ML19036A820

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Final Written Examination and Operating Test Outlines (Folder 3)
ML19036A820
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/14/2019
From:
NRC Region 1
To:
Shared Package
ML18081A982 List:
References
CAC 000956
Download: ML19036A820 (35)
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{{#Wiki_filter:ES-301 Administrative Topics Outline Form ES-301-1 Facility: Salem Date of Examination: 1/14/2019 Examination Level: RO ~ SRO D Operating Test Number: 17-01 Administrative Topic (see Type Describe activity to be performed Note) Code* Determine the maximum reactor vessel vent time in response to head Conduct of Operations voiding IAW Attachment 1 of 2-EOP-FRCl-3 R,N [2.1.25, R0-3.9; Ability to interpret reference materials, such as graphs, curves, tables, etc.] Conduct of Operations Not Used Perform Borated Water Source surveillance IAW S2.0P-ST.CVC-0010 Equipment Control R,P [2.2.37, R0-3.6; Ability to determine operability and/or availability of safety related equipment] Determine the personnel exposure and special requirements for entry into Radiation Control a radiologically controlled area. (Modified for different room entry) R,M [2.3.4, R0-3.2; Knowledge of radiation exposure limits under normal and emergency conditions] Perform Primary Communicator duties for notifications to NJ and DE Emergency Plan during an ALERT IAW Attachment 6 of EP-SA-111-F6 (Time Critical} S,N [2.4.43, R0-3.2; Knowledge of emergency communication systems and techniques] 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 (~ 1) (P)revious 2 exams (s 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Summary: (RO-A1) Determine the maximum reactor vessel vent time in response to head voiding IAW Attachment 1 of 2-EOP-FRCl-3: The plant has experienced voiding in the reactor vessel and the crew is responding by implementing 2-EOP-FRCl-3, RESPONSE TO VOIDS IN REACTOR VESSEL. The candidate will be required to perform a calculation using from 2-EOP-FRCl-3 and Figure 1 to determine the maximum vent time from the reactor vessel. (RO-A2) Perform Borated Water Source surveillance IAW S2.0P-ST.CVC-0010: The candidate is directed to perform a surveillance test of the Boric Acid Storage Tanks (BAST) using S2.0P-ST.CVC-0010, BORATED WATER SOURCES. The candidate will use Figure 3.1-2 from Technical Specifications 3.1.2.6 to determine the required BAST levels and boron concentration. The candidate will evaluate the combined BAST levels and determine that the surveillance is Unsat due to not meeting the Technical Specification requirements. (RO-A3) Determine the personnel exposure and special requirements for entry into a radiologically controlled area: The candidate will be required to use a radiological survey map and determine the personal exposure for performing a task inside the RCA. The candidate will also be required to use a Radiation Work Permit (RWP) to identify the special requirements applicable for the task. (RO-A4) Perform Primary Communicator duties for notifications to NJ and DE during an ALERT IAW of EP-SA-111-F6: The candidate will act as the Primary Communicator in the control room during an emergency event and be directed to make the required 15 minute notifications to NJ and DE authorities using EP-SA-111-F6, PRIMARY COMMUNICATOR, Attachment 6, PRIMARY COMMUNICATOR LOG. This is a Time Critical task.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Salem Date of Examination: 1/14/2019 Examination Level: RO D SRO IZI Operating Test Number: 17-01 Administrative Topic (see Type Describe activity to be performed Note) Code* Determine which ECCS pumps can be stopped to maintain minimum Conduct of Operations required injection flow IAW 2-EOP-LOCA-5, step 19.2, Figure A R,N [2.1.7, SR0-4.7: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.] Determine the Heat Stress requirements for two operators entering Containment IAW SA-M-111 Conduct of Operations R,P [2.1.26, SR0-3.6: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxvaen and hydrogen)l Determine the Technical Specification action for an inoperable safety Equipment Control related component with one Emergency Diesel Generator (EOG) R,N inoperable. [2.2.40, SR0-4.7: Ability to apply Technical Specifications for a system] Determine personnel exposure and required authorizations for work in Radiation Control a radiologically control area IAW RP-M-463 (Modified for different R,M room entry) [2.3.4, SR0-3.7: Knowledge of radiation exposure limits under normal and emeraencv conditions] Classify Emergency Event and complete the ICMF IAW EP-SA-111-Emergency Plan 101 (Time Critical) R,D [2.4.41, SR0-4.6: Knowledge of the emergency action level thresholds and classifications] 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; :;; 4 for SROs and RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (s 1, randomly selected)

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

SUMMARY

(SRO-A1) Determine which ECCS pumps can be stopped to maintain minimum required injection flow IAW 2-EOP-LOCA-5, step 19.2, Figure A: The plant was manually tripped due to a small break LOCA. Plant conditions have degraded such that no RHR pumps are available for recirculation. The crew has transitioned to EOP-LOCA-5, Loss of Emergency Recirculation. The candidate will determine which ECCS pumps, if any, can be stopped to obtain injection flow as close as possible to the minimum required flow using Figure A in LOCA-5. The candidate will be given the flows for one SI and one Charging pump to determine which pump or pumps can be stopped to minimize injection flow. (SRO-A2) Determine the Heat Stress requirements for two operators entering Containment IAW SA-AA-111: The candidate will calculate the heat stress stay time for two operators isolating a leaking spray valve in the PZR dog house. The candidate will be required to use SA-AA-111 and the Tables to determine the stay time and extended stay time for the task. (SRO-A3) Determine the Technical Specification action for an inoperable safety related component with one Emergency Diesel Generator (EDG) inoperable: The candidate is directed to evaluate Technical Specifications for an inoperable safety related component and one EDG already inoperable for scheduled maintenance. The candidate will evaluate the given condition (inoperable safety-related components) using Technical Specifications and by referring to applicable system operating procedures as necessary. The candidate identifies that TS action 3.8.1.1 action b.2 is applicable. The candidate will then evaluate TS based on additional information that the 1 B EDG and 12 Charging pump cannot be restored to operable status within 4 hours. The candidate will identify the applicable TS action requiring the unit to be placed in Mode 3 in next 6 hours and Mode 5 within the following 30 hours. (SRO-A4) Determine personnel exposure and required authorizations for work in a radiologically control area IAW RP-AA-203: The candidate will determine the dose exposure for two individuals performing a task inside the RCA using a radiological survey map. The candidate will also identify the required authorization for entry into the High Radiation Area. (SRO-AS) Classify Emergency Event and complete the ICMF IAW EP-SA-111-101: The candidate will be given plant conditions and classify the emergency event and complete an ICMF form within 15 minutes. This is a Time Critical task.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Salem Date of Examination: 1/14/2019 Exam Level: RO ~ SRO-I D SRO-U D Operating Test Number: 17-01 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety (KIA, Importance RO/SRO) Function

a. [001] Respond to a Loss of Control Rod Drive Vent Fans (A2.01, 3.1/3.7)

A,D,P,S 1

b. [006] Transfer to Hot Leg Recirculation IAW EOP-LOCA-4 (A4.05, 3.9/3.8)

A,E,EN,L,M,S 2 [MODIFIED to add steps to remove lockouts for both SJ40s in EOP-LOCA-1 and 22 SI pump tripped for alternate path to start 21 SI pump]

c. [01 OJ Respond to PZR spray valve failing to close during depressurization in A,E,L,N,S 3

EOP-SGTR-1(A2.02 3.9/3.9)

d. [002] Perform Bleed and Feed using reactor head vents IAW 2-EOP-FRHS-1 A,D,E,L,P,S 4-Pri (A2.04, 4.3/4.6)
e. [045] Perform Post Maintenance test on Main Turbine Stop Valve IAW A,D,S 4-Sec S2.0P-PT.TRB-0003 (A4.06 2.8/2.7)

(RO Only)

f. [022] Perform 22 CFCU surveillance test IAW S2.0P-ST.CBV-0003 (A 1.04, D,EN,P,S 5

3.2/3.3)

g. [064] Start and load a EOG during Loss of All Offsite Power IAW EOP-LOPA-D,E,L,S 6

1 (A4.06 3.9/3.9)

h. [008] Respond to CCW leak inside containment (lowering surge tank level)

A,E,M,S 8 IAW S2.0P-AB.CC-0001 (A2.02, 3.2/3.5) [MODIFIED to close RCP CCW valves IAW Attachment 2] In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. [004] Perform Emergency Bo ration IAW S 1.0P-AB.CR-0001 (A4.18, 4.3/4.1)

D,E,R 1

j. [012] Parallel Rod Control M-G Set IAW S1.0P-SO.RCS-0001 (A4.07, D

7 3.9/3.9)

k. [071] Perform a radioactive waste gas release IAW S2.0P-SO.WG-0008 D,R 9

(A4.26, 3.1/3.9) 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/S 8/S 4 ~1/~1/~1 ~ 1/~ 1/~ 1 (control room system) ~1/~1/~1 ~ 2/~ 2/~ 1 s 3/::. 3/::. 2 (randomly selected) ~1/~1/~1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Salem Date of Examination: 1/14/2019 Exam Level: RO D SRO-I 1:8:1 SRO-U D Operating Test Number: 17-01 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety (KIA, Importance RO/SRO) Function

a. [001] Respond to a Loss of Control Rod Drive Vent Fans (A2.01, 3.1 /3. 7)

A,D,P,S 1

b. [006] Transfer to Hot Leg Recirculation IAW EOP-LOCA-4 (A4.05, 3.9/3.8)

A,E,EN,L,M,S 2 [MODIFIED to add steps to remove lockouts for both SJ40s in EOP-LOCA-1 and 22 SI pump tripped for alternate path to start 21 SI pump]

c. [01 OJ Respond to PZR spray valve failing to close during depressurization in A,E,L,N,S 3

EOP-SGTR-1 (A2.02 3.9/3.9)

d. [002] Perform Bleed and Feed using reactor head vents IAW 2-EOP-FRHS-1 A,D,E,L,P,S 4-Pri (A2.04, 4.3/4.6)
e. Not Used
f. [022] Perform 22 CFCU surveillance test IAW S2.0P-ST.CBV-0003 (A1.04, D,EN,P,S 5

3.2/3.3)

g. [064] Start and load a EOG during Loss of All Offsite Power IAW EOP-LOPA-D,E,L,S 6

1 (A4.06 3.9/3.9)

h. [008] Respond to CCW leak inside containment {lowering surge tank level)

A,E,M,S 8 IAW S2.0P-AB.CC-0001 (A2.02, 3.2/3.5) [MODIFIED to close RCP CCW valves IAW Attachment 2] In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. [004] Perform Emergency Boration IAW S1.0P-AB.CR-0001 (A4.18, 4.3/4.1)

D,E,R 1

j. [012] Parallel Rod Control M-G Set IAW S1.OP-SO.RCS-0001 (A4.07, D

7 3.9/3.9)

k. [071] Perform a radioactive waste gas release IAW S2.0P-S0.WG-0008 D,R 9

(A4.26, 3.1/3.9) 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: __ Salem ___ Scenario No.: _1 (ESG-1) __ Op-Test No.: _ 17 Examiners: Operators: Initial Conditions: IC-256: 4% power, BOL; 23 Charging Pump is running, 21 SGFP is in service with AFW pumps secured, power ascension in progress at 10% per hour with control rods in manual and steam dumps in MS mode in Auto. 22 SW pump CIT for strainer motor replacement. Turnover: Crew is directed to continue raising Rx power to 10% and enter Mode 1 using Control Rods and Main Steam Dumps IAW S2.0P-IO.ZZ-0003. Critical Tasks:

1.

Manually actuate SI (see WOG CT-2).

2.

Isolate LOCA outside containment (see WOG CT-32). Event Malf. No. Event Event No. Type* Description 1 N/A ALL (R) Power ascension at 10% per hour and enter Mode 1 2 PR0016A RO (I) PZR pressure controlling channel fails high (TS exercised) SRO (1,TS) 3 SG0095A SRO (TS} 21 SG NR level fails low (TS only} 4 CN0094A PO (C) 21A Main Condenser tube leak SRO (C) 5 RC0006B RO (C) 22 RCP motor oil leak requiring manual reactor trip SRO (C) SJ0312A 6 SJ0312B ALL (M) RHR intersystem RCS leak on 22 RHR heat exchanger during EOP-RH0299B TRIP-2 RH0300B 7 A701 RO (I) One train of SI fails to manually actuate. Operator can actuate the A501 SRO (I) other train of SI from control room. 8 RP318S2 RO (I) 22 Charging pump fails to start by 2C SEC. Operator can manually SRO (I) start from control room. 9 VL0045 RO (I) 2CV116 and 2CV284 fail to close on Phase A isolation. Operators can VL0046 SRO (I) manually close from control room. ABs AB.PZR-1 --> AB.CW-1 --> AB.CHEM-1 --> AB.RCP-1 EOPs TRIP-1 --> TRIP-2--> TRIP-1 --> LOCA-6--> LOCA-1 (N)ormal, (R)eactivity, ( I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 (ESG-1) Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 7
2. Malfunctions after EOP entry (1-2) 3 7,8,9
3. Abnormal events (2-4) 3 2,4,5
4. Major transients (1-2) 1 6
5. EOPs entered/requiring substantive actions (1-2) 2 LOCA-6 LOCA-1
6. Entry into a contingency EOP with substantive actions (,?: 1 per 0

scenario set)

7. Preidentified critical tasks (,?:2) 2 CT-2, CT-32
8. Tech Specs exercised(,?: 2) 2 2,3

Appendix D Scenario Outline Form ES-D-1 Facility: __ Salem --- Scenario No.: _2 (ESG-4) __ Op-Test No.: _17-01_ Examiners: Operators: Initial Conditions: IC-259: 100% power, BOL; 23 Charging Pump is in service. The following equipment is out of service: 21 CFCU CIT for breaker replacement. Turnover: After the crew assumes the watch, the Primary NEO will direct the CRS to complete the review of room cooler surveillance procedure completed end of last shift. Critical Tasks:

1.

Manually actuate containment cooling (see WOG CT-3)

2.

Isolate faulted SG (see WOG CT-17) Event Malf. No. Event Event No. Type* Description 1 N/A SRO (TS) After taking watch, CRS reviews completed Room Cooler surveillance procedure (S2.0P-ST.SW-0014) (TS only) 2 CV0035 RO (I) Charging Master Flow Controller demand fails low SRO (I) 3 SW0216B PO (C)

  1. 4 SW bay leak (ramped over 2 minutes) (TS exercised)

SRO (C,TS) 4 MS0088Ar ALL (C) 21 Loop Steam Line leak inside containment (3 min ramp) Reduce turbine load to lower reactor power to s 100% 5 MS0090Ar ALL (M) 21 Loop Steam Line break inside containment resulting in auto reactor trip, MSLI and manual SI. 24 CFCU trips on low speed start (1 min delay) VC0173D RO (I) 22 CS pump trips following CS start signal 6 CS0171B 21 Containment Spray pump fails to start on SEC signal RP318L 1 SRO (I) Operator blocks 2A SEC and starts 21 CS pump from control room 7 VL0011 RO (I) 21CS2 CS pump discharge valve fails to open on CS signal. Operator SRO (I) can manually open from control room. ABs AB.CVC-1 --+ AB.SW-3--+ AB.STM-1 EOPs TRIP-1 --+ LOSC-1--+ TRIP-3 (N)ormal, (R)eactivity, ( I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 (ESG-4} Target Quantitative Attributes per Scenario (See Section 0.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 2 6,7
3. Abnormal events (2-4) 3 2,3,4
4. Major transients (1-2) 1 5
5. EOPs entered/requiring substantive actions (1-2) 2 LOSC-1 TRIP-3
6. Entry into a contingency EOP with substantive actions ( ~ 1 per 0

scenario set)

7. Preidentified critical tasks (~2) 2 CT-3, CT-17
8. Tech Specs exercised(~ 2) 2 1,3

Appendix D Scenario Outline Form ES-D-1 Facility: __ Salem ___ Scenario No.: _3 (ESG-3) __ Op-Test No.: _17-01_ Examiners: Operators: Initial Conditions: IC-258: 89.5% power, MOL; 23 Charging Pump is in service. The following equipment is out of service: 21 Charging pump CIT for oil cooler cleaning, 21A CW pump is CIT for waterbox cleaning, 21 BAT pump CIT for pump seal replacement, 22 vacuum pump CIT for pump replacement. Turnover: Main turbine valve testing was completed last shift. Calorimetric was performed SAT and MSRs are in Auto. The crew is directed to continue power ascension to 100% power at 10% per hour IAW S2.0P-IO.ZZ-0004 using control rods and turbine load control. Critical Tasks:

1.

Insert negative reactivity into the core (see WOG CT-52)

2.

Close PZR PORV Block valve (see WOG CT-10) Event Event No. Type* Description 1 N/A ALL (R) Power ascension to 100% at 10% per hour 2 VC0311A SRO (TS) Containment Pressure Channel fails high (TS only) 3 SJ0180B RO (I) 22 SI Accumulator gas leak (TS exercised) SRO (l,TS) CN0086B ALL (C) . Loss of Main Condenser vacuum due to loose tube plug. 4 . Unit power reduction to stabilize condenser vacuum RD050113 RD050122 RP0058 Two dropped control rods requiring manual reactor trip. 5 RP0059A ALL (M) RP0059B ATWTevent. RP0060A RP0060B 6 RD0061 RO (I) Rod Control speed controller fails at 8 spm in Auto. Operator can SRO (I) insert rods in Manual at 48 spm. 7 VL0095 PO (I) 2CV175 Rapid Boration valve fails to open in EOP-FRSM-1. Rapid SRO (I) borate via the RWST. 8 VL0297 RO (I) 2PR1 PZR PORV fails open during EOP-TRIP-2. Operators can SRO (I) manually close PZR block valve. ABs AB.COND-1 ---> AB.LOAD-1 EOPs TRIP-1...... FRSM-1---> TRIP-1...... TRIP-2 (N)ormal, (R)eactivity, ( I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 3 (ESG-3} Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 3 6,7,8
3. Abnormal events (2-4) 2 3,4
4. Major transients (1-2) 1 5
5. EOPs entered/requiring substantive actions (1-2) 1 FRSM-1
6. Entry into a contingency EOP with substantive actions ( ;.,; 1 per 1

FRSM-1 scenario set)

7. Preidentified critical tasks (2:':2) 2 CT-52, CT-10
8. Tech Specs exercised (2:': 2) 2 2,3

Appendix D Scenario Outline Form ES-D-1 Facility: __ Salem --- Scenario No.: _4 (ESG-5) __ Op-Test No.: _17-01_ Examiners: Operators: Initial Conditions: IC-260: 88% power, MOL; 23 Charging Pump is in service. The following equipment is out of service: 21 AFW pump CIT for oil bubbler leak repair, 21 SI pump CIT for coupling inspection and alignment checks. Turnover: Reactor power was lowered for preparation for main turbine valve testing. Testing will commence next shift. Critical Tasks:

1.

Manually trip the reactor (see WOG CT-1)

2.

Establish main feed water flow to SGs before bleed and feed is required (see WOG CT-43) Event Malf. No. Event Event No. Type* Description 1 PR0018B RO (C) 2PR2 PZR PORV leaks (TS exercised) SRO (C,TS) 2 NI0193A RO (I) 2N41 Power Range channel fails high (TS exercised) SRO (l,TS) 21 SGFP trips on turbine thrust pressure high 3 BF0105A ALL{C) Failure ofTurbine Runback following SGFP trip. Operator can EH0327 manually initiate runback from control room. Load reduction to 66% power oer AB.CN-0001 4 TU0066 ALL (M) Inadvertent Main Turbine trip signal 5 RP0058 RO (I) Reactor fails to auto trip. Operator can manually trip the reactor from RP0059B SRO (I) control room. EL0145 PO {I) Loss of 28 4K Vital Bus {loss of 22 AFW pump) 6 AF0353C . 23 AFW pump fails to auto start. Operator can manually start, but AF0183 SRO (I) will trio shortlv after time delav. (loss of all AFW flow) ABs AB.PZR-1 -> AB.NIS-1 -> AB.CN-1 EOPs TRIP-1 -> FRHS-1 with prompt SGFP recovery (N)ormal, (R)eactivity, ( I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 4 (ESG-5) Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 1 6
3. Abnormal events (2-4) 3 1,2,3
4. Major transients (1-2) 1 4
5. EOPs entered/requiring substantive actions (1-2) 1 FRHS-1
6. Entry into a contingency EOP with substantive actions ( ~ 1 per 1

FRHS-1 scenario set)

7. Preidentified critical tasks (~2) 2 CT-1, CT-43
8. Tech Specs exercised(~ 2) 2 1,2

Appendix D Scenario Outline Form ES-D-1 Facility: __ Salem --- Scenario No.: _5 (ESG-2) __ Op-Test No.: _17-01_ Examiners: Operators: Initial Conditions: IC-257: 38% power, BOL; 23 Charging Pump is in service. The following equipment is out of service: 23 Condensate pump and all Heater Drain pumps due to power level, 22 CS spray pump err to troubleshoot elevated motor vibrations, 21 B CW pump is err for waterbox cleaning. Turnover: The crew is directed to maintain current power level until maintenance completes troubleshooting and repairs on 22 SGFP for high vibration alarms. Critical Tasks:

1.

Isolate ruptured SG (see WOG CT-18)

2.

Control initial RCS Cooldown (see WOG CT-19) II Event Malf. No. Event Event I No. Type* Description 1 VL0420 PO {I} 21 MS 167 drifts from full open position SRO (I) 2 PR0017B RO (I) PZR level alarm channel fails low (TS exercised) SRO (l,TS) AN0413 3 Q4221 SRO (TS) 21 RCP loop flow channel I fails low (TS only) AJ08 4 SG0078A RO (C) 21 SG tube leak (==20 gpm) (TS exercised) SRO (C,TS} I 5 N/A ALL (R) Unit shutdown due to RCS leakage exceeding TS 6 SG0078A ALL (M) 21 SG tube rupture (650 gpm) requiring operators to trip the reactor and initiate SI. SW0215F PO {I) 26 SW pump (alternate) trips and 25 SW pump (primary) fails to start 7 RP318B3 SRO (I) on SEC signal. Operator blocks SEC signal and manually starts 25 SW0339E SW pump. 8 MS0093 PO (I) Loss of Steam Dump Vacuum permissive. Operators can use MS10's SRO (I) for RCS cooldown. 9 MS0119A SRO (C) 21 SG Steam Line Safety Relief valve fails fully open. Crew responds by transitioning to EOP-SGTR-3 ABs AB.CVC-1 --> AB.SG-1 --> AB.LOAD-1 EOPs TRIP-1 --+ SGTR-1 --> SGTR-3 for faulted ruptured SG (N)ormal, (R)eactivity, ( I )nstru ment, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 5 (ESG-2) Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 7
2. Malfunctions after EOP entry (1-2) 3 7,8,9
3. Abnormal events (2-4) 3 1,2,4
4. Major transients (1-2) 1 6
5. EOPs entered/requiring substantive actions (1-2) 1 SGTR-1
6. Entry into a contingency EOP with substantive actions ( ~ 1 per 0

scenario set)

7. Preidentified critical tasks (~2) 2 CT-18, CT-19
8. Tech Specs exercised(~ 2) 3 2,3,4

Es-401, Rev. 11 PWR Examination Outline Form Es-401-2 I Facility: Date of Exam: I RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1.

1 2 4 3 3 3 3 18 3 3 6 Emergency& I I I 2 1 1 2 2 2 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 3 5 5 5 5 4 27 5 5 10 ~ I I 31,, I I I I I 1 2 2 3 3 2 3 3 3 28 3 2 5

2.

I I I I Plant 2 1 1 0 1 1 1 1 1 1 1 1 10 2 1 3 Systems ~ I I 4'~ I I Tier Totals 3 2 4 4 3 4 4 4 38 3 8

3. Generic Knowledge and Abilities 1

2 3 4 10 t ', I 2, t*,I 4 I 7 I Categories o/ ¥ ~ 3 2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control KIA 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1.b of ES-401 for the applicable KAs.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (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 K/A 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..

ES-401, REV 11 T1G1 PWR EXAMINATION OUTLINE KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 007EK2.02 Reactor Trip - Stabilization - Recovery 2.6 2.8 D ~ D D D D D D D D D / 1 008AK2.03 Pressurizer Vapor Space Accident/ 3 2.5 2.4 D ~ D D D D D D D D D 009EK2.03 Small Break LOCA / 3 3 3.3 D ~ D D D D D D D D D 011EK2.02 LargeBreakLOCA/3 2.6 2.7 D [29 DD D DD DD DD 015AK1.04 RCP Malfunctions I 4 2.9 3.1 ~ D D D D D D D D D D 022AA1.08 Loss of Rx Coolant Makeup/ 2 3.4 3.3 D D D D D D ~ D D D D 026AA1.07 Loss of Component Cooling Water/ 8 2.9 3 D D D D D D ~ D D D D 029EG2.4.50 ATWS / 1 4.2 4.o D D D D D D D D D D ~ 054AA2.03 Loss of Main Feedwater / 4 4.1 4.2 D D D D D D D ~ D D D 056AG2.2.39 Loss of Off-site Power I 6 3.9 4.s D D D D D D D D D D ~ 058AA2.03 Loss of DC Power I 6 3.s 3.9 D D D D D D D ~ D D D Page 1 of2 FORM ES-401-2 TOPIC: Breakers, relays and disconnects Controllers and positioners S/Gs Pumps Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow VCT level Flow rates to the components and systems that are serviced by the CCWS; interactions among the components Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. Conditions and reasons for AFW pump startup Knowledge of less than one hour technical specification action statements for systems. DC loads lost; impact on ability to operate and monitor plant systems 04/30/2018 9:17 AM

ES-401, REV 11 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 062AA2.02 Loss of Nuclear Svc Water/ 4 2.9 3.6 D DDDDD~DDD The cause of possible SWS loss 065AK3.04 Loss of Instrument Air/ 8 3 3.2 D D ~ D D D D D D D D Cross-over to backup air supplies 077AG2.4.34 Generator Voltage and Electric Grid 4.2 4.1 DDDDDDDDDD~ Knowledge of RO tasks performed outside the main Disturbances / 6 control room during an emergency and the resultant operational effects WE04EK3.4 LOCA Outside Containment/ 3 3.6 3.8 DD~DDDDDDDD RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated. WE05EK1.3 Inadequate Heat Transfer - Loss of 3.9 4.1 ~DDDDDDDDDD Annunciators and conditions indicating signals, and Secondary Heat Sink / 4 remedial actions associated with the (Loss of Secondary Heat Sink). WE11EA1.3 Loss of Emergency Coolant Recirc. / 4 3.7 4.2 DDDDDD~DDDD Desired operating results during abnormal and emergency situations. WE12EK3.3 Steam Line Rupture - Excessive Heat 3.5 3.7 DD~DDDDDDDD Manipulation of controls required to obtain desired Transfer I 4 operating results during abnormal and emergency situations. Page 2 of2 04/30/2018 9:17 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: 001AA1.07 Continuous Rod Withdrawal / 1 036AK3.02 Fuel Handling Accident/ 8 037AK1.01 Steam Generator Tube Leak / 3 051AA2.02 Loss of Condenser Vacuum / 4 068AA2.06 Control Room Evac. / 8 ~- 074EA1.27 lnad. Core Cooling / 4 WE03EK2.2 LOCA Cooldown - Depress. / 4 WE08EK3.1 RCS Overcooling - PTS / 4 we15EG2.1.19 Containment Flooding / 5 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC: RO SRO 3.3 3.1 D D D D D D ~ D D D D RPI 2.9 3.6 D D ~ D D D D D D D D Interlocks associated with fuel handling equipment 2.9 3.3 ~ D D D D D D D D D D Use of steam tables 3.9 4.1 D D D D D D D ~ D D D Conditions requiring reactor and/or turbine trip 4.1 4.3 D D D D D D ~ D D D pressure -~ 4.2 4.2 D D D D D D ~ D D D D ECCS valve control switches and indicators 3.7 4.o D ~DD DD DD DD D 3.4 3.9 DD~ DD DD DD DD 3.9 3.8 D D D D D D D D D D ~ Page 1 of 1 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility. Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics. Ability to use plant computer to evaluate system or component status. 04/30/2018 9:18 AM

ES-401, REV 11 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC: RO SRO 003K6.14 Reactor Coolant Pump 2.6 2.9 DDDDD~DDDDD Starting requirements 004A2.09 Chemical and Volume Control 3.0 3.9 DDDDDDD~DDD High primary and / or secondary activity 004K3.01 Chemical and Volume Control 2.5 2.9 DD~DDDDDDDD CRDS (automatic) 005K5.05 Residual Heat Removal 2.7 3.1 DDDD~DDDDDD Plant response during "solid plant": pressure change due to the relative incompressibility of water 006K1.11 Emergency Core Cooling 2.8 3.2 ~DDDDDDDDDD ccws 007A1.03 Pressurizer Relief/Quench Tank 2.6 2.7 DDDDDD~DDDD Monitoring quench tank temperature 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 DDDD~DDDDDD Method of forming a steam bubble in the PZR 008A2.04 Component Cooling Water 3.3 3.5 DDDDDDD~DDD PRMS alarm 010K1.08 Pressurizer Pressure Control 3.2 3.5 ~DDDDDDDDDD PZR LCS 010K5.02 Pressurizer Pressure Control 2.6 3.0 DDDD~DDDDDD Constant enthalpy expansion through a valve 012A3.03 Reactor Protection 3.4 3.5 DDDDDDDD~DD Power supply Page 1 of 3 04/30/2018 9:18 AM

ES-401, REV 11 T2G1 PWR EXAMINATION OUTLINE KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 013K2.01 Engineered Safety Features Actuation 3.6 3.8 D ~ D DDDDDDD 022K2.01 Containment Cooling 026A4.05 Containment Spray 026G2.+.e6" Containment Spray z.,.zr 039A4.04 Main and Reheat Steam 3.o 3.1 D ~DD DD DD DD D 3.s 3.s D D D D D D D D D ~ D ~~ DDDDDDDDDD~ ?-C) 4.z, 3.8 3.9 D D D D D D D D D ~ D 059A2.06 Main Feedwater 2.1 2.9 DD DD DD D ~DD D 059K4.05 Main Feedwater 061~ Auxiliary/Emergency Feedwater z._<)"l-061K6.02 Auxiliary/Emergency Feedwater 062K3.01 AC Electrical Distribution 063A1.01 DC Electrical Distribution 2.s 2.8 D D D ~ D D D D D D D J,.0'~ D~DDDDDDDDD

.1
,7 2.6 2.1 DD DD D ~DD DD D 3.s 3.9 D D ~ D D D D D D D D 2.s 3.3 D D D D D D ~ D D D D Page 2 of3 FORM ES-401-2 TOPIC

ESFAS/safeguards equipment control Containment cooling fans Containment spray reset switches Knowledge of operational implications of EOP wamin

  • cautions anv.,v,v~.

-,:t,/..e'f,-,e.f~'-",'l,i.e..'hri., ( Emergency feedwater pump turbines Loss of steam flow to MFW system Control of speed of MFW pump turbine AF~iElieeel eJr1i,c11 001110 Q_ ,4-Rvfvwy:,5 Pumps Major system loads Battery capacity as it is affected by discharge rate 04/30/2018 9:18 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: 063G2.2.44 DC Electrical Distribution 064A 1. 05 Emergency Diesel Generator 073A4.01 Process Radiation Monitoring 076K4.03 Service Water 078G2.2.38 Instrument Air 103K4.04 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 4.2 4.4 D D D D D D D D D D ~ 2.s 2.s D D D D D D ~ D D D D 3.9 3.9 D D D D D D D D D ~ D 2.9 3.4 D ~DDDDDDD 3.6 4.s D D D D D D D D D D ~ 2.s 3.2 D D D ~ D D D D D D D Page 3 of 3 FORM ES-401-2 TOPIC: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions ED/G room temperature Effluent release Automatic opening features associated with SWS isolation valves to CCW heat exchanges Knowledge of conditions and limitations in the facility license. Personnel access hatch and emergency access hatch 04/30/2018 9:18 AM

ES-401, REV 11 T2G2 PWR EXAMINATION OUTLINE KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 001K4.05 Control Rod Drive 3.9 3.9 DDD~DDDDDDD 015A4.03 Nuclear Instrumentation 3.8 3.9 DDDDDDDDD~D 016K1.06 Non-nuclear Instrumentation 3.6 3.5 ~DDDDDDDDDD 028K5.04 Hydrogen Recombiner and Purge 2.6 3.2 DDDD~DDDDDD Control 034K6.02 Fuel Handling Equipment 2.6 3.3 DDDDD~DDDDD 041K2.01 Steam Dump/Turbine Bypass Control 2.8 2.9 D ~ D D D D D D D D D 071~ ,tJ.,r3 Waste Gas Disposal 072G2.4.31 Area Radiation Monitoring 075A2.01 Circulating Water 086A1.05 Fire Protection .w)A'" DD DD DD DD~ DD lo "J.~ 4.2 4.1 D D D D D D D D D D ~ 3.o 3.2 D D D D D D D ~ D D D 2.9 3.1 D D D D D D ~ D D D D Page 1 of 1 FORM ES-401-2 TOPIC: Boration and dilution. Trip bypasses AFW system The selective removal of hydrogen Radiation monitoring systems ICS, normal and alternate power supply -~ ~/Its c.."",;). "".j..).,"5 s~.._./5 Knowledge of annunciator alarms, indications, or response procedures. Loss structure FPS lineups 04/30/2018 9:19 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: G2.1.15 Conduct of operations G2.1.28 Conduct of operations G2.2.20 Equipment Control G2.2.25 Equipment Control G2.3.11 Radiation Control Radiation Control -Z...*,.'1 G2.3.13 Radiation Control G2.4.22 Emergency Procedures/Plans G2.4.3 Emergency Procedures/Plans G2.4.11 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.1 3.4 DD DD DD DD DD~ 4.1 4.1 D D D D D D D D D D ~ 2.6 3.8 D D D D D D D D D D ~ 3.2 4.2 D D D D D D DOD~ 3.8 4.3 D D D D D D D D D D ~ 3.2 3.7 DD DD DD DD DD~ 3.4 3.8 D D D D D D D D D D ~ 3.6 4.4 D D D D D D D D D D ~ 3.7 3.9 DD DD DOD~ 4.o 4.2 D D D D D D D D D D ~ Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc. Knowledge of the purpose and function of major system components and controls. Knowledge of the process for managing troubleshooting activities. Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Ability to control radiation releases. Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. Ability to identify post-accident instrumentation. Knowledge of abnormal condition procedures. 04/30/2018 9:20 AM

ES-401, REV 11 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 008AA2.23 Pressurizer Vapor Space Accident/ 3 3.6 4.3 D D D D D D D ~ D D D 011 EG2.1.27 Large Break LOCA / 3 025AG2.1.27 Loss of RHR System I 4 056AA2.22 Loss of Off-site Power I 6 065A~ Loss of Instrument Air/ 8 ?.., l. 2.~ WE04EA2.1 LOCA Outside Containment/ 3 3.9 4 DDDDDDDDDD~ 3.9 4 DDDDDDDDDD~ 3.4 3.6 D D D D D D D ~ D D D

r.t"'~ DDDDDDDDDD~

Y.\\ 1.(,1 3.4 4.3 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC: Criteria for throttling high-pressure injection after a small LOCA Knowledge of system purpose and or Knowledge of system purpose and or function. Emergency lube oil pump indicators and low-pressure alarms on ED/G Ability to analyze the effect of mainten such as d er sources, on the status of limiting cond1 ions of operations i-<r1'1""'{.,.l.ff...t--{V"'f~5e+ ~ ... J,0'1. Facility conditions and selection of appropriate procedures during abnormal and emergency operations. 04/30/2018 9:24 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: 028~ Pressurizer Level Malfunction / 2 '2_6'3 068AG2.4.50 Control Room Evac. / 8 076~ High Reactor Coolant Activity/ 9 2.u'? we10EG2.4.46 Natural Gire. With Seam Void/ 4 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO ~2-.ft' D D D D D D D ~ D D D Z,t 33 4.2 4.o D D D D D D D D D D ~ ~y DDDDDDD~DDD Z.<; '?,.() 4.2 4.2 D D D D D D D D D D ~ Page 1 of 1 FORM ES-401-2 TOPIC: The effect on indicated i;lh!' Mv*~, ambient pressure and temperature of reflux boiling <:_i, C.,r:J ";,t.j s~lo.57~iJ.c..-....Vl.., i..J;c.....fer-i2 u<l'l-/v-~//....- Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. Pf.OGOss efflae11t 1adiatior1 t11art r~ (?.C 5 r,;.).-.od,~,f /,.,_../ Vk..e/.u-Ability to verify that the alarms are consistent with the plant conditions. 04/30/2018 9:24 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: 005G2.4.41 Residual Heat Removal 008A2.09 Component Cooling Water 026A2.07 Containment Spray 062G2.2.42 AC Electrical Distribution 063A2.01 DC Electrical Distribution SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.9 4.6 D D DDDDDDD~ 2.3 2.8 D D D D D D D ~ D D D 3.6 3.9 D D D D D D D ~ D D D 3.9 4.6 D D D D D D D D D D ~ 2.s 3.2 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of the emergency action level thresholds and classifications. Results of excessive exit temperature from the letdown cooler, including the temperature effects on ion-exchange resins Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding) or sump level below cutoff (interlock) limit Ability to recognize system parameters that are entry-level conditions for Technical Specifications Grounds 04/30/2018 9:25 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: 028A2.03 Hydrogen Recombiner and Purge Control 055G2.4.11 Condenser Air Removal 079A2.01 Station Air SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.4 4.o D D D D D D D ~ D D D 4.o 4.2 D D D D D D D D D D ~ 2.9 3.2 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC: The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment Knowledge of abnormal condition procedures. Cross-connection with IAS 04/30/2018 9:26 AM

ES-401, REV 11 KA NAME/ SAFETY FUNCTION: G2.1.5 Conduct of operations G2.2.14 Equipment Control G2.2.42 Equipment Control G2.3.4 Radiation Control G2.3.7 Radiation Control G2.4.35 Emergency Procedures/Plans G2.4.38 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.9 3.9 D D D D D D D D D D ~ 3.9 4.3 D D D D D D D D D D ~ 3.9 4.6 D D D D D D D D D D ~ 3.2 3.7 D D D D D D D D D D ~ 3.s 3.6 D D D D D D D D D D ~ 3.8 4.o D D D D D D D D D D ~ 2.4 4.4 D D D D D D D D D D ~ Page 1 of 1 FORM ES-401-2 TOPIC: Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Knowledge of the process for controlling equipment configuration or status Ability to recognize system parameters that are entry-level conditions for Technical Specifications Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator. 04/30/2018 9:28 AM

Salem Generating Station - ILOT Class 17-01 Written Exam ES-401 Record of Rejected K/As Form ES-401-4 Tier/ Randomly Reason for Rejection Group Selected K/ A R056 029 Anticipated Kl A: Ability to verify system alarm setpoints and operate controls Transient Without identified in the alarm response manual 1 / 1 Scram (ATWS)- G2.4.50 During an ATWS, functional restoration procedure FRSM-1 will be performed by the crew. This functional restoration takes precedence over any alarm response procedure. Consequently, writing a question asking the crew to perform an Alarm Response Procedure while performing a Functional Restoration Procedure is not operationally valid. Replaced With 029 Anticipated Transient Without Scram (ATWS)-G2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. R062 077 Generator KIA: Knowledge of RO tasks performed outside the main control room 1 / 1 Voltage and Electric during an emergency and the resultant operational effects Grid Disturbances-G2.4.34 RO tasks during performance ofS2.0P-AB.GRID-OOOl(ABNORMAL GRID) are performed in the main control room. If you try to combine S2.0P-AB.GRID-0001 with a control room evacuation, then the crew would at a minimum trip the reactor per S2.0P-AB.CR-OOO 1 (CONTROL ROOM EVACUATION). This will negate any mitigating actions contained in S2.0P-AB.GRID-0001, since S2.0P-AB.GRID-0001 assumes the Unit will stay online or be tripped from the control room. Replaced With 077 Generator Voltage and Electric Grid Disturbances-G2.2.37 Ability to determine operability and/or availability of safety related equipment RO 15 026 Containment KIA: Knowledge of the operational implications ofEOP warnings, 2 /1 Spray - G2.4.20 cautions, and notes Unable to find a specific Containment Spray EOP warning, caution or note to test. Replaced With 026 Containment Spray - G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Salem Generating Station - ILOT Class 17-01 Written Exam ES-401 Record of Rejected K/As Form ES-401-4 RO 19 061 Auxiliary / KIA: Knowledge of bus power supplies to the following: AFW diesel 2 I 1 Emergency F eedwater driven pump (AFW) System-K2.03 Salem does not have a diesel driven AFW pump. Replace with K2.02 AFW electric drive pumps R035 071 Waste Gas Kl A: Ability to monitor automatic operation of the Waste Gas Disposal 2/2 Disposal System-System including: HRPS (hydrogen recombiner and purge control A3.0l system) At Salem, there is no interaction between Waste Gas Disposal System and HRPS. Replaced With A3.03 Radiation monitoring system alarm and actuating signals. R045 G2.3.12 Kl A: Knowledge of radiological safety principles pertaining to licensed 3 operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Very close to KIA for RO Q44 G2.3.12 plus this KIA is more related to fundamentals Replaced With G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. SR05 065 Loss of Kl A: Ability to analyze the effect of maintenance activities, such as 1 /1 Instrument Air - degraded power sources, on the status of limiting conditions for G2.2.36 operations At Salem there is no LCO directly related to Instrument Air. The CA330s serve as containment isolation valves and are bounded by LCO 3.6.3. However, LCO 3.6.3 and the CA330s were already tested in RO Q27. Replaced With G2.l.28 Knowledge of the purpose and function of major system components and controls

Salem Generating Station - ILOT Class 17-01 Written Exam ES-401 Record of Rejected K/As Form ES-401-4 SR07 028 Pressurizer (PZR) Kl A : Ability to determine and interpret the following as they apply to the 1/2 Level Control Pressurizer Level Control Malfunctions: The effect on indicated PZR Malfunction - levels, given a change in ambient pressure and temperature of reflux AA2.14 boiling The Abnormal Procedure for a malfunction of PZR Level Control is S2.0P-AB.CVC-OOO 1 (LOSS OF CHARGING). S2.0P-AB.CVC-OOO 1 only deals with a failure of a PZR level channel. No mention of Reflux Boiling is mentioned in S2.0P-AB.CVC-0001. Additionally, S2.0P-AB.RHR-000l(LOSS OF RHR) Attachment 9 (STEAM GENERATOR REFLUX COOLING) has no mention on any malfunction or inaccuracy in PZR Level Control during performance of the attachment. Replaced With A2.03 Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Charging subsystem flow indicator and controller SR09 076: High Reactor Kl A: Ability to determine and interpret the following as they apply to the 1/2 Coolant Activity - High Reactor Coolant Activity: Process effluent radiation chart recorder AA2.04 S2.0P-AB.RC-0002 (HIGH ACTIVITY IN REACTOR COOLANT SYSTEM) does not mention the 2FR1064 (RADWASTE OVERBOARD DISCH FLOW RECORDER). S2.0P-SO.WL-0003 (RELEASE OF RADIOACTIVE LIQUID WASTE FROM 2 WASTE MONITOR HOLDUP TANK does have requirements for 2FR1064. However, this concept is already being tested in RO 43 (Kl A: G2.3. l 1 Ability to control radiation releases) Replaced With AA2.03 RCS radioactivity level meter}}

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