ML19036A826

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Draft Written Examination and Operating Test Outlines (Folder 2)
ML19036A826
Person / Time
Site: Salem  
(DPR-070, DPR-075)
Issue date: 01/14/2019
From: David Silk
Operations Branch I
To:
Public Service Enterprise Group
Shared Package
ML18081A982 List:
References
CAC 000956
Download: ML19036A826 (32)
v • d • e


Text

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

S:a. I e. INl Date of Examination:

J -l'i-201°1 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.

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b.

Assess whether the outline was systematically and randomly prepared in accordance with

/IA 1'J:i__

R Section 0.1 of ES-401 or ES-401 N and whether all KIA categories are appropriately sampled.

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T

c. Assess whether the outline overemphasizes any system:,, evolutions, or generic topics.

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T

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E

d. Assess whether the justifications for deselected or rejecti!d KIA statements are appropriate.

NA ~h N

2.
a.

Using Form ES-301-5, verify that the proposed scenario.3ets cover the required number of R ~

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

~

s transients.

I M

b.

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

mix of applicants in accordance with the expected crew composition and rotation schedule R ~ ~

L without compromising exam integrity, and ensure that each applicant can be tested using at A

least one new or significantly modified scenario, that r,o scenarios are duplicated from the T

applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

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

c.

-~

quantitative criteria specified on Form ES-301-4 and described in Appendix D and in e

~

Section 0.5, "Specific Instructions for the 'Simulator Operating Test,"' of ES-301 (including 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.

Jb__

A (2)

Task repetition from the last two NRC examinations is within the limlts specified on the form.

e. d L

(3)

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

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.

R. J l G

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

H (3)

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

c.

Determine whether there are enough different outlines to test the projected number and mix of R I~ ~

applicants and ensure that no items are duplicated on subsequent days.

4.
a. Assess whether plant-specific priorities (including probabilistic risk assessment and individual R. J r,pJ_.

plant examination insights) are covered in the appropriate exam sections.

G

~ A \\t)__

E

b. Assess whether the 1 O CFR 55.41, 55.43, and 55.45 sampling is appropriate.

N Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.

R. \\ !Ji E

C.

R

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

(<..,.,b*

A R.. J 4 L

e. Check the entire exam for balance of coverage.
f.

Assess whether the exam fits the appropriate job level (RO or SRO).

(<_,.},Di -

1cvclo lo \\!rt~\\-'!~a:e/~ ~

Date

a. Author 1-zJ-/8
b. Facility Reviewer(*)

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c. NRC's Chief Examiner (#)

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d. NRC Supervisor

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  • 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-201, Page 30 of 32

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

Salem Date of Examination:

1/14/2019 Examination Level: RO cgi 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 (: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 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 lZl 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-AA-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, oxvqen and :wdroqen)l Perform Borated Water Source Surveillance IAW S2.0P-ST.CVC-0010 Equipment Control R,D and evaluate Technical Specifications

[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-203 R,M

[2.3.4, SR0-3.7: Knowledge of radiation exposure limits under normal and emergency 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 (::: 3 for ROs; ::: 4 for SROs and RO retakes)

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

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

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

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 large 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 determined 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) Perform Borated Water Source Surveillance IAW S2.0P-ST.CVC-0010 and evaluate Technical Specifications:

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. The candidate will identify the applicable Tech Specs.

(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 authorizations for the additional exposure using RP-AA-203.

(SRO-A5) 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 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 O] 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 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 Boration IAW S1.0P-AB.CR-0001 (A4.18, 4.3/4.1)

D,E,R 2

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-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 s:~

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; S/:s; 4
1/;
:1/;::1
1/;
: 1/;:: 1 (control room system)
11;
:11;::1
2/;
: 2/;:: 1
s; 3/:S: 3/s 2 (randomly selected)
11;
:11;::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

[8J 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 O] Respond to PZR spray valve failing to close during depressurization in A,E,L,N,S 3

EOP-SGTR-1 v~2.02 3.9/3.9)

d. [002] Perforr., 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 (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 Boration IAW S1.OP-AB.CR-0001 (A4.18, 4.3/4.1)

D,E,R 2

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-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 I

4-6/4-6 /2-3

(

S 9/S 8/S 4

1/;
:1/;::1"
1/;
: 1/;:: 1 (control room system)
11;
:11;::1'
21;
:21;::1" s 3/S '3/s 2 (randomly selected)
11;
:'11;:: 1

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

Scenario No.:

_1 (ESG-1 ) __

Op-Test No.: _17-01_

Examiners:

Operators:

Initial Conditions: 4% power, SOL; 21 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 JAW 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 (l,TS) 3 SG0095A PO (I)

SRb (l,TS) 21 SG NR level fails low (TS only) 4 CN0094A PO (C) 21A Main Condenser tube leak SRO (C) 5 RC00068 ALL (M) 22 RCP motor oil leak requiring manual reactor trip SJ0312A 6

SJ0312B ALL (C)

RHR intersystem RCS leak on 22 RHR heat exchanger during EOP-RH02998 TRIP-2 RH03008 7

A701 RO (I)

One train of SI fails to manually actuate. Operator can actl,ate the A501 SRO (I) other train of SI from control room.

8 RP318S2 ROC) 22 Charging pump fails to start by 2C SEC. Operator can.manually SRO (!J start from control room.

9 VL0045 RO (I) 2CV116 and 2CV284 fail to close on Phase A isolation. Operators can VL0046 SRO (I) manually <..lose from control room.

ABs AB.PZR-*I --> AB.CW-1 --> AB.CHEM-1 --> AB.RCP-1 EOPs TRIP TRIP-2--> TRIP-1 --> LOCA-6--> LOCA-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) 8
2. Malfunctions after EOP entry (1-2) 4 6,7,8,9
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 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.:

_3 (ESG-3) __

Op-Test No.: _17-01_

Examiners:

Operators:

_Initial Conditions: 89.5% power, MOL; 23 Charging Pump is in serv'ce. The following equipment is out of service:

21 Charging pump CIT for oil cooler cleaning, 21A CW pump is err for waterbox cleaning, 21 BAT pump CIT for pump seal replacement, 22 vacuum pump err for pump replacement.

Turnover: Main turbine valve testing was completed last shift. Calo,*imetric 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 Malf. No.

Event Event No.

Type*

Description 1

N/A ALL (R)

Power ascension to 100% at 10% per hour 2

VC0311A RO (I)

Containment Pressure Channel fails high (TS only)

SRO (l,TS) 3 SJ0180B RO (I) 22 SI Accumulator gas leak (TS exercised)

SRO (l,TS) 4 CN0086B PO (C)

Loss of Main Condenser vacuum due to loose tube plug SRO (C) 5 N/A ALL (R)

Unit power reduction to stabilize condenser vacuum 6

RD050113 ALL(M)

Two dropped control rods requiring manual reactor trip.

RD050122 RP0058 RP0059A RO (I) 7 RP0059B SRO (I)

ATWS RP0060A RP0060B 8

RD0061 RO (I)

Rod Control speed controller fails at 8 spm in Auto. Operator can SRO (I) insert rods in Manual at 4B spm.

9 VL0095 PO (I) 2CV175 Rapid Boration valve fails to open in EOP-FRSM-1. Rapid SRO (I) borate via the RWST.

10 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--> TR.lf'-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-3)

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) 4 7,8,9,10
3. Abnormal events (2-4) 3 2,3,4
4. Major transients (1-2) 1 6
5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-1
6. Entry into a contingency EOP with substantive actions ( ::::: 1 per 1

FRSM-1 scenario set)

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

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

Scenario No.:

_5 (ESG-5) __

Op-Test No.: _17-01_

Examiners:

Operators:

Initial Conditions: 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

PR00188 RO (I) 2PR2 PZR PORV leaks (TS exercised)

SRO (l,TS) 2 N10193A RO (I) 2N41 Power Range channel fails high (TS exercised)

SRO (l,TS) 3 BF0105A RO (I) 21 SGFP trips om high exhaust hood temp SRO (I) 4 EH0327 ALL (C)

Failure of Turbine Runback following SGFP trip. Operator can manually initiate runback froni control room.

5 NIA ALL (R)

Load reduction to 66% power per AB.CN-0001 6

TU0066 ALL (M)

Inadvertent Main Turbine trip signal 7

RP0058 RO (I)

Reactor fails to auto trip. Operator can manually trip the reactor from RP00598 SRO (I) control room..

8 EL0145 PO (I)

Loss of 28 4K Vital Bus (loss of 22 AFW pump)

SRO (I) 9 AF0353C PO (C) 23 AFW pump fails to auto start. Operator can manually start, but will AF0183 SRO (C) trip shortly after time delay. (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, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-0-1 Scenario No.: 5 (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-1
6. Entry into a contingency EOP with substantive actions (.: 1 per 1

FRHS-1 scenario set)

7. Pre identified critical tasks (.:2) 2 CT-1, CT-43
8. Tech Specs exercised(.: 2) 2 1,2

Es-401, Rev. 11 PWR Examination Outline Form Es-401-2 Facility:

Date of Exam:

RO KIA 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&

2 1

1 2

2 2

1 9

2 2

4 Abnormal Plant NIA NIA Evolutlons Tier Totals 3

5 5

5 5

4 27 5

5 10 I

I I

I 1

2 2

2 3

3 2

3 3

2 3

3 28 3

2 5

2.

I I

I I

I Plant 2

1 1

0 1

1 1

1 1

1 1

1 10 2

1 3

Systems I

I I

I I

Tier Totals 3

3 2

4 4

3 4

4 3

4 4

38 3

8

3. Generic Knowledge and Abilities 1

2 3

4 10 1 I 2 3 I 4 7

Categories I

I 3

2 2

3 1

2 2

2

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, 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 KIA 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 KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution In the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an Importance rating (IR) of 2.5 or higher shall be selected.

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) KIAs In Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1.b of ES-401 for the applicable KAs.
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; lffuel 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, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs 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~DDDDDDDDD

/ 1 008AK2.03 Pressurizer Vapor Space Accident I 3 2.5 2.4 D~DDDDDDDDD 009EK2.03 Small Break LOCA I 3 3

3.3 D~DDDDDDDDD 011EK2.02 Large Break LOCA I 3 2.6 2.7 DQ9DDDDDDDDD 015AK1.04 RCP Malfunctions I 4 2.9 3.1 ~DDDDDDDDDD 022AA1.08 Loss of Rx Coolant Makeup I 2 3.4 3.3 DDDDDD~DDDD 026AA1.07 Loss of Component Cooling Water I 8 2.9 3

DDDDDD~DDDD 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 I 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 VCTlevel 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 KA NAME / SAFETY FUNCTION:

062AA2.02 Loss of Nuclear Svc Water / 4 065AK3.04 Loss of Instrument Air/ 8 077AG2.4.34 Generator Voltage and Electric Grid Disturbances I 6 WE04EK3.4 LOCA Outside Containment I 3 WE05EK1.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 WE11EA1.3 Loss of Emergency Coolant Recirc. / 4 WE12EK3.3 Steam Line Rupture - Excessive Heat Transfer/ 4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.9 3.6 DDDDDDD~DDD 3

3.2 DD~DDDDDDDD 4.2 4.1 D D D D D D D D D D ~

3.6 3.8 D D ~ D D D D D D D D 3.9 4.1 ~DDDDDDDDDD 3.7 4.2 DDDDDD~DDDD 3.5 3.7 DD~DDDDDDDD Page2 of 2 FORM ES-401-2 TOPIC:

The cause of possible SWS loss Cross-over to backup air supplies Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 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.

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink}.

Desired operating results during abnormal and emergency situations.

Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

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 I 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 IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.3 3.1 D D D D D D ~ D D D D 2.9 3.6 D D ~ D D D D D D D D 2.9 3.3

~ D D D D D D D D D D 3.9 4.1 D D D D D D D ~ D D D 4.1 4.3 D D D D D D D ~ D D D 4.2 4.2 D D D D D D ~ D D D D 3.7 4.o D ~ D D D D D D D D D 3.4 3.9 D D ~ D D D D D D D D 3.9 3.8 D D D D D D D D D D ~

Page 1 of 1 FORM ES-401-2 TOPIC:

RPI Interlocks associated with fuel handling equipment Use of steam tables Conditions requiring reactor and/or turbine trip RCS pressure ECCS valve control switches and indicators 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 K5 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~DDDD ODD 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 FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 013K2.01 Engineered Safety Features Actuation 3.6 3.8 D~DDDDDDDDD ESFAS/safeguards equipment control 022K2.01 Containment Cooling 3.0 3.1 D~DDDDDDDDD Containment cooling fans 026A4.05 Containment Spray 3.5 3.5 DDDDDDDDD~D Containment spray reset switches 02682.4.20 Containment Spray 3.8 4.3 DOD DDDDDD~

Knowledge of operational implications of EOP warnings, cautions and notes.

039A4.04 Main and Reheat Steam 3.8 3.9 DDDDDDDDD~D Emergency feedwater pump turbines 059A2.06 Main Feedwater 2.7 2.9 DDDDDDD~DDD Loss of steam flow to MFW system 059K4.05 Main Feedwater 2.5 2.8 DDD~DDDDDDD Control of speed of MFW pump turbine 061K2.03 Auxiliary/Emergency Feedwater 4.0 3.8 D~DDDDDDDDD AFW diesel driven pump 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 DDDDD~DDDDD Pumps 062K3.01 AC Electrical Distribution 3.5 3.9 DD~DDDDDDDD Major system loads 063A1.01 DC Electrical Distribution 2.5 3.3 DDDDDD~DDDD Battery capacity as it is affected by discharge rate Page 2 of 3 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 063G2.2.44 DC Electrical Distribution 4.2 4.4 DDDDDDDDDD~

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 064A1.05 Emergency Diesel Generator 2.5 2.5 DDDDDD~DDDD ED/G room temperature 073A4.01 Process Radiation Monitoring 3.9 3.9 DDDDDDDDD~D Effluent release 076K4.03 Service Water 2.9 3.4 DDD~DDDDDDD Automatic opening features associated with SWS isolation valves to CCW heat exchanges 078G2.2.38 Instrument Air 3.6 4.5 DDDDDDDDDD~

Knowledge of conditions and limitations in the facility license.

103K4.04 Containment 2.5 3.2 DD

~DDDDDDD Personnel access hatch and emergency access hatch Page 3 of 3 04/30/2018 9:18 AM

ES-401, REV 11 T2G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 001K4.05 ControlRodDrive 3.9 3.9 DD D ~DD DD DD D 015A4.03 Nuclear Instrumentation 3.8 3.9 D D D D D D D D D ~ D 016K1.06 Non-nuclear Instrumentation 3.6 3.5

~ D D D D D D D D D D 028K5.04 Hydrogen Recombiner and Purge 2.6 3.2 D D D D ~ D D D D D D Control 034K6.02 Fuel Handling Equipment 2.6 3.3 D D D D D ~ D D D D D 041K2.01 Steam DumpfTurbine Bypass Control 2.8 2.9 D ~ D D D D D D D D D 071A3.01 Waste Gas Disposal 2.6 2.7 D D D D D D D D ~ D D 072G2.4.31 Area Radiation Monitoring 4.2 4.1 D D D D D D D D D D ~

075A2.01 Circulating Water 3.o 3.2 D D D D D D D ~ D D D 086A1.05 Fire Protection 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 AFWsystem The selective removal of hydrogen Radiation monitoring systems ICS, normal and alternate power supply HRPS Knowledge of annunciator alarms, indications, or response procedures.

Loss of intake structure FPS lineups 04/30/2018 9:19 AM

ES-401, REV 11 T3 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 G2.1.15 Conduct of operations 2.7 3.4 DDDDDDDDDD~

Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

G2.1.28 Conduct of operations 4.1 4.1 DDDDDDDDDD~

Knowledge of the purpose and function of major system components and controls.

G2.2.20 Equipment Control 2.6 3.8 DDDDDDDDDD~

Knowledge of the process for managing troubleshooting activities.

G2.2.25 Equipment Control 3.2 4.2 DDDDDDDDDD~

Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.3.11 Radiation Control 3.8 4.3 DDDDDDDDDD~

Ability to control radiation releases.

G2.3.12 Radiation Control 3.2 3.7 DDDDDDDDDD~

Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.13 Radiation Control 3.4 3.8 DDDDDDDDDD~

Knowledge of radiological safety procedures pertaining to licensed operator duties G2.4.22 Emergency Procedures/Plans 3.6 4.4 DDDDDDDDDD~

Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

G2.4.3 Emergency Procedures/Plans 3.7 3.9 DDDDDDDDDD~

Ability to identify post-accident instrumentation.

G2.4.11 Emergency Procedures/Plans 4.0 4.2 DDDDDDDDDD~

Knowledge of abnormal condition procedures.

Page 1 of 1 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 I 3 3.6 4.3 D D D D D D D ~ D D D 011 EG2.1.27 Large Break LOCA / 3 3.9 4

DDDDDDDDDD~

025AG2.1.27 Loss of RHR System I 4 3.9 4

DDDDDDDDDD~

056AA2.22 Loss of Off-site Power / 6 3.4 3.6 D D D D D D D ~ D D D 065AG2.2.36 Loss of Instrument Air/ 8 3.1 4.2 D D D D D D D D D D ~

WE04EA2.1 LOCA Outside Containment/ 3 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 function.

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 maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 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:

028AA2.14 Pressurizer Level Malfunction / 2 068AG2.4.50 Control Room Evac. / 8 076AA2.04 High Reactor Coolant Activity / 9 we1 OEG2.4.46 Natural Circ. With Seam Void/ 4 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.6 2.8 D D D D D D D ~ D D D 4.2 4.o D D D D D D D D D D ~

2.6 3

DDDDDDD~DDD 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 PZR levels, given a change in ambient pressure and temperature of reflux boiling Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Process effluent radiation chart recorder 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 DDDDDDDDDD~

2.3 2.8 DDDDDDD~DDD 3.6 3.9 DDDDDDD~DDD 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 028A2.03 NAME / SAFETY FUNCTION:

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 DD D DD DD~

DD 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 1/ 1 Transient Without identified in the alarm response manual 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-0001(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 Kl A: Knowledge of the operational implications of EOP warnings, 2 I 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. l.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 /1 Emergency Feedwater 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 KIA: Ability to analyze the effect of maintenance activities, such as Instrument Air -

degraded power sources, on the status of limiting conditions for 1/ 1 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 Level Control Pressurizer Level Control Malfunctions: The effect on indicated PZR 1 / 2 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-0001(LOSS OF CHARGING). S2.0P-AB.CVC-0001 only deals with a failure ofa PZR level channel. No mention of Reflux Boiling is mentioned in S2.0P-AB.CVC-0001.

Additionally, S2.0P-AB.RHR-0001(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 K/ 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 (K/ A: G2.3.11 Ability to control radiation releases)

Replaced With AA2.03 RCS radioactivity level meter

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