 1 9 0 0 0 Plant Evolutions Tier Totals 5 5 4 4 5 4 27 0 0 0 1 3 2 3 3 3 2 2 3 2 2 3 28 0 0 0 2. Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 0 0 0 0 Systems Tier Totals 4 3 4 4 4 3 3 4 2 3 4 38 0 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 0 Categories 2 3 3 2 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 K/A category shall not be less than two). {One Tier 3 Radiation Control K/A is allowed if the KIA 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 with justification; 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) K/As 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 K/As. 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 a category 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 KIA numbers, descriptions, I Rs, and point totals{#)

on Form ES-401-3.

Limit SRO selections to Kl As that are linked to 10 CFR 55.43. G* Generic K/As PWR RO Examination Outline Printed: 0712512016 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions

-Tier 1 I Group 1 Form ES-401-2 EIAPE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident I x 2.4.21 -Knowledge of the parameters 4.0 l 3 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, etc. 000009 Small Break LOCA I 3 x EAl.11 -AFWIMFW 4.1 l 000011 Large Break LOCA I 3 x EK3.08 -Flowpath for sump 3.9 l recirculation 0000151000017 RCP Malfunctions I 4 x AK3.07 -Ensuring that SIG levels are 4.1 1 controlled properly for natural circulation enhancement 000022 Loss of Rx Coolant Makeup I 2 x AA 1.08 -VCT level 3.4 1 000025 Loss of RHR System I 4 x AK 1.0 l -Loss of RHRS during all 3.9 1 modes of operation 000026 Loss of Component Cooling Water I x 2.4.4 -Ability to recognize abnormal 4.5 1 8 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

000027 Pressurizer Pressure Control System x AK2.03 -Controllers and positioners 2.6 l Malfunction I 3 000029 A TWS I l x EAI.15 -AFW System 4.1 l 000038 Steam Gen. Tube Rupture I 3 x 2.4.45 -Ability to prioritize and 4.1 l interpret the significance of each annunciator or alarm. 000054 Loss of Main Feedwater I 4 x AK 1.02 -Effects of feedwater 3.6 l introduction on dry SIG 000057 Loss of Vital AC Inst. Bus I 6 x AA2.03 -RPS panel alarm annunciators 3.7 l and trip indicators 000058 Loss of DC Power I 6 x AA2.0 l -That a loss of de power has 3.7 l occurred; verification that substitute power sources have come on line 000065 Loss of Instrument Air I 8 x AK3.04 -Cross-over to backup air 3.0 l supplies 000077 Generator Voltage and Electric Grid x AA2.03 -Generator current outside the 3.5 l Disturbances I 6 capability curve 07/25/2016 6:29:07 am PWR RO Examination Outline Printed: 0712512016 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions

-Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points W/E04 LOCA Outside Containment I 3 x EK2.2 -Facility's heat removal systems, 3.8 1 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 W/El l Loss of Emergency Coolant Recirc. I x EK2. l -Components, and functions of 3.6 l 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/El2 -Steam Line Rupture -Excessive x EK 1.3 -Annunciators and conditions 3.4 1 Heat Transfer I 4 indicating signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 07/25/2016 6:29:07 am 2 PWR RO Examination Outline Printed: 07/25/2016 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions

-Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000005 Inoperable/Stuck Control Rod I 1 x AK3.0l -Boration and emergency 4.0 I boration in the event of a stuck rod during trip or normal evolutions 000051 Loss of Condenser Vacuum I 4 x AA2.02 -Conditions requiring reactor 3.9 1 and/or turbine trip 000061 ARM System Alarms I 7 x AK 1.0 I -Detector limitations 2.5* 1 000069 Loss of CTMT Integrity I 5 x AK2.03 -Personnel access hatch and 2.8* I emergency access hatch W/E02 SI Termination I 3 x EA2.2 -Adherence to appropriate 3.5 1 procedures and operation within the limitations in the facility's license and amendments W /E03 LOCA Cooldown -Depress. I 4 x EK2.2 -Facility's heat removal systems, 3.7 I 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 W/E07 Inad. Core Cooling I 4 x EA 1.2 -Operating behavior 3.2 I characteristics of the facility W /E 15 Containment Flooding I 5 x 2.4.23 -Knowledge of the bases for 3.4 I prioritizing emergency procedure implementation during emergency operations.

W /E 16 High Containment Radiation I 9 x EK 1.2 -Normal, abnormal and 2.7 I emergency operating procedures associated with High Containment Radiation KIA Category Totals: 2 2 1 1 2 1 Group Point Total: 9 07/25/2016 6:29:12 am PWR RO Examination Outline Printed: 07!2S/2016 Facility:

IPEC ES-401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump x K2.0l -RCPS 3.1 l 004 Chemical and Volume Control x KS.19 -Concept of SOM 3.S l 004 Chemical and Volume Control x KS.3S -Heat exchanger 2.S 1 principles and the effects of flow, temperature and other parameters OOS Residual Heat Removal x K4.01 -Overpressure 3.0 l mitigation system 006 Emergency Core Cooling x 2. l .4S -Ability to identify 4.3 1 and interpret diverse indications to validate the response of another indication.

006 Emergency Core Cooling x K6.03 -Safety Injection 3.6 1 Pumps 007 Pressurizer Relief/Quench x K4.01 -Quench tank 2.6 1 Tank cooling 008 Component Cooling Water x 2.1.43 -Ability to use 4.1 1 procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. 008 Component Cooling Water x A2.02 -High/low surge tank 3.2 l level 010 Pressurizer Pressure Control x K2.02 -Controller for PZR 2.S l spray valve 012 Reactor Protection x K3.03 -SOS 3.1

  • l 013 Engineered Safety Features x K6.01 -Sensors and 2.7* 1 Actuation detectors 022 Containment Cooling x Kl.01-SWS/cooling 3.S 1 system 022 Containment Cooling x A4.03 -Dampers in the CCS 3.2* l 026 Containment Spray x K3.02 -Recirculation spray 4.2* l system 039 Main and Reheat Steam x KS.OS -Bases for RCS 2.7 1 cooldown limits OS9 Main Feedwater x A 1.03 -Power level 2.7* l restrictions for operation of MFW pumps and valves OS9 Main Feedwater x A3.06 -Feedwater isolation 3.2* I 061 Auxiliary/Emergency x K3.02 -SIG 4.2 I Feedwater 062 AC Electrical Distribution x Kl .03 -DC distribution 3.S I 063 DC Electrical Distribution x A2.01 -Grounds 2.S I 064 Emergency Diesel Generator x A2.06 -Operating unloaded, 2.9 I 07/25/2016 6:29:33 am PWR RO Examination Outline Printed: 07/25/2016 Facility:

lPEC ES-401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points lightly loaded, and highly loaded time limit 064 Emergency Diesel Generator x Kl.05 -Starting air system 3.4 l 073 Process Radiation Monitoring x K4.0l -Release termination 4.0 1 when radiation exceeds setpoint 076 Service Water x A l.02 -Reactor and turbine 2.6* 1 building closed cooling water temperatures 076 Service Water x A4.02 -SWS valves 2.6 1 078 Instrument Air x A3.01 -Air pressure 3.1 1 103 Containment x 2.3.5 -Ability to use 2.9 1 radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc. KIA Category Totals: 3 2 3 3 3 2 2 3 2 2 3 Group Point Total: 28 07/25/2016 6:29:33 am 2 PWR RO Examination Outline Printed: 0712512016 Facility:

IPEC ES-401 Plant Systems -Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 K5 K6 Al Al A3 A4 G KA Topic Imp. Points 015 Nuclear Instrumentation x Kl.03 -CRDS 3.1

  • 1 027 Containment Iodine Removal x K2.0l -Fans 3.1
  • l 029 Containment Purge x A4.0 l -Containment purge 2.5 l flow rate 033 Spent Fuel Pool Cooling x A 1.0 l -Spent fuel pool 2.7 l water level 035 Steam Generator x K6.0l -MSIVs 3.2 1 041 Steam Dump/Turbine Bypass x A2.03 -Loss of IAS 2.8 l Control 045 Main Turbine Generator x K3.0l -Remainder of the 2.9 1 plant 055 Condenser Air Removal x A3 .03 -Automatic diversion 2.5* 1 of CARS exhaust 072 Area Radiation Monitoring x 2.1.15 -Knowledge of 2.7 l administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc. 075 Circulating Water x K4.0 l -Heat sink 2.5 1 KIA Category Totals: 1 1 1 1 0 1 1 l 1 1 1 Group Point Total: 10 07/25/2016 6:29:38 am Facility:

IPEC Generic Catei:ory Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 07/25/2016 6:36:16 am Generic Knowledge and Abilities Outline (Tier 3) PWR RO Examination Outline Printed: 0712512016 Form ES-401-3 KA Topic 2.1.l Knowledge of conduct of operations 3.8 1 requirements.

2.1.45 Ability to identify and interpret diverse 4.3 1 indications to validate the response of another indication.

,, Category Total: 2 2.2.25 Knowledge of the bases in Technical 3.2 I Specifications for limiting conditions for operations and safety limits. 2.2.36 Ability to analyze the effect of maintenance 3.1 1 activities, such as degraded power sources, on the status of limiting conditions for operations.

2.2.37 Ability to determine operability and/or 3.6 1 availability of safety related equipment.

Category Total: 3 2.3.5 Ability to use radiation monitoring systems, such 2.9 1 as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc. 2.3.13 Knowledge of radiological safety procedures 3.4 l pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 2.3.15 Knowledge of radiation monitoring systems, such 2.9 I as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. Category Total: 3 2.4.27 Knowledge of "fire in the plant" procedure.

3.4 I 2.4.35 Knowledge of local auxiliary operator tasks 3.8 1 during an emergency and the resultant operational effects. Category Total: 2 Generic Total: 10 ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Group RO Loss of Off-Site Power KA rejected because equipment does not 000056AA2.04 1 I 1 Service Water Pump Ammeter and Flow meter exist in Indian Point Control Room Pressurizer Level Malfunction RO Change in PZR level with power change, even KA Rejected because TAVG is not constant 000028AK3.

04 1 I 2 though RCS Tavg constant, due to loop size with power change at Indian Point differences RO DC Electrical Distribution KA Rejected because this ability is evaluated 0630002.1.21 2 I 1 Ability to verify the controlled procedure copy during JPM or Simulator Scenarios RO Reactor Coolant Pump KA Rejected because too much overlap with 03000A304 2 I 1 RCS Flow question 28 -003000K201 RO Chemical and Volume Control System KA Rejected because no such interlock exists 004000K413 Interlock between letdown isolation valve and flow 2 I 1 control valve at IPEC I ES-401 Record of Rejected Kl As Form ES-401-4 RO Service Water System KA Rejected because there is no interface 2 I 1 076000K120 between the service water system and the AFW AFW system at IPEC. RO Reactor Coolant 212 002000A401 RCS Leakage calculation program using the KA Rejected because this ability is evaluated computer during JPM or Simulator Scenarios RO Fore Protection KA Rejected because there is no interface 086000K101 between Fire Protection and Service Water at 212 High Pressure Service Water IPEC Loss of RHR SRO Ability to use procedures related to shift staffing KA rejected because Generic KA statement is 0000252.1.5 1 I 1 such as minimum crew compliment, overtime not applicable to APE Loss of RHR limitations, etc. 2 ES-401 Record of Rejected K/As Form ES-401-4 SRO Continuous Rod Withdrawal KA rejected because Generic KA statement is 0000012.2.

7 Knowledge of process for conducting special or not applicable to APE Continuous Rod 1 I 2 infrequent tests Withdrawal SRO Main Feedwater 0590002.2.6 Knowledge of the process for making changes to KA rejected because this KA is best 2 I 1 procedures evaluated using a JPM. 3 Appendix D Scenario Outline Form ES-D-1 Facility:

Indian Point 2 Scenario No.: _1_ Op-Test No.: _1_ Examiners:

Operators:

Initial Conditions:

4% power. No equipment out of service for current conditions.

Startup is in progress.

Turnover:

Currently at Step 4.33 of POP-1.3. The FSS is prepared to perform turbine latch and reset per SOP-26.4.

Raise power to 6-8% in pre12arations for turbine startu12.

Event Malf. No. Event Type* Event No. Description N 1 CRS/BOP Raise power to 6-8% -R ATC 2 XMT-SGN046A I PT-449C fails high (TS) ALL 3 MOC-CVC006 c Charging Pump Trip CRS/ATC 4 PLP-SIS006 c RWST leak (TS) CRS 5 RLY-PPL487 c Inadvertent Safety Injection CRS MOC-RHR003 MOC-RHR004 c Failure of 21 and 22 RHR Pumps and 21 and 25 FCUs 6 MOC-CNM008 MOC-CNM012 BOP to start on SI signal 7 MAL-RCS006B M Small Break Loss of Coolant Accident ALL 8 --Loss of Recirculation Capability

  • (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Scenario 1 Summary The evaluation begins with the plant at 4% power with no equipment out of service. After taking the watch, the team will proceed to raise power as directed.

This will require withdrawing controls rods and/or diluting the RCS which will provide a reactivity event for the ATC operator.

SG levels will be controlled in manual using the feed regulation bypass valves which will provide a normal operation for the BOP operator.

The CRS will direct the evolution and get credit for a normal operation.

After sufficient power increase, 23 SG Pressure Transmitter PT-449C will fail high. This will cause the Atmospheric Dump Valve for 23 SG to open requiring the controller to be placed in manual by the ATC. The CRS will enter AOP-INST-1.

Bistables for the failed channel will be tripped by the BOP. This will count as an instrument failure for all operators and a tech spec call for the CRS. After bistables has been tripped for the PT-449C failure, the running charging pump will trip. The CRS will enter AOP-CVCS-1.

The ATC will start another charging pump to restore charging.

The CRS and ATC will get credit for a component failure. Next, a fork truck crashes into the RWST resulting in a large leak eight feet from the bottom of the tank. It will take 40 minutes for the tank to drain from 36' to 8'. The team will perform actions of the ARP for RWST Level Low alarm and the CRS will determine that a TS required shutdown must commence.

An inadvertent train A SI will occur when RWST level reaches -28 feet. The CRS will direct entry into E-0, Reactor Trip or Safety Injection and be credited with a component failure. 21 and 22 RHR pumps and 21 and 25 FCU will fail to auto start. The BOP will have to start these components manually.

One minute after SI is reset, a small break LOCA will occur. (Note, if team has not progressed to reset SI when RWST reaches 11 feet, the LOCA will be inserted then) This is the major event for the team. The team will determine that the RCS is not intact and transition to E-1, Loss of Reactor or Secondary Coolant. When RWST level lowers to 9.24 feet a transition to ES-1.3, Transfer to Cold Leg Recirculation will occur. The containment sump level will not support recirculation pump operation requiring a transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

The team will makeup to the RWST (may be done early from ARP response), reduce operating ECCS equipment taking suction from the RWST to one train, and initiate RCS cooldown.

The scenario will be terminated when makeup to the RWST has been initiated, containment spray has been stopped and SI pumps have been reduced to one train. Procedure flow path: POP-1.3, AOP-INST-1, AOP-CVCS-1, ARP-SBF-1, E-0, ES-1.1, E-1, ECA-1.1 Critical Tasks: 1. Stop ECCS pumps with suction aligned to the RWST before RWST decreases to < 1.5 ft. (WOG ECA-1.1-A)

2. Make up to the RWST and minimize outflow before the end of the scenario. (WOG ECA-1.1-B)

Appendix D Scenario Outline Form ES-D-1 Facility:

Indian Point 2 Scenario No.: Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

100% power. 23 SI Pump and 23 CCW Pump are OOS for preventive maintenance.

Turnover:

Team has been directed to reduce power to 90% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to support turbine valve testing. Event Malf. Event Event No. No. Type* Description 1 N Down power CRS/B OP RATC 2 XMT-I 24 SG pressure transmitter fails high. TS SGN04 ALL 6A 3 MOT-c 22 CCW Pump trips and 21fails to auto start. TS ccwoo CRS 2B BOP MOC-TS ccwoo CRS 1/3 4 FLX-c CCW leak on running charging pump cooling line. TRM CCW01 CRS 4 ATC 5 BKR-M Steam break with MSIVs failing to close and ATWS PPL003 ALL /4 AOV-SGNOO 1/2/3/4A 6 MOC-c 21 and 22 SI Pumps fail to start on SI SIS001/ BOP 2/3 * (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor SESSION OUTLINE: The evaluation begins with the plant at 100% power steady state operation.

23 SI Pump and 23 CCW Pump are out of service for maintenance.

After taking the watch, the team will begin lowering power as directed in turnover.

The ATC will borate for a reactivity manipulation.

The BOP will lower load with the governor for a normal operation.

The CRS will be credited with a normal operation for supervising the evolution.

During the downpower, 24 SG pressure transmitter PT-449C will fail high. This will cause the ADV for 24 SG to open. The ATC will close the valve in manual. Bistables for this instrument will need to be tripped to satisfy tech specs. After sufficient load decrease, 22 CCW pump trips and the standby CCW pump does not auto start as expected.

The team will respond by manually starting 21 CCW pump. When a CCW pump is running, a 25 gpm leak will occur on 22 Charging Pump CCW cooling line. The team will start another charging pump and take actions in accordance with AOP-CCW-1, Loss of Component Cooling and isolate the leak by closing local valves in the Charging Pump cell. The CCW pump trip is a Tech Spec entry. The charging pump operability is a TRM entry. After completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the Turbine Building.

The team will attempt to manually trip the plant, close MSIVs, and perform actions of E-0, Reactor Trip or Safety Injection.

The reactor will not trip from the Control Room and the team will respond per FR-S.1, Response to Nuclear Power Generation I A TWS and will S/D the reactor by manually inserting control rods and initiating Emergency Boration.

The reactor trip breakers will be locally opened and the team will transition to E-0, Reactor Trip or Safety Injection.

Following SI actuation, 21 and 22 SI pumps do not auto start. The MSIVs will fail to auto close and cannot be closed from the control room. The team will take actions per ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

When at least one MSIV is closed locally, the team will transition to E-2, Faulted Steam Generator Isolation.

The team will complete E-2 and transition to E-1, Loss of Reactor or Secondary Coolant. Procedure flow path: POP-2.1, AOP-INST-1, AOP-CCW-1, AOP-UC-1, E-0, FR-S.1, E-0, E-2, ECA-2.1, E-2, E-1. Critical Tasks: 1. Insert negative reactivity into the core by at least 1 of the following methods before Step 4 of FR-S.1 is complete:

  • De-energize the Rod Drive MG sets
  • Manually insert the rods
  • Establish Emergency Boration. (WOG FR-S.1-C)
2. Control AFW flow to not less than 85 gpm per SG to minimize RCS cooldown rate before an Integrity orange path develops. (WOG ECA-2.1-A)
3. Isolate the faulted SG before transition out of E-2. (WOG E-2-A)

Facility:

Indian Point 2 Scenario No.: 4 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 100% power IC Load Simulator Schedule-Scenario4 The Plant is at 100% power. 23 EOG is OOS. Turnover:

Perform power reduction to 60% to remove 22 MBFP from service. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) N (CRS) Power Reduction N (BOP) 2 XMT-C (ALL) VCT Level Failure CVC019A 3 XMT-l(ALL) CFW014 24 Feedwater Flow failure. TS(CRS) A 4 XMT-I (ALL) RCS028A Pressurizer Pressure failure. TS(CRS) 5 FLX-Flooding in 480V room. FPS008 6 MAL-C(ALL) EPS007D TS(CRS) Loss of 480V Bus 6A. 7 XMT-M(ALL) RCS030A Pressurizer Pressure failing causing trip. 8 AOV-C(ALL) RCS003A PORV failure 9 MAL-EPSOO?C/ M(ALL) Loss of 480V buses due to flooding.

B/A * (N)ormal, ( R )eactivity, (l)nstrument (C)omponent, (M)ajor SESSION OUTLINE: The evaluation begins with the plant at 100% power steady state operation.

The following equipment is out of service:

  • 23 EOG has been out of service for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for malfunctioning governor.

Maintenance is complete and 2-PT-M021C is in progress.

If the diesel passes, it will be declared operable.

Expected completion time in 90 minutes. After taking the watch, the team will reduce power as directed to allow for securing 22 MBFP. After sufficient load reduction, VCT level instrument will fail low causing charging pump suction to swap to RWST. The team will restore normal suction using AOP-CVCS-1.

Following the restoration of charging pump suction, 24 SG feedflow controlling channel will fail low requiring the team to swap to the other channel. However, the channel will not swap requiring the MFRV to be placed in manual. The affected instrument will be removed from service per AOP-INST-1 and TS will be reviewed.

Following removal of the feedflow channel, controlling Pressurizer Pressure instrument fails high. Team performs actions of AOP-INST-1 and swaps pressure control to an unaffected channel. TS will be reviewed.

After PRZR pressure control has been returned to automatic, the fire main adjacent to the 480V switchgear room ruptures resulting in flooding.

The team should implement AOP-FLOOD -1 which provides directions for identifying and isolating the source of flooding.

Flooding in the room will continue and the door to the 480V room fails, causing floodwater to enter the 480V room and 480V Bus 6A to fault. The team will then implement AOP-480V-1, Loss of Normal Power to Any Safeguards 480V Bus. Then, Pressurizer Pressure Channel 3 fails high resulting in a reactor trip and the associated PORV Block valve opens. Following reactor trip, flooding in the 480V Room will result in sequential loss of all remaining 480V busses. The team will transition from E-0, Reactor Trip or Safety Injection to ECA-0.0, Loss of All AC Power. PORV 456 will fail open but can be manually closed by placing its control switch to close. AFW to the S/Gs will be supplied by 22 ABFP. The team will progress through ECA-0.0 taking actions to isolate RCP seals and depressurize the S/Gs. The scenario will end when the team has demonstrated the ability to depressurize S/Gs. Procedure flow path: AOP-CVCS-1, AOP-INST-1, AOP-FLOOD-1, AOP-480V-1, E-0, ECA-0.0 CRITICAL TASKS: ECA-0.0 --A Manually close the open PZR PORV before completing Step 3 of ECA-0.0. ECA-0.0 --8 Establish at least 400 gpm AFW flow to the SIGs before SIG WR level decreases to below 14% ECA-0.0 --G If all of the following conditions are met, depressurize intact SIGs at <100°Flhr:

  • Any intact SIG NR level >10%
  • SIG pressure does not decrease below 110 psig
  • RCS cold leg temperature

>295°F

  • SUR 0 or negative ECA-0.0 --H Isolate RCP seal injection before starting a charging pump.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

IPEC Date of Examination:

10/31/2016 Examination Level: RO D SRO 0 Operating Test Number: Administrative Topic (see Note) Type Describe activity to be performed Code* Update Electrical Power Availability for Shutdown Safety Assessment Conduct of Operations MR 2.1.18 -Ability to make accurate, clear, and concise logs, records, status boards, and reports. SR0-3.8 Review Vapor Containment Daily Leakrate Conduct of Operations MR 2-PT-D-0012.1.25 Conduct of Operations

-Ability to interpret reference materials such as graphs, curves, tables etc. SR0-4.2 Reportablity for Safety Limit Violation Equipment Control NR 2.2.22 Equipment Control -Knowledge of limiting conditions for operations and safety limits. SR0-4.7 Review I Authorize a Liquid Waste Release Radiation Control M,R 2.3.6 Ability to approve release permits. SR0-3.8 Classify Event and Complete Form EP-1, Emergency Plan M RorS Part 1 2.4.41 -Knowledge of the emergency action level thresholds and classifications.

SRO -4.6 (45.11) 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 & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Date of Examination:

10/31/2016 Exam Level: RO D SRO-I SRO-U D Operating Test No.: Control Room Systems:*

8 for RO; 7 for SRO-I; 2 or 3 for SR0-1!. System I JPM Title Type Code* Safety Function a. Transfer to Hot Leg Recirc 000011A.1.11 (4.2/4.2)

A,EN,S 2 b. Initiate Bleed and Feed Cooling OOWE05A101 (4.1/4.0)

A,E,S 3 c. Reset Track and Hold 059000A.2.11 (3.0/3.3) s 4S d. Respond to #1 RCP Seal Failure 003000A2.01 (3.5/3.9)

S, E, 4P e. Deep Load Shed FSG-4 063000K.2.01 (2.9/3.1)

N, E, S, 6 f. Instrument Failure Steam Flow 035000K.4.01 (3.6/3.8)

A,S 7 g. Reset R-44 Alarm Setpoint 073000A.4.02 (3.7/3.7)

S,D 9 h. In-Plant Systems* (3 for RO); (3 for SRO-I}; (3 or 2 for SRO-U) i. Trip the Reactor Locally 000068A.1.14 ( 4.2/4.4) E, 1 j. Start a Battery Charger 063000A.4.01 (2.8/3.1)

D 6 k. Locally Operate Charging Without Instrument Air 000068A106 A, E, 8 (4.1/4.2)

  • 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; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO I SRO-I I SRO-U A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant <:1/<:1/<:1 (EN)gineered safety feature <:1 I <:1 I<: 1 (control room system) (L)ow-Power I Shutdown <:1/<:1/<:1 (N)ew or (M)odified from bank including 1 (A) <:2/<:2/<:1 (P)revious 2 exams s 3 I s 3 Is 2 (randomly selected) (R)CA <:1/<:1/<:1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Date of Examination:

10/31/2016 Exam Level: RO 0 SRO-I D SRO-U D Operating Test No.: Control Room Systems:'

8 for RO; 7 for SRO-I; 2 or 3 for SRO-!,! System I JPM Title Type Code* Safety Function a. Transfer to Hot Leg Recirc 000011A.1.11 (4.2/4.2)

A, EN, S 2 b. Initiate Bleed and Feed Cooling OOWE05A101 (4.1/4.0)

A,E,S 3 c. Reset Track and Hold 059000A.2.11 (3.0/3.3) s 4S d. Respond to #1 RCP Seal Failure 003000A2.01 (3.5/3.9)

S, E, 4P e. Deep Load Shed FSG-4 063000K.2.01 (2.9/3.1)

N, E, S, 6 f. Instrument Failure Steam Flow 035000K.4.01 (3.6/3.8)

A,S 7 g. Reset R-44 Alarm Setpoint 073000A.4.02 (3.7/3.7)

S,D 9 h. Reset Phase A 103000A.3.01 (3.9/4.2)

A, E, S, 5 In-Plant Systems' (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Trip the Reactor Locally 000068A.1.14 (4.2/4.4)

E, 1 j. Start a Battery Charger 063000A.4.01 (2.8/3.1)

D 6 k. Locally Operate Charging Without Instrument Air 000068A 106 A, E, 8 (4.1/4.2)

  • 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; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO I SRO-I / SRO-U A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature 2: 1 I 2: 1 I 2: 1 (control room system) (L}ow-Power I Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 (A) 2:2/2:2/2:1 (P)revious 2 exams :5 3 I :5 3 I :5 2 (randomly selected) (R)CA 2:1/2:1/2:1 (S)imulator ES-301 Administrative Topics Outline Form ES-301-1 Facility:

IPEC Date of Examination:

10/31/2016 Examination Level: RO 0 SRO D Operating Test Number: Administrative Topic (see Note) Type Describe activity to be performed Code* Electrical Verification

-Offsite Power Sources Surveillance Conduct of Operations M,S 2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports. R0-3.6 Vapor Containment Daily Leakrate 2-PT-D-001 Conduct of Operations M,R 2.1.25 Conduct of Operations

-Ability to interpret reference materials such as graphs, curves, tables etc. R0-3.9 Prepare a Tagout Equipment Control M,R 2.2.13 Equipment Control -Knowledge of tagging and clearance procedures.

R0-4.1 Determine Radiological Conditions, RWP Requirements, and Potential Dose Radiation Control M,R 2.3.7 Radiological Controls -Ability to comply with radiation work permit requirements during normal and abnormal conditions.

R0-3.5 Emergency Plan N/A N/A 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 & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (:5 1; randomly selected)
Retrieved from "https://kanterella.com/w/index.php?title=ML17047A599&oldid=1230135"