Text

Salem - Draft Outlines (Folder 2)
	ML16081A334
Person / Time
Site:	Salem
Issue date:	09/07/2015
From:	; Public Service Enterprise Group
To:	Todd Fish; Operations Branch I
Shared Package
ML15135A303	List: ML15159B204; ML15342A448; ML16050A330; ML16050A331; ML16081A285; ML16081A304; ML16081A334; ML16081A353; ML16081A364; ML16081A397; ML16081A406; ML16145A208;
References
	TAC U01910
	Download: ML16081A334 (23)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facilit)l: Salem Printed: 09/07/2015 Date Of Exam: 12/21 /2015 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 1 2 2 2 l 2 2 0 9 0 0 0

& N/A N/A Abnormal Tier Plant Totals 5 5 4 5 5 3 27 0 0 0 Evolutions 1 3 2 3 3 2 2 3 3 2 3 2 28 0 0 0 2.

Plant 2 l l l l l l l I 1 1 0 10 0 I 0 0 0 Systems Tier 0 0 0 4 3 4 4 3 3 4 4 3 4 2 38 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 0 Abilities Categories 3 3 2 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 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 0.1.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 KlAs 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 0.1.b of ES-401 for the applicable KlAs.

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.

09/07/2015 12:12:20 pm

PWR RO Examination Outline Printed: 09/0712015 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group l Form ES-401-2 E/APE #I Name I Safety Function Kt K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - x EK3.0l -Actions contained in EOP for 4.0 1 Recovery I 1 reactor trip 000008 Pressurizer Vapor Space Accident I x AK 1.02 - Change in leak rate with 3.1 1 3 change in pressure 000009 Small Break LOCA I 3 x EK2.03 - S/Gs 3.0 1 000022 Loss of Rx Coolant Makeup I 2 x AK3.02 - Actions contained in SOPs 3.5 1 and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging 000025 Loss of RHR System I 4 x AK2.01 - RHR heat exchangers 2.9 1 000027 Pressurizer Pressure Control System x 2.1.7 - Ability to evaluate plant 4.4 1 Malfunction I 3 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000029 A TWS I 1 x EKl.03 - Effects of boron on reactivity 3.6 1 000038 Steam Gen. Tube Rupture I 3 x 2.4.16- Knowledge ofEOP 3.5 1 implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

000054 Loss of Main Feedwater I 4 x AK 1.01 - MFW line break 4.1 1 depressurizes the S/G (similar to a steam line break) 000055 Station Blackout I 6 x EA2.01 - Existing valve positioning on 3.4 1 a loss of instrument air system 000057 Loss of Vital AC Inst. Bus I 6 x AAl.01 - Manual inverter swapping 3.7* 1 000058 Loss of DC Power I 6 x AA 1.01 - Cross-tie of the affected de 3.4* 1 bus with the alternate supply 000062 Loss of Nuclear Svc Water I 4 x AK3.02 - The automatic actions 3.6 1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000077 Generator Voltage and Electric Grid x AA2.01 - Operating point on the 3.5 1 Disturbances I 6 generator capability curve 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 09/07/2015 12:11 :52 pm

PWR RO Examination Outline Printed: 09/0712015 Facility: Salem 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/E05 Inadequate Heat Transfer - Loss of x 2.4.20 - Knowledge of operational 3.8 1 Secondary Heat Sink I 4 implications ofEOP warnings, cautions, and notes.

W/El 1 Loss of Emergency Coolant Recirc. I x EA 1.3 - Desired operating results 3.7 1 4 during abnormal and emergency situations W/El2 - Steam Line Rupture - Excessive x EA2.2 - Adherence to appropriate 3.4 1 Heat Transfer I 4 procedures and operation within the limitations in the facility's license and amendments KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 09/07/2015 12:11:52 pm 2

PWR RO Examination Outline Printed: 09/07/2015 Facility: Salem 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 000001 Continuous Rod Withdrawal I 1 x AK 1.05 - Effects of turbine-reactor 3.5 1 power mismatch on rod control 000028 Pressurizer Level Malfunction I 2 x AKl.01- PZR reference leak 2.8* 1 abnormalities 000037 Steam Generator Tube Leak I 3 x AA2.0l - Unusual readings of the 3.0 1 monitors; steps needed to verify readings 000067 Plant Fire On-site I 9 x AK3.02 - Steps called out in the site fire 2.5 1 protection plan, FPS manual, and fire zone manual 000074 Inad. Core Cooling I 4 x EK2.03 - AFW pump 4.0 1 000076 High Reactor Coolant Activity I 9 x AA2.03 - RCS radioactivity level meter 2.5 1 W/E03 LOCA Cooldown - Depress. I 4 x EA 1.3 - Desired operating results 3.7 1 during abnormal and emergency situations W/E13 Steam Generator Over-pressure I 4 x EK2.2 - Facility's heat removal systems, 3.0 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/El4 Loss ofCTMT Integrity I 5 x EA 1.1 - Components, and functions of 3.7 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features KIA Category Totals: 2 2 1 2 2 0 Group Point Total: 9 09/07/2015 12:11:57 pm

PWR RO Examination Outline Printed: 09/07/2015 Facility: Salem Plant Systems - Tier 2 I Group 1 Form ES-401-2 ES- 401 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump x A4.07 - RCP seal bypass 2.6* 1 003 Reactor Coolant Pump x Kl.01 - RCP lube oil 2.6 1 004 Chemical and Volume Control x K4.13- Interlock between 3.2* 1 letdown isolation valve and flow control valve 004 Chemical and Volume Control x K5.49 - Purpose and method 2.7 1 of hydrogen removal from RCS before opening system:

explosion hazard, nitrogen purge 005 Residual Heat Removal x K3.05 - ECCS 3.7* 1 006 Emergency Core Cooling x 2.2.42 - Ability to recognize 3.9 1 system parameters that are entry-level conditions for Technical Specifications.

007 Pressurizer Relief/Quench x Kl.QI - Containment system 2.9 I Tank 008 Component Cooling Water x A2.05 - Effect of loss of 3..)...,* 1 instrument and control air on the position of the CCW valves that are air operated 010 Pressurizer Pressure Contro 1 x A4.02 - PZR heaters 3.6 1 010 Pressurizer Pressure Control x K4.01 - Spray valve 2.7 1 warm-up 012 Reactor Protection x A4.01 - Manual trip button 4.5 1 012 Reactor Protection x K2.0l - RPS channels, 3.3 I components, and interconnections 013 Engineered Safety Features x Kl.12 - ED/G 4.1 I Actuation 022 Containment Cooling x A3.01 - Initiation of 4.1 I safeguards mode of operation 026 Containment Spray x K3.02 - Recirculation spray 4.2* I system 039 Main and Reheat Steam x A2.05 - Increasing steam 3.3 1 demand, its relationship to increases in reactor power 059 Main Feedwater x A 1.07 - Feed Pump speed, 2.5* 1 including normal control speed for ICS 061 Auxiliary/Emergency x K5.03 - Pump head effects 2.6 1 Feedwater when control valve is shut 061 Auxiliary/Emergency x K6.02 - Pumps 2.6 1 Feedwater 062 AC Electrical Distribution x K3.03 - DC system 3.7 1 062 AC Electrical Distribution x A 1.01 - Significance of DIG 3.4 1 09/07/2015 12:12:03 pm

PWR RO Examination Outline Printed: 09/0712015 Facility: Salem 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 load limits 063 DC Electrical Distribution x K4.01 - Manual/automatic 2.7 1 transfers of control 064 Emergency Diesel Generator x K6.08 - Fuel oil storage 3.2 1 tanks 073 Process Radiation Monitoring x A 1.01 - Radiation levels 3.2 1 076 Service Water x K2.01 - Service water 2.7* 1 078 Instrument Air x A3.01 - Air pressure 3.1 1 103 Containment x A2.03 - Phase A and B 3.5* 1 isolation 103 Containment x 2.2.40 - Ability to apply 3.4 1 Technical Specifications for a system.

KIA Category Totals: 3 2 3 3 2 2 3 3 2 3 2 Group Point Total: 28 09/07/2015 12:12:03 pm 2

PWR RO Examination Outline Printed: 09/0712015 Facility: Salem 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 001 Control Rod Drive x A3.02 - Rod height 3.7 1 002 Reactor Coolant x A 1.11 - Relative level 2.7 1 indications in the RWST, the refueling cavity, the PZR and the reactor vessel during preparation for refueling 011 Pressurizer Level Control x A4.04 - Transfer of PZR 3.2 I LCS from automatic to manual control 016 Non-nuclear Instrumentation x K5.0l- Separation of 2.7* 1 control and protection circuits 017 In-core Temperature Monitor x K4.02 - Sensing and 3.1 1 determination of location core hot spots 027 Containment Iodine Removal x K2.01 - Fans 3.1

1 028 Hydrogen Recombiner and x A2.01- Hydrogen 3.4* 1 Purge Control recombiner power setting, determined by using plant data book 033 Spent Fuel Pool Cooling x K3.03 - Spent fuel 3.0 1 temperature 035 Steam Generator x K6.03 - S/G level detector 2.6 1 086 Fire Protection x K 1.03 - AFW System 3.4* 1 Kl A Category Totals: 1 I 1 1 1 1 I I 1 1 0 Group Point Total: 10 09/07/2015 12:12:09 pm

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 09/07/2015 Facility: Salem Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.3 Knowledge of shift or short-term relief turnover 3.7 1 practices.

2.1.25 Ability to interpret reference materials, such as 3.9 1 graphs, curves, tables, etc.

2.1.36 Knowledge of procedures and limitations 3.0 1 involved in core alterations.

Category Total: 3 Equipment Control 2.2.3 (multi-unit license) Knowledge of the design, 3.8 1 procedural, and operational differences between units.

2.2.14 Knowledge of the process for controlling 3.9 1 equipment configuration or status.

2.2.23 Ability to track Technical Specification limiting 3.1 1 conditions for operations.

Category Total: 3 Radiation Control 2.3.12 Knowledge ofradiological safety principles 3.2 1 pertaining to licensed operator duties, such as 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 1 as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 2 Emergency Procedures/Plan 2.4.1 Knowledge of EOP entry conditions and 4.6 1 immediate action steps.

2.4.29 Knowledge of the emergency plan. 3.1 1 Category Total: 2 Generic Total: 10 09/07/2015 12:12:14 pm

ES-401 PWR Examination Outline Form ES-401-2 Facilit~c Salem Printed: 09/07/2015 Date Of Exam: 12/21/2015 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 Em erg enc, 2 0 0 0 N/A 0 0 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

Plant 2 0 0 0 0 0 0 0 0 0 0 0 0 0 I 2 1 3 Systems Tier 5 3 8 0 0 0 0 0 0 0 0 0 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 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 NRG 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 0.1.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 KlAs 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 0.1.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.

09/07/2015 12:09:48 pm

PWR SRO Examination Outline Printed: 09/07/2015 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 /Group l Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000022 Loss of Rx Coolant Makeup I 2 x 2.2.22 - Knowledge oflimiting 4.7 1 conditions for operations and safety limits.

000025 Loss of RHR System I 4 x 2.1.20 - Ability to interpret and execute 4.6 1 procedure steps.

000038 Steam Gen. Tube Rupture I 3 x EA2.17 - RCP restart criteria 4.4 1 000062 Loss of Nuclear Svc Water I 4 x 2.4.45 - Ability to prioritize and 4.3 1 interpret the significance of each annunciator or alarm.

W /E04 LOCA Outside Containment I 3 x EA2. l - Facility conditions and 4.3 1 selection of appropriate procedures during abnormal and emergency operations 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 09/07/2015 12:09:21 pm

PWR SRO Examination Outline Printed: 09/0712015 Facility: Salem 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 000003 Dropped Control Rod I 1 x 2.4.9 - Knowledge oflow 4.2 1 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

000068 Control Room Evac. I 8 x AA2.07 - PZR level 4.3 1 W/E06 Inad. Core Cooling I 4 x 2.4.23 - Knowledge of the bases for 4.4 1 prioritizing emergency procedure implementation during emergency operations.

W/ElO Natural Circ. I 4 x EA2.2 - Adherence to appropriate 3.9 I procedures and operation within the limitations in the facility's license and amendments Kl A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 09/07/2015 12:09:27 pm

PWR SRO Examination Outline Printed: 09/07/2015 Facility: Salem 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 008 Component Cooling Water x A2.02 - High/low surge tank 3.5 1 level 010 Pressurizer Pressure Control x A2.03 - PORV failures 4.2 1 022 Containment Cooling x 2.2.42 - Ability to recognize 4.6 1 system parameters that are entry-level conditions for Technical Specifications.

026 Containment Spray x A2.08 - Safe securing of 3.7 1 containment spray (when it can be done) 064 Emergency Diesel Generator x 2.1.20 - Ability to interpret 4.6 1 and execute procedure steps.

KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 09/07/2015 12:09:32 pm

PWR SRO Examination Outline Printed: 09/0712015 Facility: Salem 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 014 Rod Position Indication x A2.02 - Loss of power to the 3.6 1 RPIS 015 Nuclear Instrumentation x 2.1. 7 - Ability to evaluate 4.7 1 plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

075 Circulating Water x A2.02 - Loss of circulating 2.7 1 water pumps Kl A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 09/07/2015 12:09:38 pm

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 09/0712015 Facility: Salem Form ES-401-3 Generic Cate2ory KA Topic Conduct of Operations 2.1.41 Knowledge of the refueling process. 3.7 1 Category Total: 1 Equipment Control 2.2.1 Ability to perform pre-startup procedures for the 4.4 1 facility, including operating those controls associated with plant equipment that could affect reactivity.

2.2.38 Knowledge of conditions and limitations in the 4.5 1 facility license.

Category Total: 2 Radiation Control 2.3.11 Ability to control radiation releases. 4.3 1 2.3.14 Knowledge ofradiation or contamination hazards 3.8 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of all 4.0 I annunciators.

2.4.44 Knowledge of emergency plan protective action 4.4 I recommendations.

Category Total: 2 Generic Total: 7 09/07/2015 12:09:43 pm

ES-401 R d of Reiected K/As Salem 14-01 NRC E F ES-401-4 Tier/Group Randomly Reason for Rejection Selected KlA ROl/1 009 EK2.03 Sampled on CERT exam ROl/1 015 2.1.39 (ES-401, D.l.b)

ROl/1 026 2.1.41 (ES-401, D.l.b)

RO 111 027 2.1.36 (ES-401, D.1.b)

RO 111 027 2.4.16 (ES-401, D.1.b)

ROl/1 038 2.1.26 (ES-401, D.l.b)

RO 1/1 065 AA2.07 Salem does not have backup nitrogen supply to instrument air.

ROl/1 065 2.4.49 Loss of Instrument Air does not have any Immediate Actions.

ROl/1 056 AAl.15 Salem does not have Service Water Booster pumps RO 111 E05 2.1.38 (ES-401, D.1.b)

RO 112 005 2.1.21 (ES-401, D.1.b)

RO 1/2 061 2.4.12 (ES-401, D.l.b)

RO 1/2 068 2.2.17 (ES-401, D.1.b)

RO 1/2 E16 2.2.14 (ES-401, D.1.b)

RO 112 036 2.2.20 (ES-401, D.1.b)

R02/1 026 A3.02 Salem does not have Containment Spray heat exchangers.

R02/1 064 2.1.36 (ES-401, D.l .b)

R02/1 064 2.4.49 No immediate procedurally directed actions for operating EDGs R02/1 073 2.1.40 (ES-401, D.1.b)

RO 2/1 076 Al.02 Salem does not have Reactor and Turbine Buildings closed loop cooling systems RO 2/1 078 A3.01 Sampled on CERT exam R02/1 103 2.1.26 (ES-401, D.l.b)

Page(of2 ES-401 , Page 44 of 50

ES-401

- - - - - R d of Reiected K/As Salem 14-01 NRC E F ES-401-4 R02/2 001 Kl.01 CRD system and CCW do not have any relationship R02/2 015 2.4.42 (ES-401, D.1.b)

R02/2 033 A3.01 Salem does not have TCV for Spent Fuel temperature control.

R02/2 055 2.1.39 (ES-401, D.1.b)

R02/2 068 K5.04 Generic Fundamentals for biological hazards of radiation R03 2.3.5 More suited to operating exam R03 2.1.31 Ability to locate more suited to operating exam SRO 1/1 009 2.2.43 (ES-401, D.1.b)

SRO 111 029 2.2.17 (ES-401, D.1.b)

SRO 111 077 2.3.4 (ES-401, D.1.b)

SRO 1/2 0612.2.17 (ES-401, D.1.b)

SRO 112 E02 2.2.6 (ES-401, D.1.b)

SRO 211 076 2.1.41 (ES-401, D.1.b)

SRO 2/2 033 2.1.40 (ES-401, D.1.b)

SR03 2.1.13 Plant Access control is General Employee Training and RO knowledge also.

SR03 2.4.1 RO level knowledge Page~of 2 ES-401, Page 44 of 50

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SALEM Date of Examination: 12/14/15 Examination Level:

RO SRO Operating Test Number: 14-01 NRC Administrative Describe activity to be performed Type Topic (See Note)

Code*

TCAF Adverse Environmental Conditions (Perform the Circulating Water Conduct of R,D Degradation Index and determine required unit status)

Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Determine the CSD boron concentration and calculate the boron addition required for a natural circulation cooldown Conduct of R,M 2.1.43 Ability to use procedures to determine the effects on reactivity of plant Operations changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Review completed surveillance 2.2.37 Ability to determine operability ar:id/or Equipment Control R,N availability of safety related equipment R0-3.6 Radiation Control N/A Activate EROS during an ALERT Emergency S,P 2.4.43 Knowledge of emergency communications systems and techniques.

Procedures I Plan R0-3.2 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (~3 for ROs; ~4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~1)

(P)revious 2 exams (~1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SALEM Date of Examination: 12/14/15 Examination Level: RO

SRO Operating Test Number: 14-01 NRC Administrative Describe activity to be performed Type Topic (See Note)

Code*

Determine the required actions based on abnormal Secondary Plant chemistry Conduct of conditions.

R,M Operations 2.1.34 Knowledge of primary and secondary plant chemistry limits. SR0-3.5 Determine the TSAS for a dropped rod and complete the applicable log Conduct of R,D 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, Operations and reports. SR0-3.8 Review completed surveillance for operability. 2.2.37 Ability to determine Equipment Control R,N operability and/or availability of safety related equipment SR0-4.6 Select release path (and mark up prints) for Radioactive Liquid Release.

Radiation Control R,D 2.3.6 Ability to approve release permits SR0-3.8 Emergency Classify Emergency I Non-Emergency Events, and complete the ICMF.

S,M,P Procedures I Plan 2.4.29 Knowledge of the Emergency Plan SRO 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (~3 for ROs; ~4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2:1)

(P)revious 2 exams (~1; randomly selected)

ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2 Facility: SALEM Date of Examination: 12/14/15 Exam Level : RO SRO-I Operating Test No.: 14-01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function a) Respond to successive dropped control rods at power A,D,S 1 b) TCAF LT-112 failure, perform manual blended M/U D,S 2 c) Raise ECCS Accumulator Level and Pressure M,S 3 d) Perform Main Turbine Valve Testing A,N,S 4 (sec) e) Transfer 4KV Group Buses to APT, trip Rx upon ATWT A,D,S 6 f) TCAF Undercompensated IR NI channel in TRIP-2 A,L,D,S 7 g) TCAF loss of the CCW system EN,D,S 8 h) TCAF loss of RHR in SOC mode D,L,S 4 (pri)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) Perform Containment Spray Eductor line flushing (can make Alt path if want) N,R 5 j) Locally manually isolate RCP seal injection during LOPA D,E,R 4 (pri) k) Prepare a Waste Gas Decay Tank for Release N,R 9

@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions ; in-plant systems and functions may overlap those tested in the control room.

Type Codes: Criteria for RO/ SR0-1/SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~ 9 I ~8 /~4 (E)mergency or abnormal in-plant ~1 I ~ 1I ~ 1 (EN)gineered safety feature ~ 1 I ~ 1I ~ 1 (control room system)

(L)ow-Power I Shutdown ~ 1 I ~1 I ~1

{N)ew or (M)odified from bank including 1 (A) ~2 I ~ 2 I~ 1 (P)revious 2 exams ~3/ ~3/~2 (randomly selected)

(R)CA ~1 I ~ 1 I~ 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 14-01 NRC Examiners: Operators:

Initial Conditions: 68% power, BOL. 25 CFCU CIT for bearing replacement. Power is being raised at 10% per hour. Control Bank D is at 152 steps withdrawn. Xenon is burning out at 60 pcm per hour. 23 Condensate pump is O/S.

Turnover: Raise power from 68%-90% @ 10% per hour.

Event Malf. No. Event Event Type*

No. Description R CRS I RO 1 Power ascension N PO I

2 NI0193D PRNI fails high (TS)

ALL 3 RC0002 c 20 gpm RCS leak (TS) (all operators respond, PO will ALL perform eves letdown operations)

M 4 RC0001B LBLOCA ALL 5 RP0108 c SI fails to auto actuate RO 6 RP318A c Both RHR pumps fail to start on SEC signal RP318B ALL 7 O/R C812 c 2C 4KV vital bus UV following SEC reset O/R C809 ALL 8 CV62B c Charging pump cavitation while isolating RWST CRS/RO CT's: #1-Start Low Head ECCS, #2- Transfer to Cold Leg Recirc, #3 Trip cavitating charging pump.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No.: 14-01 NRC Examiners: Operators:

Initial Conditions: 100% power, MOL. Solar flares are occurring. SMD K-5 is in effect for next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

26 SW pump is CIT for strainer cleaning.

Turnover: Maintain current power.

Event Malf. No. Event Event Type*

No. Description 1 O/R AG01 c 21 Aux Building Exhaust fan trip (TS 3.7.7)

CRS/RO I

2 PR0016A PZR pressure channel fails low (TS)

CRS/RO R

3 AN3901 Main Generator Radio Frequency hi ALL AN0529 M MPT sudden pressure I Fire protection water deluge 4

AN0316 ALL actuation 5 AF0353C c Failure of AFW initiation AF0182A CRS/PO 6 REM I 2nct PZR pressure channel fails low FP07D ALL 7 SG0078D c SGTR ALL CT's:#1 Terminate SI (crit act time 25 min) #2 Re-establish letdown within 45 minutes.(crit act time)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-3 Op-Test No.: 14-01 NRC Examiners: Operators:

Initial Conditions: 85% power, BOL. 22 Charging pump CIT for biofouling. 26 SW pump is CIT for strainer cleaning. 23 Condensate pump CIT.

Turnover: Power is reduced due to 23 condensate pump trip last shift. Maintain current power.

Event Malf. No. Event Event Type*

No. Description 1 SW0222E N/A 25 SW pump strainer high D/P (TS)

VC0087C 2

VL0337 c Condenser vacuum pump trips VC0087A CRS/PO CN0086B R

3 Degrading condenser vacuum ALL 4 RD0065 c Stuck control rod (TS)

CRS/RO M

5 CN0117B 22 Condensate pump trip ALL 6

O/R C808 c 28 4KV vital bus UV, SEC loading in blackout.

O/R C805 ALL RP318S1 7 CV0208A c Various equipment fails to start on SEC initiation ALL RP318E2 8 AF0183 c Loss of remaining AFW pump ALL CT#1 Initiate RCS Bleed and Feed, CT#2 Close all PZR PORVs and head vent valves

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-4 Op-Test No.: 14-01 NRC Examiners: Operators:

Initial Conditions: 100% power, EOL. Personnel are in containment for surveys.

Turnover: Maintain current conditions.

Event Malf. No. Event Event Type*

No. Description 1 N/A Airlock door failure (TS) 2 c CCW pump trip (TS)

CRS/PO R

3 Steam leak outside containment I power reduction ALL

' M 4 Steamline rupture ALL 5

c 2 stuck rods post trip CRS/RO 6

c Containment air isolation valves fail to shut on SI initiation CRS/RO 7

c Train B SI operate keyswitch fails to operate RO 8

c LOCA outside containment ALL CTs #1 Borate for 2 stuck rods CT#2 Terminate LOCA outside containment

(N)ormal, (R)eact1v1ty, (l)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39