ML18135A225

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Draft Written Examination and Operating Test Outlines (Folder 2)
ML18135A225
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/20/2018
From:
Public Service Enterprise Group
To: D'Antonio J
Operations Branch I
Shared Package
ML17194A494 List:
References
CAC 000500
Download: ML18135A225 (33)
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Text

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Salem Date of Examination: 1/22/2018 Initials Item Task Description a b* c**

1. a. Verify that the outline(s) fit(s) the appropriate model in accordance with ES-401 or ES-401 N. I?. ~ //

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b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 or ES-401 N and whether all KIA categories are appropriately sampled. R. ~ ;J-I T C. Assess whether the outline overemphasizes any systems, evolutions, or generic topics. f<.  !) l'Y T

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d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. ~ () A/'
2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of s

normal evolutions, instrument and component failures, technical specifications, and major transients.

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I M b. Assess whether there are enough scenario sets (and spares) to test the projected number and u

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mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the (L e 4 T applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

0 c. To the extent possible, assess whether the outline(s) conforms with the qualitative and R

quantitative criteria specified on Form ES-301-4 and described in Appendix D and in Section D.5, "Specific Instructions for the 'Simulator Operating Test,"' of ES-301 (including fl- ~ /Y overlap).

3. a. Verify that the systems walkthrough outline meets the criteria specified on Form ES-301-2:

(1) The outline(s) contains the required number of control room and in-plant tasks distributed w among the safety functions as specified on the form.

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(2) Task repetition from the last two NRC examinations is within the limits specified on the form.

(3) No tasks are duplicated from the applicant's audit test(s).

t2.- ~ I" K (4) The number of new or modified tasks meets or exceeds the minimums specified on the form.

T (5) The number of alternate-path, low-power, emergency, and radiologically controlled area H tasks meets the criteria on the form.

R 0 b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

u (1) The tasks are distributed among the topics as specified on the form. (l G

H (2) At least one task is new or significantly modified.

(3) No more than one task is repeated from the last two NRC licensing examinations.

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c. Determine whether there are enough different outlines to test the projected number and mix of (2- /Y applicants and ensure that no items are duplicated on subsequent days. ~
4. a. Assess whether plant-specific priorities (including probabilistic risk assessment and individual plant examination insights) are covered in the appropriate exam sections.

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E b. Assess whether the 10 CFR 55.41, 55.43, and 55.45 sampling is appropriate. (L ~ ('

N C. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. (L. c) rr E

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d. Check for duplication and overlap among exam sections and the last two NRC exams. (~

A 1/1' L e. Check the entire exam for balance of coverage. (L

f. Assess whether the exam fits the appropriate job level (RO or SRO). I?- ~ vv
a. Author R" Jo \o 'h Printed Nam~na-~r:f (h~t,,\ . --- .

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Facility Reviewer(*)

NRC Chief Examiner(#) J, flA,J~,Jr" I Lhi'-;a~ ~ ( /

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d. NRC Supervisor If I i/J t I, /
  • Not applicable for NRG-prepared examination outlines.
  1. The independent NRC reviewer initials items in column "c"; the chief examiner's concurrence is required.

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

Date of Examination: 1/22/2018 Examination Level: RO iZl SRO D Operating Test Number: 16-01 Administrative Topic (see Type Describe activity to be performed Note) Code*

Perform a manual AFD calculation JAW S2.0P-ST.NIS-0001 Conduct of Operations R,D [2.1.25, R0-3.9; Ability to interpret reference materials, such as graphs, curves, tables, etc.]

Conduct of Operations Perform control room log readings for 21-24 reactor coolant loops OTDT R,N channel check IAW S2.0P-DL.ZZ-0003

[2.1.18, R0-3.6; Ability to make accurate, clear, and concise logs, records, status boards, and reportsl Calculate a manual QPTR JAW S2.0P-ST.NIS-0002 Equipment Control R,D [2.2.12, R0-3.7; Knowledge of surveillance procedures]

N/A Radiation Control Activate EROS during an ALERT JAW EP-SA-111-F8 Emergency Plan S,P [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 Ciass(R)oom (D)irect from bank (:5 3 for ROs; :;;; 4 for SROs and RO retakes)

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

(P)revious 2 exams (:5 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Salem Date of Examination: 1/22/2018 Examination Level: RO D SRO IZl Operating Test Number: 16-01 Administrative Topic (see Type Describe activity to be performed Note) Code*

Review and approve the Non-Essential heat load requirements for inoperable chiller(s) !AW S2.0P-SO.CH-0001 Conduct of Operations R,D

[2.1.25, SR0-4.2: Ability to interpret reference materials, such as graphs, curves, tables, etc.]

Determine the Heat Stress requirements for two operators entering Containment !AW SA-M-111 Conduct of Operations R,N

[2.1.26, SR0-3.6: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxyQen and hydroQen)]

Review and approve a safety tagging request !AW OP-M-109 and identify applicable Technical Specifications required Equipment Control R,D

[2.2.13, SR0-4.3: Knowledge of tagging and clearance procedures]

Authorize a Radioactive Gas Release Radiation Control R,D [2.3.6, SR0-3.8: Ability to approve a release permit]

Classify Emergency Event and complete the ICMF !AW EP-SA-111-101 (Time Critical)

Emergency Plan R,M

[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 (:5 3 for ROs; :5 4 for SR Os and RO retakes)

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

(P)revious 2 exams (:5 1, randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Salem Date of Examination: 1/22/2018 Exam Level: RO IZl SRO-I D SRO-U D Operating Test Number: 16-01 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function (KIA, Importance RO/SRO)

a. [001] TCAF a Loss of Control Rod Drive Vent Fan(s) (A2.01, 3.1/3.7) A,N,S 1
b. [004] Perform manual Makeup of the VCT IAW S2.0P-SO.CVC-0006 (A4.13, N,S 2 3.3/2.9)
c. [006] Isolate ECCS Accumulators IAW 2-EOP-TRIP-6 (A1.13, 3.5/3.7) A,D,L,P,S 3
d. [002] Initiate 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] Synchronize the main generator IAW S2.0P-SO.TRB-0001 (A4.02, D,S 4-Sec 2.7/2.6)
f. [022] Perform 22 CFCU surveillance test IAW S2.0P-ST.CBV-0003 (A 1.04, D,EN,S 5 3.2/3.3)
g. [062] Transfer 4 KV Group Buses from SPT to APT IAW S2.0P-S0.4KV- A,D,P,S 6 0008 (A2.04, 3.1/3.4)
h. [008] Start 23 CCW Pump IAW 2-EOP-APPX-1 (A2.01, 3.3/3.6) A,E,EN,L,M,S 8 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. [064] Unload and shutdown 2C EDG IAW S2.0P-SO.DG-0003 (A2.04, D,R 6 2.7/3.0)
j. [012] Locally open Reactor Trip and Bypass Breakers IAW S2.0P-AB.CR- D,E,L 7 0001 Attachment 5 (A4.06, 4.3/4.3)
k. [068] Perform a radioactive liquid release and TCAF high radiation monitor A,D,R 9 alarm IAW S2.0P-SO.WL-0001 (A2.04, 3.3/3.3)
  • 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 Criteria for R /SR0-1/SRO-U I I I

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :5 9/:5 8/:5 4 (E)mergency or abnormal in-plant 2: 1/2: 1/2: 1 (EN)gineered safety feature 2: 1/2: 1/2: 1 (control room system)

(L )ow-Power/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/:5 3/:5 2 (randomly selected)

(R)CA 2: 1/2: 1/2: 1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Salem Date of Examination: 1/22/2018 Exam Level: RO D SRO-I l:2J SRO-U D Operating Test Number: 16-01 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function (KIA, Importance RO/SRO)

a. [001] TCAF a Loss of Control Rod Drive Vent Fan(s) (A2.01, 3.1/3.7) A,N,S 1
b. [004] Perform manual Makeup of the VCT JAW S2.0P-SO.CVC-0006 (A4.13, N,S 2 3.3/2.9)
c. [006] Isolate ECCS Accumulators IAW 2-EOP-TRIP-6 (A 1.13, 3.5/3.7) A,D,L,P,S 3
d. [002] Initiate Bleed and Feed using reactor head vents JAW 2-EOP-FRHS-1 A,D,E,L,P,S 4-Pri (A2.04, 4.3/4.6)
e. N/A
f. [022] Perform 22 CFCU surveillance test IAW S2.0P-ST.CBV-0003 (A 1.04, D,EN,S 5 3.2/3.3)
g. [062] Transfer 4 KV Group Buses from SPT to APT IAW S2.0P-S0.4KV- A,D,P,S 6 0008 (A2.04, 3.1/3.4)
h. [008] Start 23 CCW Pump JAW 2-EOP-APPX-1 (A2.01, 3.3/3.6) A,E,EN,L,M,S 8 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. [064] Unload and shutdown 2C EOG IAW S2.0P-SO.DG-0003 (A2.04, D,R 6 2.7/3.0) ..
j. [012] Locally open Reactor Trip and Bypass Breakers JAW S2.0P-AB.CR- D,E,L 7 0001 Attachment 5 (A4.06, 4.3/4.3)
k. [068] Perform a radioactive liquid release and TCAF high radiation monitor A,D,R 9 alarm JAW S2.0P-SO.WL-0001 (A2.04, 3.3/3.3)
  • 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 ~S-301-2 (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :5 9/:5 8/:5 4 (E)mergency or abnormal in-plant  :::1/:::1/:::1 (EN)gineered safety feature  ;::: 1/::: 1/::: 1 (control room system)

(L)ow-Power/Shutdown  :::1/:::1/:::1 (N)ew or (M)odified from bank including 1(A)  ;::: 2/::: 2/::: 1 (P)revious 2 exams :5 3/:5 3/:5 2 (randomly selected)

(R)CA  :::1/:::1/:::1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Salem Date of Examination: 1/22/2018 Exam Level: RO D SRO-I D SRO-U ~ Operating Test Number: 16-01 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function (KIA, Importance RO/SRO)

a. N/A
b. N/A
c. [006] Isolate ECCS Accumulators IAW 2-EOP-TRIP-6 (A1 .13, 3.5/3.7) A,D,L,P,S 3
d. N/A
e. N/A
f. [022] Perform 22 CFCU surveillance test IAW S2.0P-ST.CBV-0003 (A1 .04, D,EN,S 5 3.2/3.3)
g. N/A
h. [008] Start 23 CCW Pump IAW 2-EOP-APPX-1 (A2.01, 3.3/3.6) A,E,EN,L,M,S 8 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. [064] Unload and shutdown 2C EOG IAW S2.0P-SO.DG-0003 (A2.04, D,R 6 2.7/3.0)
j. [012] Locally open Reactor Trip and Bypass Breakers IAW S2.0P-AB.CR- D,E,L 7 0001 Attachment 5 (A4.06, 4.3/4.3)
k. N/A
  • 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 Criteria for R /SR0-1/SRO-U I I I (A}lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :5 9/$ 8/$ 4 (E)mergency or abnormal in-plant 2::1/2::1/2::1 (EN)gineered safety feature 2:: 1/2:: 1/2:: 1 (control room system)

(L)ow-Power/Shutdown 2::1/2::1/2::1 (N)ew or (M)odified from bank including 1(A)  ;;:: 2/2:: 2/2:: 1 (P)revious 2 exams  :;; 3/:5 3/:5 2 (randomly selected)

(R)CA 2::1/2::1/2::1 (S)imulator

AppendixD Scenario Outline Form ES-D-1 Facility: _ _Salem_ _ Scenario No.: _ 1 (ESG-1)_ _ Op-Test No.: _16-01_

Examiners: Operators:

Initial Conditions: IC-233; 4% power, BOL; 21 Charging Pump is running, 21 SGFP is in service, power ascension in progress at 10%/hr.

Turnover: The following equipment is out of service: 23 CV Pump is CIT to repair the fluid drive linkage. Crew is directed to continue raising Rx power to 10% and enter Mode 1 using Main Steam Dumps and Control Rods.

Critical Tasks:

1. Stop 22 RCP and close 22CV104 valve within 3-5 minutes after stopping the RCP (site specific CT).
2. Control initial RCS cooldown so that transition from EOP-SGTR-1 does not occur (see WOG CT-19).

Event Malf. No. Event Event No. Type* Description 1 N/A ALL (R) power ascension at 10% per hour RO (I) 2 PR0016A PZR pressure controlling channel fails high SRO (l,TS)

ALL (C) 3 SW0216A #2 SW bay leak (ramped over 2 minutes)

SRO (C,TS)

RO (C) 4 RC007B 22 RCP #1 seal degradation (ramped over 1 minute)

SRO (C) after the crew addresses the degraded 22 RCP seal; the #1 seal will 5 RC007B ALL (M) completely fail requiring a reactor trip 24 SG tube rupture will occur following transition into EOP-TRIP-2; 6 SG0078D ALL(C) crew will initiate SI and re-enter EOP-TRIP-1 PO (C) 7 VL0026 24BF13 fails to close on a SI/ Phase A signal SRO (C)

ABs AB.PZR-1 --> AB.SW-3--> AB.RCP-1 EOPs TRIP-1 --> TRIP-2--> TRIP-1 --> SGTR-1

  • (N)ormal, (R)eactivity, (l)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) 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 TRIP-1
5. EOPs entered/requiring substantive actions (1-2) 3 TRIP-2 SGTR-1
6. Entry into a contingency EOP with substantive actions ( 2: 1 per scenario set) 0 -
7. Preidentified critical tasks (e:2) 2 Site CT, CT-19
8. Tech Specs exercised (2: 2) 2 2,3

Appendix D Scenario Outline Form ES-D~1 Facility: _ _Salem ___ Scenario No.: _ 2 (ESG-2)_ _ Op-Test No.: _16-01_

Examiners: Operators:

Initial Conditions: IC-231; 40% power, BOL; 23 Charging Pump is running, power ascension is on hold due to turbine valve testing issues.

Turnover: The following equipment is out of service: 23 Condensate pump and all Heater Drain pumps due to power level, 22 SW Pump CIT for pump packing replacement, 23B CW pump is CIT for traveling screen repair, 2A EOG is CIT for governor inspection and output breaker swap.

Critical Tasks:

1. Manually actuate SI before transition to EOPs; LOCA-1, FRTS-1, or TRIP-2 (see WOG CT-2).
2. Transfer to cold leg recirculation before RWST level drops below 1.2 feet (see WOG CT-36).

Event Malf. No. Event Event No. Type* Description PO (I}

1 VL0420 21MS167 drifts from full open position SRO (I}

RO(C) 2 VC01738 22 Containment Fan Coil Unit (CFCU) trips SRO (C,TS)

RO (C) 3 RC0002 RCS leak inside containment (35 gpm ramped over 2 minutes)

SRO (C,TS) 4 N/A ALL (R) commence unit shutdown as a result RCS leakage exceeding TS limits after shutdown has commenced, 24 RC loop line breaks inside 5 RC0001D ALL (M) containment (Large Break LOCA) requiring a reactor trip and safety injection RP0274A both trains of SI fails to auto actuate and manual key switch operation RP02748 RO (I) 6 will fail to actuate on one train; the operator will be able to manually A501 SRO(I) actuate SI using the other train key switch.

A701 2B SEC fails to actuate on SI signal resulting in operators manually 7 DG02D ALL (I}

starting safeguards loads for 28 vital bus ABs AB.RC-1 _, AB.LOAD-1 EOPs TRIP-1 --> LOCA-1 -> LOCA-3

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 (ESG-2)

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) 2 6,7
3. Abnormal events (2-4) 3 1,2,3
4. Major transients ( 1-2) 1 5 TRIP-1
5. EOPs entered/requiring substantive actions (1-2) 3 LOCA-1 LOCA-3
6. Entry into a contingency EOP with substantive actions ( ::: 1 per 0 -

scenario set)

7. Preidentified critical tasks (:::2) 2 CT-2, CT-36
8. Tech Specs exercised (::: 2) 2 2,3

Appendix D Scenario Outline Form ES-D-1 Facility: _ _ Salem _ _ _ Scenario No.: _3(ESG-5)_ Op-Test No.: _ 16 Examiners: Operators:

Initial Conditions: IC-232; 88% power, MOL; 23 Charging Pump is running.

Turnover: The following equipment is out of service: 21 Safety Injection (SI) Pump err for motor lube, 21 AFW Pump err for motor replacement. Downpower to 88% just completed to support Main Turbine valve testing later in the shift.

Critical Tasks:

1. Close PZR PORV block valve by completion of Step 9 in EOP-TRIP-2 that directs closing of PZR block valves (see WOG CT-10).
2. Establish condensate flow to SGs before bleed and feed is required [2 SG WR levels < 32 % or 37%

Adverse] (see WOG CT-43).

Event Malf. No. Event Type* Event No. Description RO (I) 1 PR0017A PZR level controlling channel fails high SRO (l,TS)

RO (I) 2 RC0014B 22 RC loop RTD fails high SRO (l,TS) 3 BF0105A ALL (C) 21 SGFP trips PO (I) failure of Turbine Runback circuit following SGFP trip; operator can 4 EH0327 SRO (I) manually initiate load reduction.

5 N/A ALL (R) turbine load reduction to 66% as directed by AB.CN-0001 6 BF0105B ALL (M) 22 SGFP trips requiring manual reactor trip PO (C) 7 AF0181B 22 AFW pump trips following reactor trip SRO (C)

RO (C) after transition into EOP-TRIP-2, PZR PORV 2PR1 valve fails 8 VL0297 SRO (C) partially open; operator can manually close PZR PORV block valve PO (C) after 2PR1 issue is addressed; 23 AFW pump trips resulting in no 9 AF0183 SRO (C) AFW flow to any SGs ABs AB.CVC-1 ---> AB.ROD-3---> AB.CN-1 EOPs TRIP-1 ---> TRIP-2 ---> FRHS-1 ---> TRIP-2

. (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 3 (ESG-5)

Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 8 -
2. Malfunctions after EOP entry (1-2) 3 7,8,9
3. Abnormal events (2-4) 4 1,2,3,4
4. Major transients ( 1-2) 1 6
5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-2
6. Entry into a contingency EOP with substantive actions ( e:: 1 per 1 FRHS-1 scenario set)
7. Preidentified critical tasks (e::2) 2 CT-10, CT-43
8. Tech Specs exercised (e:: 2) 2 1,2

ES-401 PWR Examination Outline Form ES-401-2 Facilit)l: Salem Printed: 04/13/2017 Date Of Exam: 01/23/2018 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergenc, 2 0 0 0 0 0 0 0 2 2 4

& N/A NIA 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 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 2 2 l 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 KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 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 (IRs) 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.

PWR SRO Examination Outline Printed: 04/13/2017 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group I Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident/ X AA2.29 - The effects of bubble in 4.2 I 3 reactor vessel 000011 Large Break LOCA / 3 X 2.1.41- Knowledge of the refueling 3.7 1 process .

000054 Loss of Main Feedwater / 4 X 2.2.17 - Knowledge of the process for 3.8 I managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination woth the transmission system operator.

000058 Loss of DC Power/ 6 X AA2.01 - That a loss of de power has 4.1 1 occurred; verification that substitute power sources have come on line W/E05 Inadequate Heat Transfer - Loss of X EA2. l - Facility conditions and 4.4 1 Secondary Heat Sink/ 4 *.

selection of appropriate procedures during abnormal and emergency

  • . operations W/El 1 Loss of Emergency Coolant Recirc. / X 2.3.11 - Ability to control radiation 4.3 1 4 releases.

Kl A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 04/13/2017 11:38:25 am

PWR SRO Examination Outline Printed: 04/13/2017 Facility: Salem ES- 401 Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000028 Pressurizer Level Malfunction / 2 X AA2.12 - Cause for PZR level deviation 3.5 I alarm: controller malfunction or other instrumentation malfunction 000060 Accidental Gaseous Radwaste Rel. / X AA2.04 - The effects on the power plant 3.4* 1 9 of isolating a given radioactive-gas leak 000069 Loss of CTMT Integrity / 5 X 2.4.6 - Knowledge ofEOP mitigation 4.7 1 strategies.

W/E 16 High Containment Radiation / 9 X 2.1.14 - Knowledge of criteria or 3.1 1 conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

KIA Category Totals: 0 0 0 0 2 2 Group Point Total: 4 04/13/2017 11:38:30 am

PWR SRO Examination Outline Printed: 04/13/2017 Facility: Salem Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES - 401 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 006 Emergency Core Cooling X A2. l O- Low boron 3.9 1 concentration in SIS 007 Pressurizer Relief/Quench X A2.07 - Recirculating 2.6* 1 Tank quench tank 022 Containment Cooling X 2.1.5 - Ability to use 3.9 1 procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

073 Process Radiation Monitoring X A2.03 - Calibration drift 2.9* l 078 Instrument Air X 2.2.15 - Ability to determine 4.3 1 the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.

Kl A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 04/13/2017 11:38:36 am

PWR SRO Examination Outline Printed: 04/13/2017 Facility: Salem Plant Systems - Tier 2 I Group 2 Form ES-401-2 ES- 401 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 045 Main Turbine Generator X A2.12 - Control rod 2.8* l insertion limits exceeded (stabilize secondary) 068 Liquid Radwaste X 2.4.32 - Knowledge of 4.0 l operator response to loss of all annunciators.

079 Station Air X A2.0l - Cross-connection 3.2 l with IAS KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 04/13/2017 11:38:41am

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 04/13/2017 Facility: Salem Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.4 Knowledge of individual licensed operator 3.8 I responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

2.1.7 Ability to evaluate plant performance and make 4.7 1 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Category Total: 2 Equipment Control 2.2.25 Knowledge of the bases in Technical 4.2 1 Specifications for limiting conditions for operations and safety limits.

2.2.39 Knowledge of less than or equal to one hour 4.5 1 Technical Specification action statements for systems.

Category Total: 2 Radiation Control 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.

2.3.6 Ability to approve release permits. 3.8 1 Category Total: 2 Emergency Procedures/Plan 2.4.28 Knowledge of procedures relating to a security 4.1 1 event (non-safeguards information).

Category Total: I Generic Total: 7 04/13/2017 11:38:46 am

ES-401 PWR Examination Outline Form ES-401-2 Facilit)l: Salem Printed: 04/13/2017 Date Of Exam: 01/23/2018 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 .J 3 .J 3 3 3 18 0 0 0 Emergenc 1 2 2 2 I 2 I 1 9 0 0 0

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

Plant 2 1 1 1 l 0 1 l l 1 I 1 10 0 I 0 0 0 Systems Tier ,.,

4 3 4 4 2 3 4 4 3 .J 4 38 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 0 Abilities Categories ,.,

3 2 .J 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 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 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) 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 (!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,

!Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

04/13/2017 11 :25:41 am

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # I Name/ Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EK2.02 - Breakers, relays and 2.6 I Recovery/ 1 disconnects 000011 Large Break LOCA I 3 X EKI .01- Natural circulation and 4.1 I cooling, including reflux boiling 000015/000017 RCP Malfunctions / 4 X 2.2.42 - Ability to recognize system 3.9 l parameters that are entry-level conditions for Technical Specifications.

000022 Loss of Rx Coolant Makeup / 2 X AA2.0 l - Whether charging line leak 3.2 I exists 000025 Loss ofRHR System/ 4 X AK3.01 - Shift to alternate flowpath 3.1 l 000026 Loss of Component Cooling Water/ X AA2.0l - Location ofa leak in the 2.9 l 8 ccws 000027 Pressurizer Pressure Control System X AK2.03 - Controllers and positioners 2.6 l Malfunction I 3 000029 ATWS / 1 X EAl.07 - Operating switch for charging 3.4* l pump recirculation valve 000038 Steam Gen. Tube Rupture I 3 X EK3.07 - RCS loop isolation values 3.4* 1 000054 Loss of Main Feedwater / 4 X 2.3.11- Ability to control radiation 3.8 1 releases.

000055 Station Blackout/ 6 X EK3.02 - Actions contained in EOP for 4.3 1 loss of offsite and onsite power 000056 Loss of Off-site Power I 6 X AA2.54 - Breaker position (remote and 2.9 1 local) 000065 Loss of Instrument Air I 8 X 2.4.47 - Ability to diagnose and 4.2 1 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

000077 Generator Voltage and Electric Grid X AAl.02 - Turbine I generator controls 3.8 1 Disturbances I 6 W/E04 LOCA Outside Containment / 3 X EAl.2 - Operating behavior 3.6 l characteristics of the facility W/E05 Inadequate Heat Transfer - Loss of X EK2.2 - Facility's heat removal systems, 3.9 1 Secondary Heat Sink/ 4 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility WIE 11 Loss of Emergency Coolant Recirc. / X EKI.1 - Components, capacity, and 3.7 I 4 function of emergency systems W/El2 - Steam Line Rupture - Excessive X EK 1.1 - Components:, capacity, and 3.4 l Heat Transfer I 4 function of emergency systems 04/13/2017 11 :25:12 am

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier l / Group 1 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 04/13/2017 11:25:12 am 2

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / 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 I X 2.4.28- Knowledge of procedures .). I relating to a security event V tl~-' 7-i I }

(non-safeguards information).

000037 Steam Generator Tube Leak/ 3 X AAl.07 - eves letdown flow indicator 3.1 I 000076 High Reactor Coolant Activity/ 9 X AA2.02 - Corrective actions required 2.8 1 for high fission product activity in RCS W/E03 LOCA Cooldown - Depress./ 4 X EK2. l - Components, and functions of 3.6 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E06 Inad. Core Cooling/ 4 X EKl.3 - Annunciators and conditions 3.7 1 indicating signals, and remedial actions associated with the Degraded Core Cooling W/EI3 Steam Generator Over-pressure I 4 X EK2.2 - Facility's heat removal systems, 3.0 l 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/ 5 X EK3 .2 - Normal, abnormal and 3.1 1 emergency operating procedures associated with High Containment Pressure WIE 15 Containment Flooding/ 5 X EA 1.2 - Operating behavior 2.7 l characteristics of the facility W/El6 High Containment Radiation/ 9 X EKl.2 - Normal, abnormal and 2.7 1 emergency operating procedures associated with High Containment Radiation KIA Category Totals: 2 2 1 2 1 1 Group Point Total: 9 04/13/2017 11:25:19 am

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES - 401 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K3.0l - RCS 3.7 l 004 Chemical and Volume Control X K6.20 - Function of 2.5 I demineralizer, including boron loading and temperature limits 005 Residual Heat Removal X Kl.09-RCSO 3.6 1 006 Emergency Core Cooling X K6.05 - HPVLPI cooling 3.0 1 water 006 Emergency Core Cooling X A4.09 - PZR LCS and PZR 4.1 1 PCS 007 Pressurizer Relief/Quench X K4.01 - Quench tank 2.6 1 Tank cooling 008 Component Cooling Water X A2.04 - PRMS alann .

.) .) 1 010 Pressurizer Pressure Control X KS .0 l - Determination of 3.5 I condition of fluid in PZR, using steam tables 0 l O Pressurizer Pressure Control X A3.02 - PZR pressure 3.6 I 012 Reactor Protection X K4.05 - Spurious trip 2.7 1 protection 013 Engineered Safety Features X Kl.02 - RCP 3.2 l Actuation 022 Containment Cooling X A 1.03 - Containment 3.1 1 humidity 026 Containment Spray X 2.3.7 - Ability to comply 3.5 1 with radiation work pennit requirements during normal or abnormal conditions.

026 Containment Spray X K2.01 - Containment spray 3.4* 1 pumps 039 Main and Reheat Steam X 2.2.2 - Ability to manipulate 4.6 1 the console controls as required to operate the facility between shutdown and designated power levels.

039 Main and Reheat Steam X KS.01- Definition and 2.9 1 causes of steam/water hammer 059 Main Feedwater X A 1.03 - Power level 2.7* I restrictions for operation of MFW pumps and valves 061 Auxiliary/Emergency X A2.06 - Back leakage of 2.7 1 Feed water MFW 062 AC Electrical Distribution X Al.03 - Effect on 2.5 I instrumentation and controls of switching power supplies 063 DC Electrical Distribution X K2.01 - Major DC loads 2.9* 1 064 Emergency Diesel Generator X 2.4.43 - Knowledge of 3.2 I 04/13/2017 11:25:25 am

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points emergency communications systems and techniques.

064 Emergency Diesel Generator X K3 .02 - ESF AS controlled 4.2 I or actuated systems 073 Process Radiation Monitoring X K4.01- Release termination 4.0 l when radiation exceeds setpoint 076 Service Water X A2.02 - Service water 2.7 l header pressure 078 Instrument Air X K3 .0 1 - Containment air 3.1

  • I system 078 Instrument Air X A4.0 l - Pressure gauges 3.1 1 l 03 Containment X Kl.01 - CCS 3.6 l 103 Containment X A3.01- Containment 3.9 l isolation KIA Category Totals: 3 2 3 3 2 2 3 3 2 2 3 Group Point Total: 28 04/13/2017 11 :25:25 am 2

PWR RO Examination Outline Printed: 04/13/2017 Facility: Salem Plant Systems - Tier 2 / Group 2 Form ES-401-2 ES - 401 Sys/Evol #/Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 011 Pressurizer Level Contra l X K.2.01 - Charging pumps 3.1 1 014 Rod Position Indication X A4.03 - Primary coil voltage 2.6* 1 measurement 015 Nuclear Instrumentation X A3.05 - Recognition of 2.6 1 audio output expected for a given plant condition 029 Containment Purge X A2.01 - Maintenance or 2.9 1 other activity taking place inside containment 033 Spent Fuel Pool Cooling X K4.01- Maintenance of 2.9 1 spent fuel level 034 Fuel Handling Equipment X Al.02 - Water level in the 2.9 1 refueling canal 041 Steam Dump/Turbine Bypass X K6.03 - Controller and 2.7 1 Control positioners, including ICS, SIG, CRDS 055 Condenser Air Removal X K3.01 - Main condenser 2.5 1 056 Condensate X 2.2.23 - Ability to track 3.1 1 Technical Specification limiting conditions for operations.

068 Liquid Radwaste X *.

Kl.02 - Waste gas vent 2.5 1 header KIA Category Totals: 1 1 1 1 0 1 1 1 I 1 1 Group Point Total: 10 04/13/2017 11:25:30 am

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 04/13/2017 Facilitv: Salem Form ES-401-3 Generic Cate~orv KA Topic Conduct of Operations 2.1.18 Ability to make accurate, clear, and concise logs, 3.6 l records, status boards, and reports.

2.1.28 Knowledge of the purpose and function of major 4.1 I system components and controls.

2.1.43 Ability to use procedures to determine the effects 4.1 1 on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Category Total: 3 Equipment Control 2.2.21 Knowledge of pre- and post-maintenance 2.9 1 operability requirements.

2.2.38 Knowledge of conditions and limitations in the 3.6 I facility license.

Category Total: 2 Radiation Control 2.3.7 Ability to comply with radiation work permit 3.5 1 requirements during nonnal or abnormal conditions.

2.3.13 Knowledge of radiological safety procedures 3.4 1 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.

2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 3 Emergency Procedures/Plan 2.4.23 Knowledge of the bases for prioritizing 3.4 l emergency procedure implementation during emergency operations.

2.4.47 Ability to diagnose and recognize trends in an 4.2 l accurate and timely manner utilizing the appropriate control room reference material.

Category Total: 2 Generic Total: 10 04/13/2017 11:25:36 am

ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected K/A R056 029 Anticipated Kl A: Ability to operate and monitor the following as they apply to a Transient Without ATWS: Operating switch for charging pump recirculation valve 1/ 1 Scram (ATWS)-

CV139 & CV140 are the Charging Pump recirculation valves. EOP-EAl.07 FRSM-1 (RESPONSE TO NUCLEAR POWER GENERATION) makes no reference to these valves. Consequently, to write a question about operating the switches for these two valves in accordance with EOP-FRSM-1 is not possible.

Replaced with 029 Anticipated Transient Without Scram (ATWS)-

EAl.01 Ability to operate and monitor the following as they apply to a ATWS:

Charging pumps R057 EPE: 038 Steam KIA: Knowledge of the reasons for the following responses as the apply to Generator Tube the SGTR:RCS loop isolation values 1/1 Rupture (SGTR)-

EK3.07 Salem does not have the capability to isolate any RCS loops.

Consequently, the SGTR EOPs do not address this K/ A. Need to resample.

Replaced with 038 Steam Generator Tube Rupture (SGTR)-EK3.09 Knowledge of the reasons for the following responses as the apply to the SGTR: Criteria for securing/throttling ECCS R058 APE: 054 Loss of Kl A: Ability to control radiation releases Main Feedwater 1/1 (MFW)-G2.3.1 l S2.0P-AB.CN-0001 (MAIN FEEDWATER/CONDENSATE SYSTEM ABNORMALITY) does not have any guidance on controlling I monitoring radiation releases.

Replaced with 054 Loss of Main Feedwater (MFW)-G2.4.8 Knowledge of how abnormal operating procedures are used in conjunction withEOPs R067 APE: 024 Emergency KIA: Knowledge of procedures relating to a security event (non-safeguards Boration-G2.4.28 information).

1/2 There is no direct tie between Emergency Boration procedural guidance and security procedures.

Replaced with APE: 024 Emergency Boration -G2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects RO 13 026 Containment Kl A: Ability to comply with radiation work permit requirements during Spray System (CSS)- normal or abnormal conditions 2/1 G2.3.7 Complying with RWPs is a generic task that is not unique to Containment Spray. Any attempt to write a question relating RWP compliance and Containment Spray would be a "tack-on" Replaced with 026 Containment Spray System (CSS)-G2.1.27 Knowledge of system purpose and/or function.

ES-401 Record of Rejected K/As Form ES-401-4 RO 21 064 Emergency Kl A: Knowledge of emergency communications systems and techniques Diesel Generators 2/1 (ED/G)-G2.4.43 Emergency communication techniques are generic tasks that are not unique to EDGs. Any attempt to write a question relating Emergency communication techniques and EDGs would be a "tack-on" Replaced with 064 Emergency Diesel Generators (ED/G)-G2.2.22 Knowledge oflimiting conditions for operations and safety limits R030 014 Rod Position Kl A: Ability to manually operate and/or monitor in the control room:

Indication System Primary coil voltage measurement 2/2 (RPIS)-A4.03 Salem does not have the ability to operate and/or monitor RPIS primary coil voltage in the MCR Replaced with 014 Rod Position Indication System (RP1S)-A4.02 Ability to manually operate and/or monitor in the control room: Control rod mode-select switch R037 056 Condensate Kl A: Ability to track Technical Specification limiting conditions for System-G2.2.23 operations 2/2 The Condensate System does not have any safety function and there are no LCOs concerning the Condensate System.

Replaced with 056 Condensate System -G2.1.30 Ability to locate and operate components, including local controls SR02 EPE: 011 Large K/ A: Knowledge of the refueling process Break LOCA-G2.l.14 1/1 There is no direct tie between the LOCA Series EOPs and refueling. Any attempt to write a refueling question during a LOCA would be a "tack-on" Replaced with 011 Large Break LOCA -G2.l.2 Knowledge of operator responsibilities during all modes of plant operation SR03 APE: 054 Loss of Kl A: Knowledge of the process for managing maintenance activities Main Feedwater during power operations, such as risk assessments, work prioritization, and 1/1 (MFW)-G2.2. l 7 coordination with the transmission system operator There is no direct tie between the S2.0P-AB.CN-0001 (MAIN FEEDW ATER/CONDENSATE SYSTEM ABNORMALITY) and maintenance activities. Any attempt to write a maintenance I work control question during a Loss of Main Feedwater would be a "tack-on".

Replaced with 054 Loss of Main Feedwater (MFW)-G2.1.6 Ability to manage the control room crew during plant transients

ES-401 Record of Rejected K/As Form ES-401-4 SR04 APE: 058 Loss of DC KIA: Ability to determine and interpret the following as they apply to the Power-AA2.0 I Loss of DC Power: That a loss of de power has occurred; verification that III substitute power sources have come on line Salem does not an AB or EOP that deals with malfunctions within the DC power system. All malfunctions within the DC power system are addressed using Alarm Response Procedures. Additionally, the majority of ARPs are too similar to write a discerning question. "Check if a DC breaker is tripped and refer to Protective Circuit Breaker/ Breaker reset and reclosure policy. Initiate a notification to correct the cause of the alarm".

Need to resample including new procedure.

Replaced with 015/017 Reactor Coolant Pump (RCP) Malfunctions-AA2.10 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection SR06 W/El I Loss of Kl A: Ability to control radiation releases Emergency Coolant 1/1 Recirculation-G2.3. l l There is no direct tie between the EOP-LOCA-5 (LOSS OF EMERGENCY RECIRCULATION) and controlling radiation releases. In fact, EOP-LOCA-5 is trying to prevent core damage and minimizing radiation being released to the public.

Replaced with W/Ell Loss of Emergency Coolant Recirculation-G2.1.9 Ability to direct personnel activities inside the control room SRO IO W/El6 High Kl A: Knowledge of criteria or conditions that require plant-wide Containment announcements, such I as pump starts, reactor trips, mode changes, etc 1/2 Radiation-G2. l. l 4 There is no direct tie between the FRCE-3 (RESPONSE TO HIGH CONTAINMENT RADIATION) and making plant-wide announcements.

Any attempt to write a plant-wide announcement requirement question during implementation ofFRCE-3 would be a "tack-on". Need to resample.

Replaced with W/E16 High Containment Radiation-G2.4.1 Knowledge of EOP entry conditions and immediate action steps

ES-401 Record of Rejected K/As Form ES-401-4 SRO 13 022 Containment K/ A: Ability to use procedures related to shift staffing, such as minimum Cooling-G2. l .5 crew complement, overtime limitations, etc.

2/1 There is no direct tie between Containment Cooling System and the ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations. Any attempt to write a staffing question as related to containment cooling would be a "tack-on".

Additionally, different aspects of the CFCUs (which provide containment cooling) have been tested on R026, R027, R039, R040, R051 and R054. Testing another different aspect of the CFCUs at the SRO level seems to be an oversampling of containment cooling.

Need to resample including new system.

Replaced with 025 Containment Spray-G2.2.40 Ability to apply Technical Specifications for a system SRO 14 073 Process Radiation K/A: Ability to (a) predict the impacts of the following malfunctions or Monitoring (PRM) operations on the PRM system; and (b) based on those predictions, use 2/1 System-A2.03 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Calibration drift.

Unable to write a discerning question that complies with SRO-Only guidance of NUREG-1021. Operations Procedures concerning Radiation monitors address detector failure but really don't address calibration drift.

Need to resample.

073 Process Radiation Monitoring (PRM) System-A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure SRO 17 068 Liquid Radwaste K/A: Knowledge of operator response to loss of all annunciators.

System (LRS)-

2/2 A loss of all annunciators is a generic malfunction that is not specifically G2.4.32 related to the Liquid Radwaste System. Any attempt to write a loss of all annunciators question related to the Liquid Radwaste System would be a "tack-on".

Additionally, SRO Q8 and SRO Q24 are questions that have already been sampled on this exam that also relate to radiation releases. Writing a third SRO question concerning radiation released is an oversampling.

Need to resample including new system.

Replaced with 033 Spent Fuel Pool Cooling-G.2.1.20 Ability to interpret and execute procedure steps

ES-401 Record of Rejected K/As Form ES-401-4 SR023 G2.3.5 Kl A: Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring 3 equipment, etc ..

Throughout the entire RO and SRO exam, 7 questions have tested some type of fixed radiation monitor (RO 52, RO 75, RO 7, RO 23, SRO 8, SRO 24, and SRO 14). This is an over sampling resulting in not being able to develop an additional SRO question without overlap.

Need to resample to generic Emergency Procedures I Plan (2.4)

Replaced with G2.4.21 Knowledge of the parameters 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.

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