ML20300A584

Wb 2020301 Exam Final Items - Delayed Release - File 2A-2

ML20300A584
Person / Time
Site:	Watts Bar
Issue date:	10/26/2020
From:	NRC/RGN-II
To:
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Download: ML20300A584 (553)

Text

ML20300A584 Watts Bar Nuclear Plant NRC EXAM 2020301 Scenario 1

[Page 1 of 109]

Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No. 1 Op Test No.: 2020-301 Examiners: Operators: SRO RO BOP Run Time: 90 to 120 minutes Initial Conditions: Unit 1 is in MODE 1 at 100% power.

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal).

Unit 2 is at 100% power.

Turnover: Maintain 100% power Event Malf. No. Event Type* Event Description No.

1 cv22a I-RO 1-FT-62-93A, CHARGING FLOW transmitter fails HIGH.

2 rx11a I-RO 1-PT-1-73, IMPULSE PRESS transmitter fails LOW.

TS-SRO 3 rd07b R-RO A single RCCA (C-5) drops into the core.

N-BOP TS-SRO 4 rp01c M-All Turbine Trip (ATWS) tc09 5 Override C-RO Rods Fail to Insert in AUTO 6 ms16d C-BOP SG4 PORV fails OPEN

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2020-301 Watts Bar NRC Examination [Page 2 of 109]

Appendix D Scenario Outline Form ES-D-1 Scenario 1 - Summary Event Description 1 1-FT-62-93A, CHARGING FLOW transmitter fails HIGH. The crew will enter 1-AOI-20, Malfunction of Pressurizer Level Control System where the RO will be directed to take manual control of 1-HIC-62-93 and restore Pzr level to normal.

2 1-PT-1-73, IMPULSE PRESS transmitter fails LOW. Crew enters 1-AOI-2, Malfunction of Reactor Control System. Operator will bypass the failed input. SRO will refer to TS 3.3.1, RTS Instrumentation.

3 A single RCCA drops into the core. The RO places control rods in MANUAL per immediate action of 1-AOI-2, Malfunction of Reactor Control System, Section 3.5, Dropped RCCA. The crew will stabilize the unit and then reduce reactor power to < 75% IAW 1-AOI-39, Rapid Load Reduction. SRO will refer to TS 3.1.5, Rod Gp Alignment Limits.

4 The Main Turbine will trip. Applicants recognize that the reactor failed to trip automatically and attempt to manually trip the reactor. The reactor fails to trip. The crew enters 1-E-0, Reactor Trip or Safety Injection, then transitions to 1-FR-S.1.

5 The RO may place Control Rods in AUTO which will fail to insert. The RO should recognize this failure and return the Control Rods to MAN and insert them manually.

6 After an operator is dispatched to open reactor trip breakers (~ 20 sec), SG 4 PORV will fail OPEN resulting in lowering RCS temperature. Direction to ENSURE SG PORVs are closed is provided in 1-E-0 (and 1-ES-0.1 if SI does not actuate) prior to determining if transitioning to 1-E-2 is required.

2020-301 Watts Bar NRC Examination [Page 3 of 109]

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Critical Tasks Critical Description Task 1 Insert CRs prior to reactor trip breakers being opened (~ 5 minutes after event actuation).

2 Isolate the steam leak (manually close the open SG PORV) prior to SI Actuation on low RCS Pressure (1870 psig).

References Number Title Revision 1-AOI-20 Malfunction of Pressurizer Level Control System 9 1-AOI-2 Malfunction of Reactor Control System 13 1-AOI-39 Rapid Load Reduction 7 1-E-0 Reactor Trip or Safety Injection 16 1-FR-S.1 Nuclear Power Generation / ATWS 2 1-ES-0.1 Reactor Trip Response 2 2020-301 Watts Bar NRC Examination [Page 4 of109]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 5 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 1: CHARGING FLOW 1. CHARGING FLOW HI/LO in alarm M5 Window 108-A transmitter fails HIGH. 2. RCP SEAL SUPPLY FLOW LO in alarm M5 Window 101-E

3. REGEN HX LTDN TEMP HI in alarm M6 Window 110-A Crew should recognize low charging flow resulting from the 4. Charging flow lowering transmitter failing high and enter 1-AOI-20. 5. Pzr level lowering

6. 1-FCV-62-93, CHRG FLOW PZR LEVEL CONTROL traveling No DCS alarms occur on this event. closed SRO Directs entry into 1-AOI-20, Malfunction of Pressurizer Level Control System.

1-AOI-20 SRO SRO determines that 1-FCV-62-93 is responding to a transmitter failure and proceeds to section 3.2.

If it is not recognized that an instrument failure has occurred, the SRO may decide to proceed to Section 3.3.

Section 3.3 starts on page 13.

1-AOI-20, Section 3.2 Operator can dispatch operator to verify flow on 1-FI RO 93C.

BOOTH OPERATOR: If dispatched, report level from 1-FI-62-93C.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 6 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.2 RO It is determined that Auto Control is impacted. Proceeds to step 5.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 7 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 8 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-AOI-20, Section 3.2

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 9 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.2 SRO evaluates Tech Specs: SRO TS 3.3.1 LCO is met.

TS 3.3.3 LCO is met.

TS 3.4.8 LCO is met.

BOOTH OPERATOR: As Work Control, acknowledge request to remove failed channel from service and initiate repairs. RO BOOTH OPERATOR: As maintenance, acknowledge request to initiate repairs.

Attachment 1 starts on page 10.

When TS are addressed or at the discretion of the lead examiner, proceed with Event 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 10 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 11 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 12 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 13 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 14 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 15 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 16 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 17 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 18 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 19 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 20 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 21 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 22 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 23 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 24 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 25 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 26 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 27 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 28 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 29 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 30 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 1 Page 31 of 109 Event

Description:

1-FT-62-93A, CHARGING FLOW transmitter fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 SRO RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 32 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew observes the following; Examiner, insert Event 2: 1-PT-1-73, IMPULSE LO TURB IMPULSE PRESS ROD BLOCK in alarm M4 PRESS transmitter fails LOW. Window 66-A SRO Directs RO to address alarm.

RO informs SRO to refer to 1-AOI-2.

SRO Announces entry into 1-AOI-2.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 33 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Malfunction of Reactor Control System SRO SRO determines that Section 3.2 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 34 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 35 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 36 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 37 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO RO should recognize that 1-PT-1-73 has failed.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 38 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 39 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO BOOTH OPERATOR: As maintenance, acknowledge request for repairs.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 40 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 2 Page 41 of 109 Event

Description:

1-PT-1-73, IMPULSE PRESS transmitter fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.2 SRO evaluates Tech Specs:

TS 3.1.1 LCO is met TS 3.1.5 LCO is met TS 3.1.6 LCO is met TS 3.1.7 LCO is met RO TS 3.2.1 LCO is met TS 3.2.2 LCO is met TS 3.2.4 LCO is met TS 3.2.3 LCO is met TS 3.3.1 Condition A: Enter condition ref. in Tbl 3.3.1-1 immediately.

16.f: Condition S: Verify Intlk is in required state

a. (P-13, Window 70-E Dark)

< 1 hr OR Be in Mode 2 < 7 hr.

TS 3.3.2 LCO is met TS 3.3.3 LCO is met When TS are addressed, or at the discretion of the lead examiner, proceed to Event 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 42 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 3: RCCA drops into the Rod Position Indication displays one control rod fully core.

inserted RODS AT BOTTOM in alarm M4 Window 87-D PZR PRESS LO-DEVN BACKUP HTRS ON in alarm M5 Window 90-B POWER RANGE UPR DETECTOR FLUX DEVN in alarm M4 Window 83-B POWER RANGE LWR DETECTOR FLUX DEVN in alarm M4 Window 83-C POWER RANGE CHANNEL DEVIATION in alarm M4 Window 83-E CERPI TROUBLE in alarm M4 Window 86-C RO may place control rods in MANUAL as an 1-AOI-2 SRO Direct entry into 1-AOI-2, malfunction of Reactor Control System.

Immediate Action Step.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 43 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2 SRO determines that section 3.3 is applicable.

SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 44 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.3 RO RO may have already placed CRs in MANUAL.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 45 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.3 RO BOOTH OPERATOR: As Reactor Engineering, acknowledge the request to evaluate.

As STA, acknowledge request to perform 1-SI-0-21.

As AUO, if dispatched to rod control cabinet to investigate, acknowledge the request.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 46 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.3 SRO evaluates Tech Specs: SRO TS 3.1.5 Condition B: Verify SDM < COLR limit < 1 hr OR Initiate Boration < 1 hr AND Reduce Pwr to < 75% RTP < 2 hr AND Verify SDM within limits 1/every 12 hr AND Perform SR 3.2.1.1, 3.2.1.2, 3.2.2.1 AND Re-Evaluate safety analysis.

TS 3.4.1 Condition A. Restore RCS press > 2214 psig

< 2hr.

BOOTH OPERATOR: As Maintenance, acknowledge request to initiate repairs.

RO As ODM, acknowledge notification of dropped RCCA.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 47 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-2, Section 3.3 RO SRO direct power reduction to < 75%.

(May use 1-AOI-39, Rapid Load Reduction)

BOOTH OPERATOR: As Reactor Engineering, acknowledge the request to provide a retrieval rate.

When power is < 75% or at the discretion of the lead examiner, proceed to Event 4.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 48 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, RAPID LOAD REDUCTION SRO SRO determines that Section 3.2 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 49 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 50 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 51 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 52 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 53 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 3 Page 54 of 109 Event

Description:

A single RCCA (C-5) drops into the core Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 As Chemistry, acknowledge notification of power RO change.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 55 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 4,5,6: Turbine Trip, ATWS, Main Turbine Trip SG 4 PORV opens when reactor trips.

Reactor Failed to trip SRO Direct tripping the reactor and performing 1-E-0, Reactor Trip or Safety Injection.

RO determines that the reactor will not automatically trip or RO 1-E-0 manually trip from the Control Room. Informs SRO of ATWS condition.

SRO Announce transferring to 1-FR-S.1, Nuclear Power Generation /

ATWS.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 56 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 CRITICAL TASK 1: Insert CRs prior to reactor trip breakers being opened RO/BOP SRO may direct dispatching AUOs to open reactor trip / MG set breakers early in FR-S.1.

Automatic Rod insertion does not work. Requires manual rod insertion.

Operator will start AFW pumps.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 57 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 58 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 59 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 BOOTH OPERATOR: As AUO, acknowledge request to open Reactor Trip Breakers and MG Set RO/BOP Output Breakers then activate Event 5 to:

Fail SG 4 PORV open in ~ 20 seconds.

RT breakers to open in ~ 3 minutes.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 60 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 61 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 62 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 63 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 64 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 65 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 66 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 67 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 68 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-FR-S.1 RO/BOP SRO SRO announces returning to E-0.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 69 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 70 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 71 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO If SI is not actuated, the crew will proceed to 1-ES-0.1, Reactor Trip Response. (Page 91)

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 72 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO Appendix A starts on Page 78.

Appendix B starts on Page 90.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 73 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-E-0 RO should identify and manually close SG 4 PORV by this time.

CRITICAL TASK 2: Isolate the steam leak (manually close the open SG PORV) prior to SI Actuation on low RCS Pressure (1870 psig).

Scenario can be terminated when Critical Tasks are complete or at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 74 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 75 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 76 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 77 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-E-0

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 78 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 79 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 80 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 81 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 82 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 83 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 84 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 85 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 86 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 87 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 88 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 89 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 90 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix B RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 91 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 92 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO CRITICAL TASK 2: Isolate the steam leak (manually close the open SG PORV) prior to SI Actuation on low RCS Pressure (1870 psig).

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 93 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 94 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 95 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 96 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 97 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 98 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 99 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 100 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 101 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 102 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 103 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 104 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 105 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 1 Event # 4,5,6 Page 106 of 109 Turbine Trip Event

Description:

ATWS SG4 PORV fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-0.1 RO Scenario can be terminated when Critical Tasks are complete or at the discretion of the lead examiner.

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 1 Simulator Console Operators Instructions

1. SIMULATOR SET UP

a. ENSURE exam security is established.

b. LOAD IC 346.

c. LOAD schedule file for 2020-301 NRC Examination Scenario 1.

d. ENSURE the following are BYPASSED in DCS:

1) 1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance.

e. ENSURE DCS workstations are in Initial environment

f. ENSURE ICS Screens are clear

g. ENSURE ICS alarms are acknowledged

h. ENSURE correct AUO cards are available to US, OAC and BOP.

i. ENSURE ALL operator aids NOT required for the scenario are removed from the boards.

j. ENSURE ALL recorders are clear.

k. PLACE simulator in RUN until alarm 82-F, DCS Trouble, clears.

NOTE: IF desired, THEN Simulator may be placed in FREEZE until prompted by NRC CHIEF EXAMINER to return to RUN.

l. ENSURE ALL ARIs are clear of all writing.

m. IF the first scenario of the day THEN ENSURE:

1) ALL EOIs are clear of all writing

2) ALL AOIs are clear of all writing

3) ALL ECAs are clear of all writing

4) ALL FRs are clear of all writing

5) ALL Tech Specs are clear of all writing

6) ALL back-up copies are clear of all writing

n. IF NOT the first scenario of the day THEN ENSURE the following procedures to be used are not written on:

1) 1-AOI-20

2) 1-AOI-2

3) 1-AOI-39

4) 1-FR-S.1

5) 1-E-0

6) 1-ES-0.1 2020-301 Watts Bar NRC Examination [Page 107 of 109]

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 1 Simulator Console Operators Instructions

2. GENERIC SCENARIO NOTES

a. Typical Response Times: Unless specified in the SEG or determined by the NRC CHIEF EXAMINER, the response time of AUOs or other personnel dispatched should be approximately 3 to 5 min.

b. Plant Data or Information Requests: Information not contained in this exam guide should be discussed with the NRC CHIEF EXAMINER before providing any information to the crew.

c. General Notifications: If not specifically addressed in the SEG, general notifications to Operations Management, Shift Manager, Load Coordinator, Plant Duty Manager, etc. will be acknowledged by the Console Operator.

3. TURNOVER INFORMATION a) Provide Crew with the following information:

Shift Turnover sheet with current Unit Status.

2020-301 Watts Bar NRC Examination [Page 108 of 109]

SHIFT TURNOVER CHECKLIST SM US Unit 1 UO Unit 2 Off-going - Name AUO Station WBN STA On-coming - Name Part 1 - Completed by off-going shift / Reviewed by on-coming shift:

Abnormal equipment lineup / conditions:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal).

SIs/Tests in progress / planned: (including need for conduct of evolution briefings)

None Major Activities / Procedures in progress or planned:

None Plant Risk: Green. Grid: Qualified.

Unit 2 is in MODE 1 at 100% power.

Radiological changes during the shift:

None Part 2 - Completed by on-coming shift prior to assuming duties:

Review station rounds /Abnormal readings (AUOs only)

Review Narrative Logs (previous day and carry-over items)

Current qualification status Leadership and Team Effectiveness applicability Review the current controlling Reactivity Management Plans (N/A for AUOs)

Review current TS/TRM/ODCM/FPR Required Actions (N/A for AUOs)

Walk down MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM /STA)

CR reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:___________

Part 3 - Completed by on-coming shift. These items may be reviewed after assuming duties:

Review Operator Workarounds, Burdens and Challenges (applicable Unit / Station)

Review applicable ODMI actions (first shift of shift week)

Review changes in Standing / Shift Orders (since last shift worked)

Review changes to TACFs issued (since last shift worked) (N/A for AUOs)

Review Control Room Deficiencies (first shift of shift week) (N/A for AUOs)

Review Component Deviation Log (N/A for AUOs)

TVA 40741

Watts Bar Nuclear Plant NRC EXAM 2020301 Scenario 2

[Page 1 of 66]

Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No. 2 Op Test No.: 2020-301 Examiners: Operators: SRO RO BOP Run Time: 90 to 120 minutes Initial Conditions: Unit 1 is in MODE 2 at 3% power 1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal)

Unit 2 is at 100% power Turnover: Continue with the startup. Raise power to 14%.

Event Malf. No. Event Type* Event Description No.

1 mux_14c003 I-RO IR N35 fails LOW ni04a TS-SRO nin135ds209

-1 2 R-RO Operator raises power to 14%.

3 rc08b C-RO Loop 2 Pressurizer Spray valve fails OPEN.

TS-SRO 4 cv11 I-RO/SRO 1-LT-62-129, VCT Level, fails HIGH.

5 th02b M - ALL LB LOCA 6 si09l C-BOP When the SI is actuated, both SI pumps fail to start si09m automatically.

7 rh12 C-RO 1-FCV-63-72 and 1-FCV-63-73, Containment Sump Valves, rh09 fail to OPEN automatically when RWST level reaches 34%.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2020-301 Watts Bar NRC Examination [Page 2 of 66]

Appendix D Scenario Outline Form ES-D-1 Scenario 2 - Summary Event Description 1 IR N35 fails LOW which requires entry into 1-AOI-4, Nuclear Instrumentation Malfunctions.

TS 3.3.1, Reactor Trip System (RTS) Instrumentation will be reviewed by the SRO which will direct the crew to raise power to > 10% within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2 Turnover directs crew to raise power to 14% in accordance with 1-GO-3, Unit S/U from <

4% to 30% in preparation for rolling the Main Turbine.

3 Loop 2 Pressurizer Spray valve fails OPEN requiring entry into 1-AOI-18, Malfunction of Pressurizer Pressure Control System where they will be directed to take manual control of the spray valve. The operator may place the controller in MANUAL prior to AOI entry as it is an Immediate Action. SRO will refer to TS 3.4.1, DNB.

4 1-LT-62-129, VCT Level, fails HIGH causing Letdown to divert to Holdup Tank (HUT) A which causes actual VCT level to lower (suction source for in-service CCP). OAC will position 1-HS-62-118A, LETDOWN DIVERT TO HUT, to VCT position IAW ARI 109-A, and bypass the failed transmitter in DCS. US will evaluate Fire Protection Report.

5 A Large Break LOCA occurs. Crew will perform 1-E-0, Reactor Trip or Safety Injection and then transition to 1-E-1, Loss of Reactor or Secondary Coolant.

6 When RCS pressure drops to below the actuation setpoint, SI pumps will not automatically start. This will require them to be manually started. Both will start and operate properly.

7 When RWST level lowers to below 34%, the crew will transition to 1-ES-1.3, Transfer to Containment Sump. 1-FCV-63-72 & 73, Train A & B Containment Sump Valves, fail to OPEN automatically when RWST level lowers to 34%. The crew should recognize this failure and manually open valves as directed by 1-ES-1.3 or by prudent operator action.

2020-301 Watts Bar NRC Examination [Page 3 of 66]

Appendix D Scenario Outline Form ES-D-1 Critical Tasks Critical Description Task 1 Close Pzr Spray Valve prior to Rx Trip on Low RCS Pressure.

2 Open CNTMT SUMP TO RHR PMP A & CNTMT SUMP TO RHR PMP B SUCT, prior to U1 RWST level reaching 8%.

References Number Title Revision 1-AOI-4 Nuclear Instrumentation Malfunctions 2 Unit Startup From Less Than 4% Reactor Power to 16 1-GO-3 30% Reactor Power 1-AOI-18 Malfunction of Pressurizer Pressure Control 9 System 1-ARI-109-115 CVCS & RHR-RPS & ESF 11 1-E-0 Reactor Trip or Safety Injection 16 1-E-1 Loss of Reactor or Secondary Coolant 11 1-ES-1.3 Transfer to Containment Sump 6 2020-301 Watts Bar NRC Examination [Page 4 of 66]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 1 Page 5 of 66 Event

Description:

IR N35 fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew responds to the following:

Examiner, insert Event 1: IR N35 fails LOW. CHANNEL I SOURCE/INTERMEDIATE RANGE TROUBLE M4 Window 81-A in alarm N35 indicates low N35 SUR indicates negative SRO SRO directs entry into 1-AOI-4, Nuclear Instrumentation Malfunctions.

SRO 1-AOI-4 SRO determines that Section 3.3 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 1 Page 6 of 66 Event

Description:

IR N35 fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-AOI-4 BOOTH OPERATOR: As SM, if notified about the failure or if the crew is contemplating reducing power, direct the crew to raise power to > 10%

power.

SRO evaluates Tech Specs:

TS 3.3.1 LCO is not met:

Condition A: Reference Table 3.3.1-1 Immediately

1. 4 Condition F: Reduce Thermal Power to

< P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR Increase Thermal Power to > P-10 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

TS 3.3.3 LCO is not met:

Condition A: Restore required channel to OPERABLE < 30 days.

SRO SRO should determine that raising power > 10% (P-10) will take the plant out of the condition of applicability for TS 3.3.1 and 3.3.3. (LCO 3.0.4 is not applicable)

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 1 Page 7 of 66 Event

Description:

IR N35 fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-AOI-4 When the SRO addresses TS or at the discretion of the lead examiner, proceed to Event 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 2 Page 8 of 66 Event

Description:

Operator raises power to 14%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior SRO Directs crew to perform 1-GO-3, Unit Startup From Less Than 4%

Reactor Power to 30% Reactor Power, beginning at Section 5.3, Raise Reactor Power to between 13 and 15%.

RO/BOP 1-GO-3, Section 5.3 BOOTH OPERATOR: As SM if the crew is contemplating reducing power, direct the crew to raise power to > 10% power.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 2 Page 9 of 66 Event

Description:

Operator raises power to 14%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-GO-3, Section 5.3 RO BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 2 Page 10 of 66 Event

Description:

Operator raises power to 14%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-GO-3, Section 5.3 RO BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 2 Page 11 of 66 Event

Description:

Operator raises power to 14%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-GO-3, Section 5.3 BOP When reactor power > 10 % or at the discretion of the lead examiner, proceed to Event 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 12 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 3: Loop 2 Pressurizer Spray RCS pressure lowering Valve fails OPEN.

PZR PRESS LO-DEVN BACKUP HTRS ON M5, Window 90-B in alarm RO may manually close the spray valve prior to AOI entry SRO Directs entry into 1-AOI-18, Malfunction of Pressurizer Pressure due to it being an immediate action. Control System.

SRO 1-AOI-18 SRO determines that Section 3.2 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 13 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO Spray valve will close manually using PZR PRESS MASTER CONTROL (1-PIC-68-340A) or LOOP 2 SPRAY CONTROL (1-PIC-68-340B).

CRITICAL TASK 1: Close Pzr Spray Valve prior to Rx Trip on Low RCS Pressure.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 14 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 15 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 16 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 17 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 3 Page 18 of 66 Event

Description:

Loop 2 Pressurizer Spray valve fails OPEN Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-18 RO SRO Evaluates Tech Specs:

TS 3.4.1 Condition A: Restore RCS DNB Parameter to within limit (> 2214 psig)

< 2 hr.

When SRO evaluates TS or at the discretion of the lead examiner, proceed to Event 5.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 4 Page 19 of 66 Event

Description:

1-LT-62-129, VCT Level, fails HIGH.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 4: VCT level fails high.

VCT level indication rising VCT LEVEL HI/LO M6, Window 109-A in alarm SRO Directs RO to address alarm.

1-ARI-109-115, 109A VCT LEVEL HI/LO BOOTH OPERATOR: If contacted as an operator to investigate VCT level, acknowledge the request. RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 4 Page 20 of 66 Event

Description:

1-LT-62-129, VCT Level, fails HIGH.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ARI-109-115, 109A RO OAC will position 1-HS-62-118A, LETDOWN DIVERT TO HUT, to VCT position IAW ARI 109-A, and bypass the failed transmitter in DCS. US will evaluate Fire Protection Report.

When failed instrument is bypassed or at the discretion of the lead examiner, proceed to Event 5.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 21 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERTOR: When directed by the lead SRO Directs RO to perform Immediate Actions of 1-E-0, Reactor Trip or examiner, insert Event 5, Large Break LOCA, SI Safety Injection.

Pmps fail to start, Cnt Sump Vlvs fail to open.

1-E-0, Reactor Trip or Safety Injection RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 22 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 23 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO Both SI pumps fail to start automatically.

Both SI pumps can be started manually.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 24 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 Appendix A starts on page 52.

Appendix B starts on page 63. RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 25 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 26 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 27 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 28 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP SRO recognizes that Containment pressure is not normal.

Makes decision to proceed to 1-E-1, Loss of Reactor or Secondary Coolant.

SRO Announces transition to 1-E-1, Loss of Reactor or Secondary Coolant.

1-FR-P.1, PRESSURIZED THERMAL SHOCK SRO may transition to 1-FR-P.1, Pressurized Thermal Shock however, with RCS pressure < 150 psig and adequate RHR flow, they will return to this point in the procedure.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 29 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1, Loss of Reactor or Secondary Coolant RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 30 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 31 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP BOOTH OPERATOR: When contacted to check analyzer temperature lights NOT lit and to RESET local alarm panel, acknowledge the request reset local alarm panel.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 32 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 33 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 34 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 35 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 36 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 37 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP 1-AOI-17 steps start on page 47.

Appendix B starts on page 46.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 38 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 39 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 40 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP 1-FCV-63-72 & 73, Train A & B Containment Sump Valves, fail to OPEN automatically when RWST level lowers to 34%.

CRITICAL TASK 2: Open CNTMT SUMP TO RHR PMP A & CNTMT SUMP TO RHR PMP B SUCT, prior to U1 RWST level reaching 8%.

1-ES-1.3 starts on page48.

Scenario can be terminated when both Critical Tasks are complete or at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 41 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 42 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 43 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 44 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 45 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-1, Appendix B RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 46 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-17, Turbine Trip Only the first 3 steps of 1-AOI-17 are provided.

RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 47 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-1.3, Transfer to containment Sump RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 48 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-1.3 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 49 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-1.3 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 50 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ES-1.3 RO/BOP CRITICAL TASK 2: Open CNTMT SUMP TO RHR PMP A & CNTMT SUMP TO RHR PMP B SUCT, prior to U1 RWST level reaching 8%.

Scenario can be terminated when both Critical Tasks are complete or at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 51 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 52 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 53 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 54 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 55 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 56 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 57 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 58 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 59 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 60 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 61 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 62 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 2 Event # 5,6,7 Page 63 of 66 LB LOCA Event

Description:

Both SI pumps fail to start automatically Containment Sump Valves, fail to OPEN automatically when RWST level reaches 34%

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix B RO

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 2 Simulator Console Operators Instructions

1. SIMULATOR SET UP

a. ENSURE exam security is established.

b. LOAD IC 350.

c. LOAD schedule file for 2020-301 NRC Examination Scenario 2.

d. ENSURE the following are BYPASSED in DCS:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal).

e. ENSURE DCS workstations are in Initial environment

f. ENSURE ICS Screens are clear

g. ENSURE ICS alarms are acknowledged

h. CRITICAL STEP: ENSURE Scenario 2.evt loaded.

i. ENSURE MOL Reactivity Briefing Book and placard are used. ENSURE MOL Reactivity Briefing Book is UPDATED for current conditions.

j. ENSURE ALL malfunctions listed on the Simulator Input Summary are loaded in Director.

k. PERFORM Independent Verification that ALL malfunctions listed on the Simulator Input Summary are loaded in Director.

l. ENSURE "B" Train Channel II sign, MODE 1 sign, and A Protected train sign are posted on 1-M-30.

m. ENSURE correct AUO cards are available to US, OAC and BOP.

n. ENSURE ALL operator aids NOT required for the scenario are removed from the boards.

o. ENSURE ALL recorders are clear.

p. PLACE simulator in RUN until alarm 82-F, DCS Trouble, clears.

NOTE: IF desired, THEN Simulator may be placed in FREEZE until prompted by NRC CHIEF EXAMINER to return to RUN.

q. ENSURE ALL ARIs are clear of all writing.

r. IF the first scenario of the day THEN ENSURE:

1) ALL EOIs are clear of all writing

2) ALL AOIs are clear of all writing

3) ALL ECAs are clear of all writing

4) ALL FRs are clear of all writing

5) ALL Tech Specs are clear of all writing

6) ALL back-up copies are clear of all writing

s. IF NOT the first scenario of the day THEN ENSURE the following procedures to be used are not written on:

1) 1-AOI-4

2) 1-AOI-18

3) 1-GO-3

4) 1-ARI-109-115

5) 1-E-0 2020-301 Watts Bar NRC Examination [Page 64 of 66]

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 2 Simulator Console Operators Instructions

6) 1-E-1

7) 1-ES-1.3

2. GENERIC SCENARIO NOTES

a. Typical Response Times: Unless specified in the SEG or determined by the NRC CHIEF EXAMINER, the response time of AUOs or other personnel dispatched should be approximately 3 to 5 min.

b. Plant Data or Information Requests: Information not contained in this exam guide should be discussed with the NRC CHIEF EXAMINER before providing any information to the crew.

c. General Notifications: If not specifically addressed in the SEG, general notifications to Operations Management, Shift Manager, Load Coordinator, Plant Duty Manager, etc. will be acknowledged by the Console Operator.

3. TURNOVER INFORMATION a) Provide Crew with the following information:

Shift Turnover sheet with current Unit Status.

2020-301 Watts Bar NRC Examination [Page 65 of 66]

SHIFT TURNOVER CHECKLIST SM US Unit 1 UO Unit 2 Off-going - Name AUO Station WBN STA On-coming - Name Part 1 - Completed by off-going shift / Reviewed by on-coming shift:

Unit 1 Reactor Power = 3%

Unit 2 Reactor Power = 100%

Abnormal equipment lineup / conditions:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal).

Raise power to 14% in accordance with 1-GO-3.

SIs/Tests in progress / planned: (including need for conduct of evolution briefings)

None Major Activities / Procedures in progress or planned:

Continue startup IAW 1-GO-3, Unit Startup From Less Than 4% Reactor Power to 30% Reactor Power.

Radiological changes during the shift:

None Part 2 - Completed by on-coming shift prior to assuming duties:

Review station rounds /Abnormal readings (AUOs only)

Review Narrative Logs (previous day and carry-over items)

Current qualification status Leadership and Team Effectiveness applicability Review the current controlling Reactivity Management Plans (N/A for AUOs)

Review current TS/TRM/ODCM/FPR Required Actions (N/A for AUOs)

Walk down MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM /STA)

CR reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:___________

Part 3 - Completed by on-coming shift. These items may be reviewed after assuming duties:

Review Operator Workarounds, Burdens and Challenges (applicable Unit / Station)

Review applicable ODMI actions (first shift of shift week)

Review changes in Standing / Shift Orders (since last shift worked)

Review changes to TACFs issued (since last shift worked) (N/A for AUOs)

Review Control Room Deficiencies (first shift of shift week) (N/A for AUOs)

Review Component Deviation Log (N/A for AUOs)

TVA 40741

Watts Bar Nuclear Plant NRC EXAM 2020301 Scenario 3

[Page 1 of 62]

Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No. 3 Op Test No.: 2020-301 Examiners: Operators: SRO RO BOP Run Time: 90 to 120 minutes Initial Conditions: Unit 1 is in MODE 1 at 77% power 1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal)

Unit 2 is at 100% power Turnover: Maintain 75% power Event Malf. No. Event Type* Event Description No.

1 ni09c I-RO PR N43 Detector B fails HIGH TS-SRO 2 rx26c I-BOP 1-PT-1-9A, SG 2 Pressure, fails LOW TS-SRO 3 Remote C-RO The 1A Primary Water Pump trips 4 N/A R-RO Condenser Tube Leak, rapid shutdown N-BOP TS-SRO 5 ms01b M-ALL Steam Line break inside of containment SG2 6 ms04a C-RO All MSIVs fail to close ms04b ms04c ms04d 7 cv01b C-BOP Standby CCP 1B-B fails to start on SI

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2020-301 Watts Bar NRC Examination [Page 2 of 62]

Appendix D Scenario Outline Form ES-D-1 Scenario 3 - Summary Event Description 1 PR N43 Detector B fails HIGH. The RO will place control rods in manual (Immediate action of 1-AOI-4, NIS Malfunctions). The crew will enter 1-AOI-4 and perform actions including defeating N43 PRM Function at the NIS Rack. SRO will evaluate TS 3.3.1-1 Reactor Trip System and TS 3.2.4, Quadrant Power Tilt.

2 1-PT-1-9A, SG 2 Pressure, fails LOW. Operator may respond to SG2 PRESS LO or recognize the instrument failure and proceed to 1-AOI-16, Loss of Normal Feedwater.

SRO will evaluate TS 3.3.2, ESFAS Instrumentation and TS 3.3.3, PAM Instrumentation.

3 The 1A Primary Water Pump trips. The crew will enter ARI 101-C, PRI WTR HDR PRESS LOW which will direct the RO to manually start the 1B Primary Water Pump.

4 Condenser Tube Leak. Chemistry reports to the Control Room that condensate sample indicates a Main Condenser tube leak (Action Level 3). Crew will enter 1-AOI-41, Condenser Tube Leak which will direct power reduction to 5% as quickly as possible. The crew will then perform 1-AOI-39, Rapid Load Reduction.

5 Main Steam Line break occurs inside of containment. Containment pressure will rise resulting in containment isolation and SI. Crew will perform 1-E-0, Reactor Trip or Safety Injection then transition to 1-E-2, Faulted Steam Generator Isolation.

6 Main Steam Line Isolation Valves will fail to close automatically on Steam Pressure. The operator will be able to close them manually.

7 The Standby CCP will fail to automatically start on SI actuation. The operator will manually start it as directed by 1-E-0 or as a Prudent Operator Action.

2020-301 Watts Bar NRC Examination [Page 3 of 62]

Appendix D Scenario Outline Form ES-D-1 Critical Tasks Critical Description Task 1 Close MSIVs prior to prior to Accumulators discharging into RCS (RCS press ~ 600 psig).

2 Isolate AFW to SG 2 prior to ORANGE path criteria being met for 1-FR-P.1, Pressurized Thermal Shock (Any Tc< 240 oF).

References Number Title Revision 1-AOI-16 Loss of Normal Feedwater 10 1-AOI-4 Nuclear Instrumentation Malfunctions 2 1-ARI-116-123 RPS & ESF 5 1-ARI-57-63 Feedwater & Main Steam 4 1-AOI-41 Condenser Tube Leak 0 1-AOI-39 Rapid Load Reduction 7 1-E-0 Reactor Trip or Safety Injection 16 1-E-2 Faulted Steam Generator Isolation 3 2020-301 Watts Bar NRC Examination [Page 4 of 62]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 5 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 1: PR N43 Detector B Control rods temporarily inserting fails HIGH.

POWER RANGE LWR DETECTOR FLUX DEVN M4 Window 83C in alarm POWER RANGE CHANNEL DEVIATION M4 Window 83E in alarm RO may place Control Rods in MAN prior to 1-AOI-4 entry SRO Announces entry into 1-AOI-4, Nuclear Instrument Malfunctions (Immediate Action).

SRO 1-AOI-4 SRO determines that Section 3.4 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 6 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Section 3.4 RO RO may have already placed Control Rods in MANUAL.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 7 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Section 3.4 RO Attachment 3 starts on page 12.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 8 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Section 3.4 RO BOOTH OPERATOR: When contacted as maintenance, acknowledge request for repairs.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 9 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: As Work Control, if notified 1-AOI-4, Section 3.4 acknowledge request.

SRO evaluates Tech Specs:

TS 3.3.1 LCO Condition A: Enter condition referenced in Table RO 3.3.1-1 immediately.

2.a - Condition D:

Place Ch in Trip within72 hr OR Be in Mode 3 within 78 hr.

3.a - Condition E:

Place Ch in trip within 72 hr OR Be in Mode 3 within 78 hr.

6 - Condition W:

Place ch in trip within 72 hr OR Be in Mode 3 within 78 hr.

16.c - Condition S: P-8 (70-C) Dark Verify Intlk is in req state within 1 hr OR Be in Mode 2 within 7 hr.

16.d - Condition S: P-9 (69-E) Dark 16.e - Condition R: P-10 (64-E) Lit Verify Intlk is in req state within 1 hr OR Be in Mode 3 within 7 hr.

TS 3.2.4 LCO SR 3.2.4.2: Verify QPTR is within limit Using either incore detectors or PDMS.

BOOTH OPERATOR: As ODM and Rx Eng, acknowledge notification.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 10 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior RO 1-AOI-4, Section 3.4

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 11 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Section 3.4 RO When Control Rods are in AUTO, or at the discretion of the lead examiner, proceed to Event 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 12 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Attachment 3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 13 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Attachment 3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 14 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Attachment 3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 1 Page 15 of 62 Event

Description:

PR N43 Detector B fails HIGH Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-4, Attachment 3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 16 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 2: SG 2 Pressure, fails 1SG 2 PRESS LO M6 Window 117-A in alarm LOW. DCS TROUBLE M4 Window 82-F in alarm SG LEVEL DEVIATION M3 Window 63-F in alarm SRO Directs BOP to refer to alarm response.

1-ARI-116-123 BOP BOP determines that alarm is due to instrument failure.

SRO directs entry into 1-AOI-16, Loss of Normal Feedwater.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 17 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-ARI-57-63 BOP BOP should direct SRO to 1-AOI-16, Loss of Normal Feedwater.

BOOTH OPERATOR: As maintenance, acknowledge service request.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 18 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-16, Loss of Normal Feedwater SRO SRO determines that Section 3.8 is applicable.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 19 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-16, Section 3.8 BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 20 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-16, Section 3.8 BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 21 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOP 1-AOI-16, Section 3.8 SRO evaluates Tech Specs:

TS 3.3.2 Condition A: Enter condition in Tbl 3.3.2-1 immediately.

1.e: Condition D 4.d(1) Condition D:

Place Ch in Trip < 72 hr OR Be in Mode 3 < 78 hr AND Mode 4 < 84 hr.

TS 3.3.3 Condition A: Restore channel to operable < 30 days.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 2 Page 22 of 62 Event

Description:

1-PT-1-9A, SG 2 Pressure, fails LOW Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOP 1-AOI-16, Section 3.8 At the discretion of the lead examiner, proceed to Event 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 3 Page 23 of 62 Event

Description:

The 1A Primary Water Pump trips Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 3: The 1A Primary Water PRI WTR HDR PRESS LO M5 Window 101-B in alarm Pump trips due to bearing wear.

SRO Directs BOP to refer to alarm response.

1-ARI-95-101 BOP BOP starts Standby (1B) Primary Water Pump.

BOOTH OPERATOR: As auxiliary operator, acknowledge direction to determine cause of pump trip. After ~ 4 minutes, report that molded case breaker (1A1-A C&A Vent Board, Compartment 2D) has tripped.

If asked to look at the B PWP in order to start, report that conditions are normal.

When the Standby pump has been started, or at the discretion of the lead examiner, proceed to Event 4.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 24 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead SRO Upon receiving report from chemistry, announce entry into 1-AOI-Examiner, as Chemistry, report to the control room 41, Condenser Tube leak.

that CONFIRMED SAMPLE of the Condensate System indicates a Main Condenser tube leak

( Action Level 3).

1-AOI-41 Condenser Tube Leak 1-AOI-41 will direct reducing power to less than 5%.

SRO should perform 1-AOI-39, Rapid Load Reduction to reduce power.

BOOTH OPERATOR: If the crew decides to use 1-GO-4 to reduce power, notify the control room as the Shift Manager and direct reducing power using 1-AOI-39.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 25 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior SRO Announce entry into 1-AOI-39, Rapid Power Reduction.

1-AOI-39 SRO determines that Section 3.2 is applicable.

SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 26 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 27 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 28 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 29 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 30 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 31 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 BOOTH OPERATOR: As chemistry, when informed RO about >15% power change, acknowledge the notification.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 32 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 4 Page 33 of 62 Event

Description:

Condenser Tube Leak, rapid shutdown Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-39, Section 3.2 RO When power has been reduced by ~ 5% or at the discretion of the lead examiner, proceed to Event 5.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 34 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 5, 6, 7:

Numerous Control Room alarms Steam Line break inside of containment Reactor Trip All MSIVs fail to close Standby CCP fails to start ECCS Actuation Phase A actuation SRO Directs RO to perform Immediate Actions of 1-E-0, Reactor Trip or Safety Injection.

1-E-0, Reactor Trip or Safety Injection RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 35 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 36 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 37 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 Appendix A starts on page 47.

Appendix B starts on page 59. RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 38 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP Operator manually closes MSIVs.

CRITICAL TASK 1: Close MSIVs prior to prior to Accumulators discharging into RCS (RCS press ~ 600 psig).

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 39 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 40 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP RCPs may have to be secured due to RCS pressure < 1500 psig if MSIVs are open long enough.

SRO directs entry into 1-E-2, Faulted Steam Generator Isolation.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 41 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2, Faulted Steam Generator Isolation.

RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 42 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 43 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 44 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2 RO/SRO CRITICAL TASK 2: Isolate AFW to SG 2 prior to ORANGE path criteria being met for 1-FR-P.1, Pressurized Thermal Shock (Any Tc< 240 oF).

Scenario can be terminated when Critical Tasks are complete and at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 45 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2 RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 46 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-2 RO/BOP Scenario can be terminated when Critical Tasks are complete and at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 47 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 48 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 49 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 50 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP Operator determines that standby CCP is not running.

Manually starts CCP.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 51 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 52 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 53 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 54 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 55 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 56 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 57 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 58 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 3 Event # 5,6,7 Page 59 of 62 Steam Line break inside of containment SG2 Event

Description:

All MSIVs fail to close Standby CCP fails to start Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix B RO

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 3 Simulator Console Operators Instructions

1. SIMULATOR SET UP

a. ENSURE exam security is established.

b. LOAD IC 347.

c. LOAD schedule file for 2020-301 NRC Examination Scenario 3.

d. ENSURE the following are BYPASSED in DCS:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal).

e. ENSURE DCS workstations are in Initial environment

f. ENSURE ICS Screens are clear

g. ENSURE ICS alarms are acknowledged

h. DEPRESS CLR pushbutton on Area Rad Monitors (5) and Wide Range Condenser Vacuum Exhaust Rad Monitors (2)

i. ENSURE MOL Reactivity Briefing Book and placard are used. ENSURE MOL Reactivity Briefing Book is UPDATED for current conditions.

j. ENSURE ALL malfunctions listed on the Simulator Input Summary are loaded in Director.

k. PERFORM Independent Verification that ALL malfunctions listed on the Simulator Input Summary are loaded in Director.

l. ENSURE "B" Train Channel III sign, MODE 1 sign, and B Protected train sign are posted on 1-M-30.

m. ENSURE correct AUO cards are available to US, OAC and BOP.

n. ENSURE ALL operator aids NOT required for the scenario are removed from the boards.

o. ENSURE ALL recorders are clear.

p. PLACE simulator in RUN until alarm 82-F, DCS Trouble, clears.

NOTE: IF desired, THEN Simulator may be placed in FREEZE until prompted by NRC CHIEF EXAMINER to return to RUN.

q. ENSURE ALL ARIs are clear of all writing.

r. IF the first scenario of the day THEN ENSURE:

1) ALL EOIs are clear of all writing

2) ALL AOIs are clear of all writing

3) ALL ECAs are clear of all writing

4) ALL FRs are clear of all writing

5) ALL Tech Specs are clear of all writing

6) ALL back-up copies are clear of all writing

s. IF NOT the first scenario of the day THEN ENSURE the following procedures to be used are not written on:

1) 1-AOI-4

2) 1-AOI-41

3) 1-AOI-39

4) 1-ARI-57-63

5) 1-ARI-116-23 2020-301 Watts Bar NRC Examination [Page 60 of 62]

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 3 Simulator Console Operators Instructions

6) 1-ARI-95-101

7) 1-E-0

8) 1-E-2

2. GENERIC SCENARIO NOTES

a. Typical Response Times: Unless specified in the SEG or determined by the NRC CHIEF EXAMINER, the response time of AUOs or other personnel dispatched should be approximately 3 to 5 min.

b. Plant Data or Information Requests: Information not contained in this exam guide should be discussed with the NRC CHIEF EXAMINER before providing any information to the crew.

c. General Notifications: If not specifically addressed in the SEG, general notifications to Operations Management, Shift Manager, Load Coordinator, Plant Duty Manager, etc. will be acknowledged by the Console Operator.

3. TURNOVER INFORMATION a) Provide Crew with the following information:

Shift Turnover sheet with current Unit Status.

2020-301 Watts Bar NRC Examination [Page 61 of 62]

SHIFT TURNOVER CHECKLIST SM US Unit 1 UO Unit 2 Off-going - Name AUO Station WBN STA On-coming - Name Part 1 - Completed by off-going shift / Reviewed by on-coming shift:

Unit 1 Reactor Power ~ 77% holding on primary chemistry.

Unit 2 Reactor Power = 100%.

Abnormal equipment lineup / conditions:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal)

SIs/Tests in progress / planned: (including need for conduct of evolution briefings)

Major Activities / Procedures in progress or planned:

None Plant Risk: Green. Grid: Qualified.

Radiological changes during the shift:

None Part 2 - Completed by on-coming shift prior to assuming duties:

Review station rounds /Abnormal readings (AUOs only)

Review Narrative Logs (previous day and carry-over items)

Current qualification status Leadership and Team Effectiveness applicability Review the current controlling Reactivity Management Plans (N/A for AUOs)

Review current TS/TRM/ODCM/FPR Required Actions (N/A for AUOs)

Walk down MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM /STA)

CR reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:___________

Part 3 - Completed by on-coming shift. These items may be reviewed after assuming duties:

Review Operator Workarounds, Burdens and Challenges (applicable Unit / Station)

Review applicable ODMI actions (first shift of shift week)

Review changes in Standing / Shift Orders (since last shift worked)

Review changes to TACFs issued (since last shift worked) (N/A for AUOs)

Review Control Room Deficiencies (first shift of shift week) (N/A for AUOs)

Review Component Deviation Log (N/A for AUOs)

TVA 40741

Watts Bar Nuclear Plant NRC EXAM 2020301 Scenario 4

[Page 1 of 77]

Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No. 4 Op Test No.: 2020-301 Examiners: Operators: SRO RO BOP Run Time: 90 to 120 minutes Initial Conditions: Unit 1 is in MODE 1 at 100% power 1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal)

Unit 2 is at 100% power Turnover: Maintain 100% power Event Malf. No. Event Type* Event Description No.

1 fw56a C-BOP 1A #3 Heater Drain Pump bearings seize. Automatic rp03 R-RO turbine runback circuit fails.

TS-SRO 2 cv31a C-BOP CCP-A shaft shears.

TS/SRO 3 th05a C-RO A tube leak develops on the #1 SG of approximately 50 TS-SRO gpm.

4 th05a M-ALL SGTR on #1 SG, LOOP ed01 5 eg03a C-BOP Both DGs fail to start automatically.

eg03b 6 si09a C-RO BIT Outlet Valves will not automatically open on the SI si09b signal.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2020-301 Watts Bar NRC Examination [Page 2 of 77]

Appendix D Scenario Outline Form ES-D-1 Scenario 4 - Summary Event Description 1 1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails. Crew enters 1-AOI-37, Turbine Runback Response and performs manual power reduction to

< 85% power. SRO reviews TS 3.4.1, RCS Press, Temp and Flow and 3.2.3, AFD.

2 The shaft on the operating CCP will shear. The crew will enter 1-AOI-20, Malfunction of Pressurizer Level Control System, secure the affected CCP, isolate Letdown, start the remaining CCP and restore Letdown. The SRO will review TS 3.5.2, ECCS - Operating and TR 3.1.4, Charging Pumps, Operating.

3 A tube leak develops on the #1 SG of approximately 50 gpm. Crew will enter 1-AOI-33, Steam Generator Tube Leak. SRO will evaluate TS 3.4.13, RCS Operational Leakage.

4 The SG tube leak will degrade into a SGTR requiring a reactor trip. The crew enter 1-E-0, Reactor Trip or Safety Injection, then transfer to 1-E-3, Steam Generator Tube Rupture.

The crew will cool down the RCS in preparation for RCS depressurization.

5 When the reactor trips, a Loss of Offsite Power will occur. Both Diesel Generators fail to start. When 1-E-0 is performed, it will direct manually starting DGs. This will work and DG output breakers will automatically close to restore power to SD Busses.

6 BIT outlet valves will not open automatically. The operator will be able to open them manually.

2020-301 Watts Bar NRC Examination [Page 3 of 77]

Appendix D Scenario Outline Form ES-D-1 Critical Tasks Critical Description Task 1 Manually runback the plant when HDP #3 trips prior to Reactor Trip on LO LO SG Level.

2 Isolate SG#1 ( SG PORV Aligned, Stm to TD AFW closed, Blowdown Isolated, MSIV AND Bypass closed, AFW Isolated)prior to commencing unit cooldown.

References Number Title Revision 1-AOI-37 Turbine Runback Response 8 1-AOI-20 Malfunction of Pressurizer level Control System 9 1-AOI-33 Steam Generator Tube leak 8 1-AIO-39 Rapid Load Reduction 7 1-E-0 Reactor Trip or Safety Injection 16 1-E-3 Steam Generator Tube Rupture 7 2020-301 Watts Bar NRC Examination [Page 4 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 5 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew observes the following; Examiner, insert Event 1: 1A #3 Heater Drain Pump M-1 THRU M-6 MOTOR OVERLOAD M1 Window 14-D in bearings seize. Automatic turbine runback circuit alarm fails. M-1 THRU M-6 MOTOR TRIPOUT Window 14-E in alarm in alarm TURBINE RUNBACK BOP M2 Window 28-E in alarm ICS Alarm AFD 1A #3 HDP has tripped SRO Announces entry into 1-AOI-37, Turbine Runback Response.

1-AOI-37, Turbine Runback Response SRO determines that Section 3.2 is applicable.

SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 6 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 RO Crew should perform step 1 RNO, then proceed to step 12.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 7 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 BOP CRITICAL TASK 1: Manually runback the plant prior to Reactor Trip on LO LO SG Level.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 8 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 RO BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 9 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 starts on page 15. RO BOOTH OPERATOR: As auxiliary operator, acknowledge the request to investigate the HDP trip.

BOP BOOTH OPERATOR: As Chemistry, acknowledge the request to initiate power change sampling requirements.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 10 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 BOOTH OPERATOR: If notified as AUO to investigate HDP, wait 3 minutes and report that the BOP breaker has tripped. The pump appears to be seized and is hot to the touch.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 11 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 SRO Evaluates Tech Specs:

TS 3.2.3: Condition A: Reduce Thermal Power to BOP

< 50% RTP < 30 minutes.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 12 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Section 3.2 RO BOOTH OPERATOR: As Maintenance, acknowledge the request for repairs.

When the plant has been stabilized, or at the discretion of the lead examiner, proceed to Event 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 13 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 14 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 1 Page 15 of 77 Event

Description:

1A #3 Heater Drain Pump bearings seize. Automatic turbine runback circuit fails.

Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-37, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 16 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 2: CCP-A shaft shears.

CHARGING FLOW HI/LO M5 Window 108-A in alarm RCP SEAL SUPPLY FLOW LO M5 101-E CCP-A amps are minimum SRO Announces entry into 1-AOI-20, Malfunction of Pressurizer Level Control System 1-AOI-20, Malfunction of Pressurizer Level Control System SRO determines that Section 3.3 is applicable. SRO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 17 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO BOOTH OPERATOR: As AUO, if notified to investigate CCP A, wait ~ 3 minutes and report that it has a sheared shaft.

EXAMINER NOTE: Crew may isolate Letdown in accordance with OPDP-1, Conduct of Operations.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 18 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 19 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO BOOTH OPERATOR: If contacted as auxiliary operator to walk down the Standby CCP, wait ~ 3 minutes and report that all conditions are normal.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 20 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 21 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 22 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 23 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO Attachment 1 starts on Page 25.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 24 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Section 3.3 RO SRO evaluates Tech Specs:

TS 3.4.9 LCO is met.

TS 3.5.2 Condition A: Restore to operable < 72 hr.

TR 3.1.4 Condition A: Restore CCP to operable

< 72 hr OR Be in Mode 3 < 78 hr AND Borate to SDM ~ 1% k/k at 200 oF. AND Restore to operable < 246 hr.

TS 3.4.1 Condition A may be applicable if RCS pressure lowers to below 2214 psig.

BOOTH OPERATOR: As SM, acknowledge request to evaluate staffing and nuclear event response process.

BOOTH OPERATOR: As Work Control Center, acknowledge request to initiate repairs.

When the SRO address TS and TR or at the discretion of the lead examiner, proceed to Event 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 25 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 26 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 2 Page 27 of 77 Event

Description:

CCP-A shaft shears Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-20, Attachment 1 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 28 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew observes the following:

Examiner, insert Event 3: A tube leak develops VAC PMP EXH 1-RM-119 RAD HI in alarm on the #1 SG of approximately 50 gpm.

SRO Announces entry into 1-AOI-33, Steam Generator Tube Leak 1-AOI-33, Steam Generator Tube Leak RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 29 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 30 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 31 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 32 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO/BOP If the crew decides to trip the reactor, proceed to Event 4.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 33 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 34 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 RO BOOTH OPERATOR: Acknowledge notification for:

Operations Manager Radiation Protection: Wait ~ 3 minutes and report back SG 1 Rad Levels are elevated.

Chemistry: Wait ~ 10 minutes and report that SG 1 indicates a tube leak.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 35 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 BOP BOOTH OPERATOR: As AUO, acknowledge direction to perform Attachment 1.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 3 Page 36 of 77 Event

Description:

A tube leak develops on the #1 SG of approximately 50 gpm Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-AOI-33 SRO SRO Evaluates Tech Specs:

TS 3.4.13: Condition B: Be in Mode 3 < 6 hr Be in Mode 5 < 36 hr TS 3.7.5 LCO is met TS 3.7.6 LCO is met TS 3.7.14 (Secondary Specific Activity) LCO is waiting on chemistry sample.

When SRO directs 1-AOI-39, Rapid Load Reduction to be performed, proceed with Event 4.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 37 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior BOOTH OPERATOR: When directed by lead Crew Crew recognizes the following:

Examiner, insert Event 4, 5, 6:

RCS Pressure lowering SGTR on #1 SG, LOOP Reactor Trip Both DGs fail to start automatically. Safety Injection BIT Outlet Valves will not automatically open on the SI signal.

SRO Directs RO to perform 1-E-0, Reactor Trip or Safety Injection Immediate Actions

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 38 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Reactor Trip or Safety Injection RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 39 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO RO Emergency Starts both Diesel Generators. Once Emergency Started, both Diesel Generators automatically tie in to their respective busses.

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 40 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 41 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 Appendix A starts on page 62.

Appendix B starts on page 74. RO/BOP

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 42 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP 2020-301 Watts Bar NRC Examination [Page 42 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 43 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP 2020-301 Watts Bar NRC Examination [Page 43 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 44 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP 2020-301 Watts Bar NRC Examination [Page 44 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 45 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0 RO/BOP SRO directs entry into 1-E-3, Steam Generator Tube Rupture.

2020-301 Watts Bar NRC Examination [Page 45 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 46 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior SRO Announces entering 1-E-3, Steam Generator Tube Rupture 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 46 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 47 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 47 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 48 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 48 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 49 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 49 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 50 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 50 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 51 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP CRITICAL TASK 2: Isolate SG#1 ( SG PORV Aligned, Stm to TD AFW closed, Blowdown Isolated, MSIV AND Bypass closed, AFW Isolated)prior to commencing unit cooldown.

Scenario can be terminated when Critical Tasks are complete or at the discretion of the lead examiner.

2020-301 Watts Bar NRC Examination [Page 51 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 52 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP BOOTH OPERATOR: As radiation protection, acknowledge request to survey secondary plant.

BOOTH OPERATOR: As Chemistry, acknowledge request to get samples.

2020-301 Watts Bar NRC Examination [Page 52 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 53 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP CRITICAL TASK 2: Isolate SG#1 ( SG PORV Aligned, Stm to TD AFW closed, Blowdown Isolated, MSIV AND Bypass closed, AFW Isolated)prior to commencing unit cooldown.

2020-301 Watts Bar NRC Examination [Page 53 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 54 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 54 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 55 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 55 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 56 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 56 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 57 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 57 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 58 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 58 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 59 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 59 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 60 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP 2020-301 Watts Bar NRC Examination [Page 60 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 61 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-3, Steam Generator Tube Rupture RO/BOP Scenario can be terminated when Critical Tasks are complete or at the discretion of the lead examiner.

2020-301 Watts Bar NRC Examination [Page 61 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 62 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 62 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 63 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 63 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 64 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 64 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 65 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP Operator determines that BIT outlet valves are closed.

Opens them manually.

2020-301 Watts Bar NRC Examination [Page 65 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 66 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 66 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 67 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 67 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 68 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 68 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 69 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 69 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 70 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 70 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 71 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 71 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 72 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 72 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 73 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix A BOP 2020-301 Watts Bar NRC Examination [Page 73 of 77]

Appendix D Required Operator Actions Form ES-D-2 Op Test 301 Scenario # 4 Event # 4,5,6 Page 74 of 77 SGTR on #1 SG, LOOP Event

Description:

Both DGs fail to start automatically.

BIT Outlet Valves will not automatically open on the SI signal Sequence of Events / Examiner Notes Position Applicants Actions or Behavior 1-E-0, Appendix B RO 2020-301 Watts Bar NRC Examination [Page 74 of 77]

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 4 Simulator Console Operators Instructions

1. SIMULATOR SET UP

a. ENSURE exam security is established.

b. LOAD IC 349.

c. LOAD schedule file for 2020-301 NRC Examination Scenario 4.

d. ENSURE the following are BYPASSED in DCS:

1) 1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance.

e. ENSURE DCS workstations are in Initial environment

f. ENSURE ICS Screens are clear

g. ENSURE ICS alarms are acknowledged

h. ENSURE correct AUO cards are available to US, OAC and BOP.

i. ENSURE ALL operator aids NOT required for the scenario are removed from the boards.

j. ENSURE ALL recorders are clear.

k. PLACE simulator in RUN until alarm 82-F, DCS Trouble, clears.

NOTE: IF desired, THEN Simulator may be placed in FREEZE until prompted by NRC CHIEF EXAMINER to return to RUN.

l. ENSURE ALL ARIs are clear of all writing.

m. IF the first scenario of the day THEN ENSURE:

1) ALL EOIs are clear of all writing

2) ALL AOIs are clear of all writing

3) ALL ECAs are clear of all writing

4) ALL FRs are clear of all writing

5) ALL Tech Specs are clear of all writing

6) ALL back-up copies are clear of all writing

n. IF NOT the first scenario of the day THEN ENSURE the following procedures to be used are not written on:

1) 1-AOI-37

2) 1-AOI-20

3) 1-AOI-33

4) 1-AOI-39

5) 1-E-0

6) 1-E-3 2020-301 Watts Bar NRC Examination [Page 75 of 77]

Watts Bar Nuclear Plant 2020-301 NRC Examination Scenario 4 Simulator Console Operators Instructions

2. GENERIC SCENARIO NOTES

a. Typical Response Times: Unless specified in the SEG or determined by the NRC CHIEF EXAMINER, the response time of AUOs or other personnel dispatched should be approximately 3 to 5 min.

b. Plant Data or Information Requests: Information not contained in this exam guide should be discussed with the NRC CHIEF EXAMINER before providing any information to the crew.

c. General Notifications: If not specifically addressed in the SEG, general notifications to Operations Management, Shift Manager, Load Coordinator, Plant Duty Manager, etc. will be acknowledged by the Console Operator.

3. TURNOVER INFORMATION a) Provide Crew with the following information:

Shift Turnover sheet with current Unit Status.

2020-301 Watts Bar NRC Examination [Page 76 of 77]

SHIFT TURNOVER CHECKLIST SM US Unit 1 UO Unit 2 Off-going - Name AUO Station WBN STA On-coming - Name Part 1 - Completed by off-going shift / Reviewed by on-coming shift:

Unit 1 Reactor power = 100%

Unit 2 Reactor power = 100%

Abnormal equipment lineup / conditions:

1-LT-68-320 PZR LEVEL transmitter is in Bypass for maintenance (MIG Cal)

SIs/Tests in progress / planned: (including need for conduct of evolution briefings)

US/ SM review late SI report (SQN and WBN only)

Major Activities / Procedures in progress or planned:

None Plant Risk: Green. Grid: Qualified.

Radiological changes during the shift:

None Part 2 - Completed by on-coming shift prior to assuming duties:

Review station rounds /Abnormal readings (AUOs only)

Review Narrative Logs (previous day and carry-over items)

Current qualification status Leadership and Team Effectiveness applicability Review the current controlling Reactivity Management Plans (N/A for AUOs)

Review current TS/TRM/ODCM/FPR Required Actions (N/A for AUOs)

Walk down MCR Control Boards with off-going Operator (N/A for AUOs, as applicable for SM /STA)

CR reviews complete for previous shift (SM/US/STA)

Relief Time: Relief Date:___________

Part 3 - Completed by on-coming shift. These items may be reviewed after assuming duties:

Review Operator Workarounds, Burdens and Challenges (applicable Unit / Station)

Review applicable ODMI actions (first shift of shift week)

Review changes in Standing / Shift Orders (since last shift worked)

Review changes to TACFs issued (since last shift worked) (N/A for AUOs)

Review Control Room Deficiencies (first shift of shift week) (N/A for AUOs)

Review Component Deviation Log (N/A for AUOs)

TVA 40741

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM a

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Task: Retrieve a Dropped Control Rod Alternate Path: Yes Facility JPM #: 3-OT-JPMR095C Safety Function: 1

Title:

Reactivity Control K/A APE 003 Ability to operate and/or monitor the following as they apply to a Dropped AA1.08 Control Rod: CRDS Rating(s): 3.7 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant Classroom

References:

1-AOI-2 R13 Task Number: RO-085-AOI-2-004

Title:

Respond to a dropped RCCA Task Standard: The applicant:

1) Performs actions of 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, to withdraw Control Bank D rod H-12.

2) When Control Bank D rod H-12 is withdrawn to greater than or equal to 40 steps diagnoses that Control Bank D Group 2 rods D-8 and H-8 have dropped and performs IMMEDIATE ACTIONS by manually tripping the reactor.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 400

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Final Value rd07d Dropped rod h-12 1 0 176 rd13cbdd8 control rod fail to position control bank d d8 M 21

4. Ensure Auto Event Trigger is assigned to Event 21: The Event Code should read pc_rdbc0074a>=40.

5. Place simulator in RUN and acknowledge any alarms.

6. Clear DCS Trouble alarm.

6. ENSURE a marked-up copy of 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, signed (circled-and-slashed) through Step 16 is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-AOI-2 Page 5 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 was operating at 100% power when Control Bank D rod H-12 dropped into the core due to a power cabinet card problem about 15 minutes ago.

2. 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and has been performed through Step 16.

3. Reactor power was reduced to approximately 70%.

4. The problem has been repaired.

5. The Unit Supervisor, Shift Manager, Reactor Engineering and STA have agreed on a retrieval rate of 48 steps per minute and a maximum power level of 75%.

6. You are the Operator-at-the-Controls.

INITIATING CUES:

The Unit Supervisor directs you to realign H-12 rod starting at 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.

Notify the Unit Supervisor when Control Bank D, H-12 rod has been realigned.

Page 6 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Start Time:

Step # 1. 1-AOI-2, Section 3.3 Critical Step?

17. PLACE rod control in bank select position for affected bank.

Y Applicant rotates 1-RBSS, ROD BANK SELECT to the left from the MAN position to Standard:

the CBD position to select control bank D.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 2. 1-AOI-2, Section 3.3 Critical Step? NOTE Computer Points for the individual rod positions and bank demand positions are on the RPI ICS screen.

18. RECORD the value of the following:

N Affected banks step counter(s)

Computer step indication for rods in affected bank Bank overlap counter (N/A for shutdown bank) [control rod drive room, el 782, panel 1-L-122]

Applicant may record either:

Control Bank D Group Step Counter - 183 steps OR ICS Step Indication for Control Bank D C0072A H-4 179 steps Standard:

C0075A M-8 179 steps C0076A H-8 177steps C0073A D-8 174 steps C007 H-12 0 steps Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: When contacted, report that the Bank overlap counter is indicating 524 steps.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 3. 1-AOI-2, Section 3.3 Critical Step?

19. DISCONNECT all lift coils (toggle up) in affected bank, EXCEPT for Y dropped RCCA.

Standard: Applicant places toggle switches for rods M-4, D-4, M-12, D-12, H-4, M-8, H-8, D-8 in the disconnect position (up position) in cabinet 1-XS-85-1.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 4. 1-AOI-2, Section 3.3 Critical Step? NOTE The next step will cause a CONTROL ROD URGENT FAILURE alarm (except for Shutdown Banks C and D). After the rods are aligned and the rod position is updated, then this alarm will be reset.

N

20. INSERT affected RCCA greater than 10 steps, and CONTINUE until NO RCCA motion observed on RPI.

Applicant positions 1-FLRM, ROD MOTION CONTROL IN-OUT, to the IN position, Standard:

until 1-CBDG2, CONTROL BANK D 2, Group Counter inserts greater than 10 steps.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 5. 1-AOI-2, Section 3.3 Critical Step?

21. SET affected step counter to 000.

N The applicant lifts the cover on 1-CBDG2, CONTROL BANK D 2 and depresses the reset button (center button labeled RS) to set the counter to 000. (The applicant Standard:

may elect to depress the D button multiple times to set the step counter to 000.) The applicant closes the cover.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 6. 1-AOI-2, Section 3.3 Critical Step? 22. IF the affected RCCA is in Group 1, THEN, USE the Plant Computer to set affected banks position to zero:

a. SELECT NSSS AND BOP.

N b. SELECT ROD BANK UPDATE.

c. ENTER 0 in affected bank position, THEN PRESS F3 to save.

Standard: Applicant determines that Group 1 is not affected. Marks step as N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 7. 1-AOI-2, Section 3.3 Critical Step? 23. DO NOT CONTINUE UNTIL the following agree on a retrieval rate:

Unit SRO N Shift Manager Reactor Engineering STA Applicant determines that the above personnel have agreed to retrieval rate and Standard:

maximum power level per initial conditions.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

This information is provided in the INITIAL CONDITIONS.

If any one of the above are contacted, state that the Unit SRO, Shift Manager, Cue: Rx Engineering and STA are in agreement to retrieve the rod at normal manual speed of 48 steps/minute. Maximum power level is 75%. Recover from present power level.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 8. 1-AOI-2, Section 3.3 Critical Step? NOTE Boric acid requirements can be determined using Reactivity Briefing Sheet.

24. ALIGN RCCA to affected bank position:

() USING rod control in Bank Select, position affected RCCA to Y bank affected position recorded in Step 18

() BORATE RCS to maintain Tavg and Tref within 3oF.

MAINTAIN less than or equal to 75% Reactor power. The applicant will trip the reactor.

Applicant attempts to realign the rod by placing 1-FLRM, ROD MOTION CONTROL IN-OUT to the OUT position AND determines that the rod is withdrawing. Applicant Standard: stops withdrawing rod after recognizing other rods have dropped into core.

Returns to 1-AOI-2, Section 3.3, Step 1.

Performance: SATISFACTORY UNSATISFACTORY The applicant may refer to the REACTIVITY BRIEFING BOOK for thumb rule values for boron for possible use in Step 24 (JPM Step 8).

During the performance of step 24 (JPM Step 8.) when Rod H-12 has been Examiner Notes: withdrawn approximately 40 steps, Control Bank D rods H-8 and D-8 will drop. The applicant will trip the reactor (Immediate Actions of E-0 are not required for this JPM).

Alternate Path starts here.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Step # 9. 1-AOI-2, Section 3.3 Critical Step? 1. PERFORM the following:

Y

a. MONITOR ONLY ONE rod a. IF more than one rod dropped, dropped THEN

() TRIP reactor

• • GO TO 1-E-0, Reactor Trip or Safety Injection.

Standard: Applicant trips the reactor.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Any procedural actions taken in this procedure that do not make progress towards tripping the reactor (placing the plant in a safe condition) do not meet the intent of this critical step.

Cue:

Comments:

Terminating Cue: The JPM is terminated when the applicant trips the reactor.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE a

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 was operating at 100% power when Control Bank D rod H-12 dropped into the core due to a power cabinet card problem about 15 minutes ago.

2. 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and has been performed through Step 16.

3. Reactor power was reduced to approximately 70%.

4. The problem has been repaired.

5. The Unit Supervisor, Shift Manager, Reactor Engineering and STA have agreed on a retrieval rate of 48 steps per minute and a maximum power level of 75%.

6. You are the Operator-at-the-Controls.

INITIATING CUES:

The Unit Supervisor directs you to realign H-12 rod starting at 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.

Notify the Unit Supervisor when Control Bank D, H-12 rod has been realigned.

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM b

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Task: TRANSFER ECCS to RHR Containment Sump per 1-ES-1.3 Alternate Path: Yes Facility JPM #: 3-OT-J1F-1-1SI-E13 Safety Function: 2

Title:

Reactivity Coolant System Inventory Control K/A 006 Ability to manually operate and/or monitor in the A4.05 control room: Transfer of ECCS flowpaths.

Rating(s): 4.1 CFR: 41.7 / 45.5 / 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-ES-1.3 R6 Task Number: RO-113-ES-1.3-001

Title:

Following an accident, transfer ECCS and containment spray suction to the containment sump in accordance with ES-1.3, Transfer to Containment Sump.

Task Standard: The applicant:

1) Performs actions of 1-ES-1.3, Transfer to Containment Sump.

2) When Containment Sump valve fails to open, secure the associated RHR pump.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 29

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 29

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 401

3. ENSURE the following information appears on the Director Summary Screen:

Key rh09 FCV-63-73 failed closed th01b Loca hot leg loop 2 cs06g Air return fan a-a fail to start on phase b cs06h Air return fan b-b fail to start on phase b sir14 Rwst to rhr pmp flow cntl vlv power, fcv-63-1 sir01 Pwr to cold leg accum isolation valves 63-67, 80, 98, 118 sir06 Cold leg injection mov power 63-22 csr04 Containment spray pump b power PMP-72-10

4. Place simulator in RUN and acknowledge any alarms.

6. ENSURE a copy of 1-ES-1.3, Transfer to Containment Sump is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 29

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-ES-1.3 R6 Page 5 of 29

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 2 is at 100% power

2. A Large Break LOCA has occurred on Unit 1

3. 1-ES-1.3, Transfer to Containment Sump, has just been entered

4. You are the Operator at the Controls (OAC)

5. You are the only operator available INITIATING CUES:

The Unit Supervisor directs you to perform 1-ES-1.3 Notify the Unit Supervisor when 1-ES-1.3 is complete Page 6 of 29

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Start Time:

Step # 1. 1-ES-1.3 Critical Step? CAUTION ECCS flow to RCS must be maintained at all times to ensure adequate core cooling.

Transfer to recirculation mode may cause high radiation in the Auxiliary Building.

NOTES Performance of this Instruction is a higher priority than performance of the FRs because it maintains ECCS pump N

suction.

The transfer sequence should be performed without delay.

Implementation of FRs is delayed UNTIL transfer sequence is completed or transitioned from.

1. ENSURE both RHR pumps RUNNING.

Applicant verifies Red breaker position indicating lights illuminated on both RHR Standard: Pump Hand switches (1-HS-74-10A & 1-HS-74-20A) or RHR Pump amps verified in normal range (1-EI-74-17A & 1-EI-74-26).

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 2. 1-ES-1.3 Critical Step? 2. DETERMINE if cntmt spray should be stopped:

a. CHECK ANY cntmt spray pump running.

b. ENSURE the following:

N One Cntmt Spray pump running One Cntmt Spray pump in PULL-TO-LOCK

c. MONITOR containment pressure greater than or equal to 2.0 psig.

Standard: Applicant determines that CS is not in operation.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 3. 1-ES-1.3 Critical Step? 3. ESTABLISH CCS to RHR heat exchangers [M-27B]:

a. ENSURE RHR HX 1B OUTLET 1-FCV-70-153 and RHR HX 1A Y OUTLET 1-FCV-70-156 OPEN.

Applicant fully opens 1-FCV-70-153 with 1-HS-70-153.

Standard:

Applicant opens 1-FCV-70-156 with 1-HS-70-156A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If applicant attempts to have another operator perform this step, direct them to perform Cue:

it.

Comments:

Step # 4. 1-ES-1.3 Critical Step? 3. ESTABLISH CCS to RHR heat exchangers [M-27B]:

b. IF Unit 2 has been SHUTDOWN > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, THEN N ENSURE RHR HX 2B OUTLET 2-FCV-70-153 THROTTLED to 2800 gpm if in service.

Standard: Performer determines that RHR HX 2B is not in service Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 5. 1-ES-1.3 Critical Step? 3. ESTABLISH CCS to RHR heat exchangers [M-27B]:

Y c. CLOSE SFP heat exchanger A CCS supply 0-FCV-70-197.

Applicant closes 0-FCV-70-197 with 0-HS-70-197A and is checked closed by green Standard:

position valve close light illuminated.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 6. 1-ES-1.3 Critical Step? 3. ESTABLISH CCS to RHR heat exchangers [M-27B]:

d. ENSURE CCS flow to ESF supply header is greater than 5000 gpm.

Train A: 1-FI-70-159 N

Train B: 1-FI-70-165 Standard: CCS flow verified on 1-FI-70-159 and 165 greater than 5000 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 7. 1-ES-1.3 Critical Step? 3. ESTABLISH CCS to RHR heat exchangers [M-27B]:

N e. MONITOR level in CCS surge tanks.

Standard: CCS Surge Tank level verified stable on 1-LI-70-63A and 99A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 8. 1-ES-1.3 Critical Step?

4. CHECK RWST level less than 34%.

N Applicant checks RWST level indicators, 1-LI-63-50, 51, 52, and 53 indicating less Standard:

than 34%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 9. 1-ES-1.3 Critical Step?

5. CHECK cntmt sump level greater than or equal to 16.1 %.

N Applicant checks Cntmt Sump level indicators 1-LI-63-180, 181, 182, and 183 Standard:

indicating 16.1%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 10. 1-ES-1.3 Critical Step? 6. ENSURE automatic switchover complete:

N a. ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

Applicant determines 1-FCV-63-72 is fully open by observing respective valve position red indicating light lit, green light off.

Applicant determines that 1-FCV-63-73 is not open by observing that the respective Standard: valve green light is lit and red light is dark, 1B-B RHR pump discharge pressure is lower than the other train.

Applicant proceeds to the RNO step.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Alternate Path starts here.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 11. 1-ES-1.3 Critical Step? 6. ENSURE automatic switchover complete:

RNO: IF EITHER cntmt sump valve can NOT be fully opened, THEN Y STOP and PULL TO LOCK RHR pump(s) on the associated train(s).

Applicant stops the 1B-B RHR pump by placing 1-HS-74-20A to STOP, then PULL Standard:

TO LOCK.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 12. 1-ES-1.3 Critical Step? 6. ENSURE automatic switchover complete:

b. ENSURE RWST to RHR suction valves 1-FCV-74-3 and 1-FCV-74-21 Y CLOSED.

1- FCV-74-3 is verified closed by the green light lit on 1-HS-74-3A. (Not Critical)

Standard: Applicant rotates 1-HS-74-21A to the CLOSE position. Verifies green light becomes lit, red light becomes dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 13. 1-ES-1.3 Critical Step? 6. ENSURE automatic switchover complete:

N

c. INITIATE power restoration to 1-FCV-63-1 USING Appendix A (1-ES-1.3), 1-FCV-63-1 Breaker Operation.

Standard: Applicant dispatches AUO to perform Appendix A of 1-ES-1.3.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When the AUO is dispatched to restore power to 1-FCV-63-1, or asked about Cue:

the status of 1-FCV-63-1. Respond: Power has been restored to 1-FCV-63-1.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 14. 1-ES-1.3 Critical Step? CAUTION If RWST level drops to 8%, then any charging, SI or cntmt spray pump taking suction from the RWST must be stopped.

N 7. MONITOR RWST level greater than 8%.

RNO: STOP and PULL TO LOCK pumps taking suction from the RWST.

Applicant monitors RWST level > 8%.

Standard: RNO: If RWST level is < 8%, the applicant will STOP and PULL TO LOCK [1A &

1B CCPs, 1A & 1B SIPs, and 1A &1B CSPs]. The RNO step is CRITICAL if required.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 15. 1-ES-1.3 Critical Step?

8. MONITOR RCS press less than 1350 psig.

N Applicant checks and monitors RCS press less than 1350 psig by any of the Standard:

following: 1-PR-68-63, 1-PR-68-340, and 1-PI-68-340A/334/323/322.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 16. 1-ES-1.3 Critical Step? CAUTION If a valve fails during the transfer sequence, any corrective action should be postponed UNTIL transfer is complete, EXCEPT as required to satisfy each step.

NOTE Each transfer sequence action is identified by a number on the control board (e.g. #1).

Y

9. (#1) ISOLATE SI pump miniflow:

CLOSE 1-FCV-63-3.

CLOSE 1-FCV-63-175.

CLOSE 1-FCV-63-4.

Performer isolates SI pump miniflow using 1-HS-63-3A, 1-HS-63-175A and 1-HS Standard: 4A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 17. 1-ES-1.3 Critical Step? 10. (#2) ISOLATE RHR crossties:

CLOSE 1-FCV-74-33.

Y CLOSE 1-FCV-74-35.

Standard: Performer isolates RHR crossties using 1-HS-74-33A and 1-HS-74-35A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

Step # 18. 1-ES-1.3 Critical Step? 11. (#3) ALIGN charging pump and SI pump supply from RHR:

OPEN 1-FCV-63-6.

Y OPEN 1-FCV-63-7.

ENSURE 1-FCV-63-177 OPEN.

Applicant aligns charging and SI pumps' supply from RHR using 1-HS-63-6A, 1-HS-Standard:

63-7A, and 1-HS-63-177A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 19. 1-ES-1.3 Critical Step? NOTE 1-FCV-63-8 and 1-FCV-63-11 are interlocked with the SI pump miniflows being full closed.

12. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

Y

a. OPEN 1-FCV-63-8.

b. OPEN 1-FCV-63-11.

Applicant aligns RHR discharge to charging and SI pumps' suction using 1-HS 8A (Critical) and 1-HS-63-11A. Determines that 1-FCV-63-11 does not open due to Standard: interlock with 1-FCV-63-73 (CNTMT SUMP TO RHR PMP B SUCT).

Applicant proceeds to the RNO step b.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 20. 1-ES-1.3 Critical Step? 12. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

RNO: b. ENSURE Train A RHR operation:

N Train A RHR pump RUNNING.

1-FCV-63-8 OPEN.

Either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

Applicant ensures 1A-A RHR pump is running, that 1-FCV-63-8 is OPEN, and 1-Standard:

FCV-63-6 & 1-FCV-63-7 are OPEN by checking respective handswitches.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

Step # 21. 1-ES-1.3 Critical Step?

13. DO NOT CONTINUE this Instruction UNTIL Steps 9 thru 12 complete.

N Standard: Applicant proceeds to step 14.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 22. 1-ES-1.3 Critical Step? CAUTION If RCS press is greater than 1350 psig, the SI pumps should NOT be restarted because the recirc path is isolated.

N

14. RESTART any charging pumps and SI pumps as necessary.

No action required unless the RWST level had reached 8% and were stopped, Standard:

THEN any pump stopped must be restarted as necessary.

Performance: SATISFACTORY UNSATISFACTORY This step is critical if CCPs and SIPs were secured earlier due to RWST level Examiner Notes:

dropping below 8%. In which case the step is critical to restore ECCS flow.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 23. 1-ES-1.3 Critical Step? CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

15. (#5) RESET SI, and CHECK the following:

N SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

Applicant verifies that [70-A] SI ACTUATED is dark, and [70-B] AUTO SI BLOCKED Standard:

is lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 24. 1-ES-1.3 Critical Step? 16. IF offsite power is lost, THEN

a. PLACE charging pumps in PULL TO LOCK.

b. RESTART RHR pumps.

N

c. RESTART charging pumps.

d. IF RCS press less than 1350 psig, THEN RESTART SI pumps.

Standard: No Applicant action required, stated condition does not apply.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 25. 1-ES-1.3 Critical Step?

17. (#6) ISOLATE charging pump suction from RWST:

Y a. CLOSE 1-LCV-62-135.

Standard: Applicant closes 1-LCV-62-135 using 1-HS-62-135A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 26. 1-ES-1.3 Critical Step? 17. (#6) ISOLATE charging pump suction from RWST:

Y b. CLOSE 1-LCV-62-136.

Standard: Applicant closes 1-LCV-62-136 using 1-HS-62-136A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

Step # 27. 1-ES-1.3 Critical Step? 17. (#6) ISOLATE charging pump suction from RWST:

N c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

Standard: Applicant verifies 1-HS-62-135A is in A-AUTO (pushed in).

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 28. 1-ES-1.3 Critical Step? 17. (#6) ISOLATE charging pump suction from RWST:

N d. ENSURE 1-HS-62-136A in A-AUTO (pushed in).

Standard: Applicant verifies 1-HS-62-136A is in A-AUTO (pushed in).

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

Step # 29. 1-ES-1.3 Critical Step?

18. (#7) ISOLATE SI pump suction from RWST:

Y CLOSE 1-FCV-63-5.

Standard: Applicant closes 1-FCV-63-5 using 1-HS-63-5A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Step # 30. 1-ES-1.3 Critical Step? 19. (#8) ISOLATE RHR suction from RWST:

a. ENSURE power restored to 1-FCV-63-1 USING Appendix A (1-ES-1.3), 1-FCV-63-1 Breaker Operation.

Y

b. CLOSE 1-FCV-63-1.

Applicant verifies power restored to 1-FCV-63-1 (Not Critical) and closes 1-FCV Standard:

1 using 1-HS-63-1A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Transfer sequence actions (#1 through #8) must be performed in sequence.

Cue:

Comments:

Terminating Cue: The JPM is terminated when the applicant closes 1-FCV-63-1 Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE b

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 2 is at 100% power

2. A Large Break LOCA has occurred on Unit 1

3. 1-ES-1.3, Transfer to Containment Sump, has just been entered

4. You are the Operator at the Controls (OAC)

5. You are the only operator available INITIATING CUES:

The Unit Supervisor directs you to perform 1-ES-1.3 Notify the Unit Supervisor when 1-ES-1.3 is complete

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM c

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Task: Standby MFP Shutdown Alternate Path: N/A Facility JPM #: New Safety Function: 4S

Title:

Heat Removal from the Reactor Core (Secondary System)

K/A 059 Ability to predict and/or monitor changes in parameters (to prevent A1.07 exceeding design limits) associated with operating the MFW controls including: Feed Pump speed, including normal control speed for ICS.

Rating(s): 2.5*/2.6* CFR: 41.7 / 45.5 / 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-SOI-2&3.01 R31 Task Number: RO-003-SOI-2/3-009

Title:

Startup/Shutdown the Main Feedwater system Task Standard: The applicant:

1) Performs actions of 1-SOI-2&3.01, Section 7.3.4 to remove STBY MFWP from service.

Validation Time: 20 minutes Time Critical: Yes No X Page 2 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 402

3. ENSURE the following information appears on the Director Summary Screen:

Key Event Fwr21 Stby mn feed pmp disch isolation vlv fcv-3-205 1 Fwr21 Stby mn feed pmp disch isolation vlv fcv-3-205 2

4. Place simulator in RUN and acknowledge any alarms.

5. Clear DCS Trouble.

6. ENSURE a copy of 1-SOI-2&3.01, is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-SOI-2&3.01 R31 Page 5 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. Both Main Feedwater Pumps AND the Standby Main Feedwater Pump are in service INITIATING CUES:

The Unit Supervisor directs you to remove the Standby Main Feedwater Pump from service and place in a standby alignment in accordance with 1-SOI-2&3.01, Section 7.3.4.

Notify the Unit Supervisor when the STBY MFWP is in the standby alignment Page 6 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Start Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Step # 1. 1-SOI-2&3.01 Critical Step?

[1] IF TDMFP to carry load, THEN PERFORM the following:

Y [1.1] SLOWLY OPEN 1-FCV-3-208, STANDBY MAIN FEEDWATER PUMP MIN FLOW valve using 1-FIC-3-208 [1-M-3].

Applicant slowly opens 1-FCV-3-208, STANDBY MAIN FEEDWATER Standard:

PUMP MIN FLOW, valve using 1-FIC-3-208 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 2. 1-SOI-2&3.01 Critical Step? [1] IF TDMFP to carry load, THEN PERFORM the following:

[1.2] SLOWLY RAISE TDMFP output to minimize SBFP forward flow USING the following controllers, as desired:

(N/A option(s) NOT used)

N 1-SIC-46-20A, MFPT A - SPEED CONTROL.

1-SIC-46-20B, MFPT B - SPEED CONTROL.

1-PC-46-20, MFPT A & B MASTER SPEED CONTROL.

Standard: TDMFPs will automatically pick up load.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Step # 3. 1-SOI-2&3.01 Critical Step? [2] ENSURE 1-FCV-3-208, STANDBY MAIN FEEDWATER PUMP MIN FLOW is full open if SBFP flow is reduced below 1500 gpm (minimum N required flow).

Applicant verifies 1-FIC-3-208 indicates 100% OUTPUT with SBFP flow below 1500 Standard:

gpm.

Performance: SATISFACTORY UNSATISFACTORY Annunciator 59-A, Standby MFP FLOW LO, is expected once SBFP flow is less than Examiner Notes:

1500 gpm.

Cue:

Comments:

Step # 4. 1-SOI-2&3.01 Critical Step?

[3] ENSURE 1-PIC-3-40 set at 1200 psia, and 1-PCV-3-40 CLOSED. (May N be N/Ad if 1-HS-3-45 is in Normal)

Standard: Applicant sets 1-PIC-3-40 to 1200 psia or marks N/A if no adjustment made.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Step # 5. 1-SOI-2&3.01 Critical Step? [4] WHEN MFP(s) have stabilized, THEN:

N [4.1] MONITOR MFP(s) picking up additional load.

Standard: Applicant monitors MFW Pump flow 1-FI-3-70 and 1-FI-3-84 have risen.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 6. 1-SOI-2&3.01 Critical Step? [4] WHEN MFP(s) have stabilized, THEN:

N

[4.2] CLOSE 1-FCV-3-205 using 1-HS-3-205, STANDBY MAIN FEEDWATER PUMP DISCHARGE ISOL [T1J/729].

Standard: Applicant dispatches operator to close 1-FCV-3-205 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Operator should remain in the area to open the valve in a few steps.

When dispatched as AUO, Activate Event 1. Inform applicant that 1-Cue:

FCV-3-205 is closed.

Comments: STANDBY MFP DISCH FCV-3-205 NOT FULL OPEN will alarm.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Step # 7. 1-SOI-2&3.01 Critical Step? [4] WHEN MFP(s) have stabilized, THEN:

Y [4.3] PLACE 1-HS-3-200A in STOP/PULL-TO-LOCK.

Standard: Applicant rotates 1-HS-3-200A to the STOP, then PULL TO LOCK position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 8. 1-SOI-2&3.01 Critical Step? [4] WHEN MFP(s) have stabilized, THEN:

N

[4.4] OPEN 1-FCV-3-205 using 1-HS-3-205, STANDBY MAIN FEEDWATER PUMP DISCHARGE ISOL [T1J/729].

Standard: Applicant direct dispatched operator to open 1-FCV-3-205.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When dispatched as AUO, Activate Event 2. Inform applicant that 1-Cue:

FCV-3-205 is OPEN.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Step # 9. 1-SOI-2&3.01 Critical Step?

[4] WHEN MFP(s) have stabilized, THEN:

N [4.5] PLACE 1-HS-3-200A in P-AUTO.

Standard: Applicant pushes in on 1-HS-3-200A, and then rotates to the P-AUTO position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. 1-SOI-2&3.01 Critical Step?

[5] ENSURE 1-FIC-3-208, STANDBY MFWP RECIRC CONTROL, in AUTO N at 22% (1500 gpm)[1-M-3], and 1-FCV-3-208 CLOSED [T1J/729].

Standard: Applicant ensures/places 1-FIC-3-208 in AUTO with the SETPOINT at 22%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue:

The JPM can be terminated when JPM step 10 is complete.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE c

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. Both Main Feedwater Pumps AND the Standby Main Feedwater Pump are in service INITIATING CUES:

The Unit Supervisor directs you to remove the Standby Main Feedwater Pump from service and place in a standby alignment in accordance with 1-SOI-2&3.01, Section 7.3.4.

Notify the Unit Supervisor when the STBY MFWP is in the standby alignment

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM d

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Task: Loss of Shutdown Cooling Alternate Path: Yes Facility JPM #: New Safety Function: 4P

Title:

Heat Removal from the Reactor Core (Primary System)

K/A 025 Ability to operate and/or monitor the following as they AA1.03 apply to a Loss of the Residual Heat Removal System: RHR Rating(s): 4.0 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant Classroom

References:

1-AOI-14 R7 Task Number: RO-074-AOI-14-003

Title:

Respond to RHR System Outleakage Task Standard: The applicant:

1) Aligns the A RHR train to provide Shutdown Cooling.

2) Mitigates the failure of Loop 4 RHR Suction valve.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 403

3. ENSURE the following information appears on the Director Summary Screen:

Key rh13 Fail FCV-74-01 closed rhr19 Supply power to FCV-74-9 rhr02 Open FCV-74-9 rhr18 Supply power to FCV-74-8 rhr01 Open FCV-74-8

4. Place simulator in RUN and acknowledge any alarms.

5) Clear DCS Trouble.

6. ENSURE a copy of 1-AOI-14, RHR System Outleakage, Section 3.7, RHR System Outleakage or LOCA While ON Shutdown Cooling, is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-AOI-14 R7 Page 5 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. While in Shutdown Cooling mode of operation, system Outleakage occurred.

2. The crew entered 1-AOI-14, Section 3.7, RHR System Outleakage or LOCA While On Shutdown Cooling.

3. The source of leakage has been determined and Shutdown Cooling is to be restored.

INITIATING CUES:

The Unit Supervisor directs you to perform 1-AOI-14, Appendix A, RHR Pump 1A-A Alignment.

Establish ~ 2500 gpm RHR flow.

Notify the Unit Supervisor when the RHR Train A is in operation.

Page 6 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Start Time:

Step # 1. 1-AOI-14, Appendix A Critical Step? NOTE These steps apply when the RHR pump to be aligned and started is in standby with the proper boron concentration and is available for immediate service. If these conditions do not exist, then SOI-74.01 should be used.

N

1. OPEN 1-FCV-70-156, CCS to RHR HX A.

Standard: Applicant verifies 1-HS-70-156A is already open.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 2. 1-AOI-14, Appendix A Critical Step? 2. ENSURE RCS HL to RHR suction OPEN:

1-FCV-74-1, Loop 4 HL To RHR Suction.

N 1-FCV-74-2, Loop 4 HL To RHR Suction.

Applicant rotates 1-HS-74-1A to the OPEN position.

Standard: Recognizes that the Green light stays lit and the Red light stays dark.

Applicant proceeds to the RNO step.

Performance: SATISFACTORY UNSATISFACTORY If applicant operates 1-HS-74-2A first, it will operate normally.

Examiner Notes:

Alternate path begins here.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 3. 1-AOI-14, Appendix A Critical Step? 2. ENSURE RCS HL to RHR suction OPEN:

RNO:

N PERFORM the following:

a. ENSURE 1-FCV-74-1 and 1-FCV-74-2 CLOSED.

Applicant verifies 1-FCV-74-1 is closed (it failed to open) and 1-FCV-74-2 is Standard: closed. If the applicant opened 1-FCV-74-2, they rotate 1-HS-74-2A to the CLOSE position. Verify Green light becomes lit, Red light goes dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 4. 1-AOI-14, Appendix A Critical Step? 2. ENSURE RCS HL to RHR suction OPEN:

RNO:

PERFORM the following:

Y

b. RESTORE power to, and OPEN bypass valves:

1) OPEN 1-FCV-74-9, RHR System Isol Bypass.

Applicant dispatches an operator to restore power to 1-FCV-74-9 and then open it Standard: locally.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

BOOTH OPERATOR: When directed by the operator, activate Event 2 to restore Cue:

power, and then activate Event 3 to open 1-FCV-74-9.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 5. 1-AOI-14, Appendix A Critical Step? 2. ENSURE RCS HL to RHR suction OPEN:

RNO:

PERFORM the following:

Y

b. RESTORE power to, and OPEN bypass valves:

2) OPEN 1-FCV-74-8, RHR System Isol Bypass.

Applicant dispatches an operator to restore power to 1-FCV-74-8 and then open it Standard:

locally.

Performance: SATISFACTORY UNSATISFACTORY BOOTH OPERATOR: When directed by the operator, activate Event 4 to restore Examiner Notes:

power, and then activate Event 5 to open 1-FCV-74-8.

Cue:

Comments:

Step # 6. 1-AOI-14, Appendix A Critical Step?

3. OPEN 1-FCV-74-3, RHR pump 1A-A suction.

N Standard: Applicant verifies 1-HS-74-3A is already open.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 7. 1-AOI-14, Appendix A Critical Step?

4. CLOSE RHR Hx outlets and bypass:

N 1-FCV-74-16, RHR Hx A outlet.

Standard: Applicant determines that 1-HIC-74-16A is already closed.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 8. 1-AOI-14, Appendix A Critical Step?

4. CLOSE RHR Hx outlets and bypass:

Y 1-FCV-74-28, RHR Hx B outlet.

Standard: Applicant depresses the [<<] pushbutton on 1-HIC-74-28A until output = 0%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 9. 1-AOI-14, Appendix A Critical Step?

4. CLOSE RHR Hx outlets and bypass:

Y 1-FCV-74-32, RHR Hx bypass.

Standard: Applicant depresses the [<<] pushbutton on 1-HIC-74-32A until output = 0%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. 1-AOI-14, Appendix A Critical Step?

4. CLOSE RHR Hx outlets and bypass:

Y 1-FCV-62-83, RHR Letdown To CVCS.

Standard: Applicant depresses the [<<] pushbutton on 1-HS-62-83 until output = 0%.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 11. 1-AOI-14, Appendix A Critical Step?

5. ALIGN RHR pump 1A-A discharge:

Y a. OPEN 1-FCV-63-93, RHR A to CL 2 & 3.

Applicant rotates 1-HS-63-93A to the OPEN position. Verifies Red light is lit and Standard:

Green light is dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 12. 1-AOI-14, Appendix A Critical Step?

5. ALIGN RHR pump 1A-A discharge:

Y b. OPEN 1-FCV-74-33, RHR Hx A outlet xtie.

Applicant rotates 1-HS-74-33A to the OPEN position. Verifies Red light is lit and Standard:

Green light is dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 13. 1-AOI-14, Appendix A Critical Step?

5. ALIGN RHR pump 1A-A discharge:

Y c. CLOSE 1-FCV-74-35, RHR Hx B outlet xtie.

Applicant rotates 1-HS-74-35A to the CLOSE position. Verifies Red light is dark and Standard:

Green light is lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 14. 1-AOI-14, Appendix A Critical Step?

5. ALIGN RHR pump 1A-A discharge:

Y d. CLOSE 1-FCV-63-94, RHR B to CL 1 & 4.

Applicant rotates 1-HS-63-94A to the CLOSE position. Verifies Red light is dark and Standard:

Green light is lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 15. 1-AOI-14, Appendix A Critical Step? CAUTION Maximum flow is limited to 2300 gpm per 1-GO-10, Appendix on Limiting RHR Flow Rate, while on midloop operation.

Prior to starting RHR pump RCS level must be greater than el 718 6 or pump may cavitate.

Y Re-establishing RHR flow may cause an RCS level drop due to shrink or void collapse.

6. START RHR pump 1A-A.

Applicant rotates 1-HS-74-10A to the START position. Verifies Red light becomes lit Standard:

and Green light becomes dark. Pump amps rise.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Step # 16. 1-AOI-14, Appendix A Critical Step?

7. ADJUST 1-FCV-74-16 to establish RHR flow.

Y Standard: Applicant depresses the [>>] pushbutton on 1-HIC-74-16A to establish flow ~ 2500 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Inform applicant that another operator will complete the procedure.

Comments:

Terminating Cue: The JPM can be terminated when the applicant establishes ~ 2500 gpm RHR flow.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE d

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. While in Shutdown Cooling mode of operation, system Outleakage occurred.

2. The crew entered 1-AOI-14, Section 3.7, RHR System Outleakage or LOCA While On Shutdown Cooling.

3. The source of leakage has been determined and Shutdown Cooling is to be restored.

INITIATING CUES:

The Unit Supervisor directs you to perform 1-AOI-14, Appendix A, RHR Pump 1A-A Alignment.

Establish ~ 2500 gpm RHR flow Notify the Unit Supervisor when the RHR Train A is in operation

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM e

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Task: Raise PRT Level Alternate Path: No Facility JPM #: New Safety Function: 5

Title:

Containment Integrity K/A 007 Ability to manually operate and monitor in the control room: PRT A4.01 makeup valve.

Rating(s): 4.0 CFR: 41.5 / 41.7 / 45.5 / 45.7 / 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-SOI-68.01 R6 Task Number: PRA- SYS068

Title:

System Refresher -- RCS Task Standard: The applicant:

1) Raise PRT level to ~ 71% in accordance with 1-SOI-68.01, RCS PRT Operations using primary water.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 407

3. ENSURE the following information appears on the Director Summary Screen:

Key Event WPR05 HS-77-415 RCDT Drain Valve Control Switch Close

4. Place simulator in RUN and acknowledge any alarms.

5. Clear DCS Trouble.

6. ENSURE a copy of 1-SOI-68.01, is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-SOI-68.1 R6 Page 5 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Annunciator 88-B (PRT LEVEL HI/LO) is alarming due to a low level.

Primary Water is aligned per 0-SOI-81.01 INITIATING CUES:

The Unit Supervisor directs you to perform 1-SOI-68.01, Reactor Coolant System Pressurizer Relief Tank Operations, Section 8.2, Return PRT level to normal from low level to raise PRT level to ~ 71%.

Notify the Unit Supervisor when the filling lineup is secured.

Page 6 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Start Time:

Step # 1. 1-SOI-68.01, Section 8.2 Critical Step? [1] PERFORM the following:

[1.1] NOTIFY UO of the anticipated primary water usage.

N

[1.2] ENSURE Primary Water is aligned per 0-SOI-81.01.

Standard: Applicant notifies the RO of anticipated primary water usage.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Acknowledge the notification.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 2. 1-SOI-68.01, Section 8.2 Critical Step? NOTE Steps 8.2[1.3] and 8.2[1.4] may be N/Ad when Primary Water system is in bypass mode.

N [1] PERFORM the following:

[1.3] ENSURE a Primary Makeup Water Pump is running.

Standard: Applicant verifies Red light is lit on 1-HS-81-3A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. 1-SOI-68.01, Section 8.2 Critical Step? [1] PERFORM the following:

[1.4] ENSURE the non-running Primary Makeup Water Pump handswitch N is in P-AUTO.

Standard: Applicant places 1-HS-81-7A in the P AUTO position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 4. 1-SOI-68.01, Section 8.2 Critical Step? NOTE Reduced Primary Water header pressure in the following step may require the non-running Primary Water Pump to be started.

[2] PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID PERF Y INITIAL PRIMARY WATER TO PRT & 1-M-5 OPEN 1-FCV-81-12 STANDPIPES Applicant rotates 1-HS-81-12A to the OPEN position. Verifies Red light becomes lit, Standard:

Green light becomes dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 5. 1-SOI-68.01, Section 8.2 Critical Step? [2] PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID PERF Y INITIAL PRI WATER TO PRT 1-M-5 OPEN 1-FCV-68-303 Applicant rotates 1-HS-68-303A to the OPEN position. Verifies Red light becomes Standard:

lit, Green light becomes dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 6. 1-SOI-68.01, Section 8.2 Critical Step? NOTE Steps 8.2[3] and 8.2[5] are N/A if NOT performed.

[3] IF PRT press reaches 8 psig, THEN PERFORM the following:

N

[3.1] ENSURE 1-FCV-77-18, RCDT TO WDS VENT HDR CIV -AIN CNTMT, OPEN [1-M-15].

Standard: Applicant verifies 1-HS-77-18A in the OPEN position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: This step may not be required.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 7. 1-SOI-68.01, Section 8.2 Critical Step? [3] IF PRT press reaches 8 psig, THEN PERFORM the following:

[3.2] ENSURE 1-FCV-77-19, RCDT TO WDS VENT HDR CIV - ØAOUT N CNTMT, OPEN [1-M-15].

Standard: Applicant verifies 1-HS-77-19 in the OPEN position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: This step may not be required.

Cue:

Comments:

Step # 8. 1-SOI-68.01, Section 8.2 Critical Step? [3] IF PRT press reaches 8 psig, THEN PERFORM the following:

N [3.3] OPEN 1-PCV-68-301, PRT VENT TO WDS VENT HDR [1-M-5].

Applicant rotates 1-HS-68-301A to the OPEN position. Verifies Red light becomes Standard: lit, Green light becomes dark. When PRT pressure lowers to < 8 psig, rotates 1-HS-68-301A to the CLOSE position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: This step may not be required.

As AUO, if directed to locally monitor PRT pressure at 0-L-2, acknowledge the Cue:

request.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 9. 1-SOI-68.01, Section 8.2 Critical Step? [4] WHEN PRT level reaches 67-80%, THEN PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID PERF INITIAL Y

PRIMARY WATER TO PRT & 1-M-5 CLOSED 1-FCV-81-12 STANDPIPES Standard: Applicant rotates 1-HS-81-12A to the CLOSE position. Verifies Red light becomes dark, Green light becomes lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. 1-SOI-68.01, Section 8.2 Critical Step? [4] WHEN PRT level reaches 67-80%, THEN PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID PERF Y INITIAL PRI WATER TO PRT 1-M-5 CLOSE 1-FCV-68-303 Standard: When PRT level indicates ~ 71%, applicant rotates 1-HS-68-303A to the CLOSE position. Verifies Red light becomes dark, Green light becomes lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Initiating cue states the applicant is to raise PRT level to ~ 71%.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Step # 11. 1-SOI-68.01, Section 8.2 Critical Step? NOTE Step 8.2[5] may be N/Ad when Primary Water system is in bypass mode.

N [5] ENSURE Primary Makeup Water Pumps aligned for current plant conditions, USING 0-SOI-81.01.

Applicant determines that Primary Makeup Water Pumps are aligned for current Standard:

plant conditions.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Primary Makeup Water Pumps are aligned for current plant conditions.

Cue:

If operator refers to 0-SOI-81.01, inform them that another operator will perform 0-SOI-81.01 to return PW to correct alignment.

Comments:

Step # 12. 1-SOI-68.01, Section 8.2 Critical Step? [6] IF 1-PCV-68-301 was opened during fill process, THEN ENSURE PRT pressure is less than 8 psig, AND CLOSE PCV-68-301, PRT VENT TO N WDS VENT HDR.

Standard: Applicant rotates 1-HS-68-301A to the CLOSE position. Verifies Red light becomes dark, Green light becomes lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Terminating Cue:

The JPM can be terminated when the applicant completes Section 8.2.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE e

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Annunciator 88-B (PRT LEVEL HI/LO) is alarming due to a low level.

Primary Water is aligned per 0-SOI-81.01 INITIATING CUES:

The Unit Supervisor directs you to perform 1-SOI-68.01, Reactor Coolant System Pressurizer Relief Tank Operations, Section 8.2, Return PRT level to normal from low level to raise PRT level to ~ 71%.

Notify the Unit Supervisor when the filling lineup is secured

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM f

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Task: Unload and shut down Diesel Generator Alternate Path: Yes Facility JPM #: New Safety Function: 6

Title:

Electrical K/A 064 Ability to manually operate and monitor in the control room: Manual start, loading, and stopping of the EDG A4.06 Rating(s): 3.9 CFR: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

0-SOI-82.01 R12 0-ARI-195-201 R3 Task Number: PRA- SYS082

Title:

System Refresher -- EDG Task Standard: The applicant:

1) Performs shutdown of 1A-A Emergency Diesel Generator after an emergency start.

2) Recognizes a DG trip condition and shuts down the DG.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 405

3. ENSURE the following information appears on the Director Summary Screen:

Key Event 07c048 DG 1A-A Crankcase Pressure High HS-57-41B to close 20

4. Place simulator in RUN and acknowledge any alarms.

5. Clear DCS Trouble.

6. ENSURE a copy of 1-SOI-82.01 Diesel Generator (DG) 1A-A, Section 8.3, Removing DG from Service after Emergency Start is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-SOI-82.01 R13 0-ARI-195-201 R3 Page 5 of 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

A loss of offsite power occurred after a reactor trip approximately 30 minutes ago DGs started and are supplying power to their respective shutdown boards Offsite power has been recovered INITIATING CUES:

The Unit Supervisor directs you to perform 1-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.3, Removing DG from Service after Emergency Start, 8.3.1, Removing DG from Service-DG Tied on to SD Bd.

Notify the Unit Supervisor when Section 8.3.1 is complete Page 6 of 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Start Time:

Step # 1. 1-SOI-82.01, Section 8.3 Critical Step? NOTE This section provides instructions for removing the DG from service and returning it to Standby Alignment after starting from either a Blackout, Safety Injection, manual emergency start or inadvertent emergency start.

Section 8.3.1 provides instructions for removing DG from service when N tied on to SD Bd.

8.3.1 Removing DG from Service-DG Tied on to SD Bd

[1] IF SI signal is present, THEN RESET SI Signal before removing DG from service.

Standard: Applicant determines that SI did not actuate.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 2. 1-SOI-82.01, Section 8.3 Critical Step? [2] IF amber light, 1-XI-82-19, EMERG START LOCKOUT RELAY 86 LOR MONITOR [0-M-26] is already ILLUMINATED and 43T(L) is in NORMAL, THEN N

GO TO Step 8.3.1[7].

Standard: Applicant recognizes that 1-XI-82-19 is dark and 43T(L) is in NORMAL, Proceeds to step 7.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If dispatched as an AUO to determine the status of 43T(L), inform the applicant Cue:

that 43T(L) is in NORMAL.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 3. 1-SOI-82.01, Section 8.3 Critical Step? [7] ENSURE one of the following ACBs CLOSED, and voltage available (CSST C is preferred, N/A ACBs NOT selected).

NOMENCLATURE LOCATION POSITION UNID INITIALS COMMON STATION SERVICE 0-ECB-2 CLOSED ACB 1712 TRANSFORMER C (NORMAL)

N COMMON STATION SERVICE 0-ECB-3 CLOSED ACB 1812 TRANSFORMER D (ALTERNATE) 6.9kV UNIT BOARD 1B 1-M-1 CLOSED ACB 1714 (MAINTENANCE)

Standard: Applicant determines that 0-ACB-1712 is closed. Marks other ACBs N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 4. 1-SOI-82.01, Section 8.3 Critical Step? [8] NOTIFY the load dispatcher that a DG will be synchronized to the grid and that the WBN control room should be notified to remove the DG from N service if the offsite power supply line protection is lost as detailed in 0-TI-12.15.

Standard: Applicant notifies load dispatcher.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Acknowledge notification.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 5. 1-SOI-82.01, Section 8.3 Critical Step?

[9] ENSURE 1-XS-57-43, 6.9 SD BD 1A-A XFER SELECTOR [1-M-1], in N MAN.

Standard: Applicant verifies 1-XS-57-43 is in the MAN position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 6. 1-SOI-82.01, Section 8.3 Critical Step? [10] ENSURE the following sync switches for 1A-A D/G in OFF:

NOMENCLATURE LOCATION POSITION UNID INITIALS MAINTENANCE 6.9 UNIT 0-M-26 OFF 1-HS-57-45 BD 1B SYNC SWITCH NORMAL - CSST C SYNC 0-M-26 OFF 1-HS-57-42 N

SWITCH DG SYNC SWITCH 0-M-26 OFF 1-HS-57-47 ALTERNATE CSST D SYNC 0-M-26 OFF 1-HS-57-114 SWITCH Standard: Applicant verifies that all sync switches are in the OFF position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 7. 1-SOI-82.01, Section 8.3 Critical Step? [11] PLACE Sync Switch for supply selected in Step 8.3.1[7] to SYN position (N/A switches NOT selected):

NOMENCLATURE LOCATION POSITION UNID INITIALS NORMAL - CSST C SYNC 0-M-26 SYN 1-HS-57-42 Y SWITCH ALTERNATE CSST D SYNC 0-M-26 SYN 1-HS-57-114 SWITCH MAINTENANCE 6.9 UNIT 0-M-26 SYN 1-HS-57-45 BD 1B SYNC SWITCH Standard: Applicant rotates 1-HS-57-42 to the SYN position (critical) and marks other switches N/A (not critical).

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 8. 1-SOI-82.01, Section 8.3 Critical Step? CAUTION When adjusting speed and voltage, care must be taken to prevent overshooting desired values. Voltage control response is approximately five times faster than speed control response.

N [12] MATCH generator Incoming Frequency (1-XI-82-2) with Running Frequency (1-XI-82-3) using 1-HS-82-13, SPEED CONTROL [0-M-26].

Applicant manipulates 1-HS-82-13 in the RAISE and/or LOWER positions to match Standard:

frequencies.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 9. 1-SOI-82.01, Section 8.3 Critical Step?

[13] MATCH running voltage (1-EI-82-5) to incoming voltage N (1-EI-82-4) with 1-HS-82-12, VOLTAGE REGULATOR [0-M-26].

Applicant manipulates 1-HS-82-12 in the RAISE and/or LOWER positions to match Standard:

voltages.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 10. 1-SOI-82.01, Section 8.3 Critical Step?

[14] PLACE 1-HS-82-18, DG MODE SELECTOR, in PARALLEL [0-M-26].

Y Standard: Applicant rotates 1-HS-82-18 to the PARALLEL position. Verifies Red light becomes lit, Green light becomes dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 11. 1-SOI-82.01, Section 8.3 Critical Step? [15] ENSURE DG Frequency and Voltage are MATCHED with 6.9 kV SD Bd, AND ADJUST 1-HS-82-13, SPEED CONTROL, [0-M-26] to obtain desired Y clockwise rotation (15 or more seconds) on 1-XI-82-1,TRAIN 1A-A SYNCHROSCOPE.

Applicant rotates 1-HS-82-13 as necessary to obtain clockwise rotation on 1-XI-82-1.

Standard:

Time requirement (15 or more seconds) is not critical.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If applicant asks for CV, inform them that the parameters have been verified.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 12. 1-SOI-82.01, Section 8.3 Critical Step? [16] IF a white breaker disagreement light is lit for any of the following handswitches, THEN CLEAR the disagreement by taking the handswitch to TRIP.

(N/A handswitches with no disagreement)

NOMENCLATURE LOCATION POSITION UNID INITIALS N 1716-NORMAL FROM CSST C 0-M-26 TRIP 1-HS 41B 1932 ALTERNATE FROM 0-M-26 TRIP 1-HS CSST D 97B 1718-MAINTENANCE FROM 0-M-26 TRIP 1-HS 6.9 UNIT BD 1B 44B Standard: Applicant determines that no disagreement exists and marks steps N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 13. 1-SOI-82.01, Section 8.3 Critical Step? [17] WHEN TRAIN 1A-A SYNCHROSCOPE (1-XI-82-1) reaches 12 oclock, THEN CLOSE the applicable supply breaker for the selected power supply:

(N/A handswitches NOT used)

NOMENCLATURE LOCATION POSITION UNID INITIALS Y 1716-NORMAL FROM CSST C 0-M-26 CLOSE 1-HS-57-41B 1932 ALTERNATE FROM 0-M-26 CLOSE 1-HS-57-97B CSST D 1718-MAINTENANCE FROM 0-M-26 CLOSE 1-HS-57-44B 6.9 UNIT BD 1B Applicant rotates 1-HS-57-41B to the CLOSE position. Verifies Red light becomes Standard:

lit, Green light becomes dark (critical). Marks other steps N/A (not critical).

Performance: SATISFACTORY UNSATISFACTORY When 1-HS-57-41B is placed in CLOSE, the malfunction for High Crankcase Examiner Notes:

Pressure will be inserted.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Step # 14. 1-SOI-82.01, Section 8.3 Critical Step? [18] PLACE the Sync switch selected in step 8.3.1[11] in OFF:

(N/A handswitches NOT used)

NOMENCLATURE LOCATION POSITION UNID INITIALS NORMAL - CSST C SYNC 0-M-26 OFF 1-HS-57-42 N SWITCH ALTERNATE CSST D SYNC 0-M-26 OFF 1-HS-57-114 SWITCH MAINTENANCE 6.9 UNIT 0-M-26 OFF 1-HS-57-45 BD 1B SYNC SWITCH Standard: Applicant rotates 1-HS-57-42 to the OFF position. Marks the other steps N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM 0-ARI-195-201 Step # 15.

CRANKCASE PRESS HI Critical Step? [1] IF DG running with NO emergency start present, THEN ENSURE DG shutdown by Emergency Stop:

Remote - Depress 1-HS-82-17A, EMERGENCY STOP pushbutton on 0-M-26.

Y Local - Depress EMERGENCY STOP pushbutton on DG Control Board.

Applicant pulls Alarm Response Instruction for CRANKCSE PRESS HI, THEN Standard: depresses 1-HS-82-17A EMERGENCY STOP pushbutton.

Applicant MUST trip the DG prior to proceeding with the ARI or SOI in order to satisfactorily complete this step.

Performance: SATISFACTORY UNSATISFACTORY Applicant may trip the DG using PRUDENT OPERATOR ACTIONS.

Examiner Notes: Applicant must trip the DG prior to proceeding with steps in the SOI or ARI.

Alternate Path starts here.

Cue:

Comments:

Terminating Cue:

The JPM can be terminated when the applicant trips DG 1A-A.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE f

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

A loss of offsite power occurred after a reactor trip approximately 30 minutes ago DGs started and are supplying power to their respective shutdown boards Offsite power has been recovered INITIATING CUES:

The Unit Supervisor directs you to perform 1-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.3, Removing DG from Service after Emergency Start, 8.3.1, Removing DG from Service-DG Tied on to SD Bd.

Notify the Unit Supervisor when Section 8.3.1 is complete

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM g

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Task: Start CCW pump Alternate Path: Yes Facility JPM #: New Safety Function: 8

Title:

Plant Service Systems K/A 075 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those A2.02 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps.

Rating(s): 2.5/2.7 CFR: 41.5 / 43.5 / 45.3 / 45.13 Evaluation Method: Simulator X In-Plant Classroom

References:

1-SOI-27.01 R10 1-ARI-159-165 R5 Task Number: RO-027-AOI-11-001

Title:

Respond to a loss of Condenser Circulating Water.

Task Standard: The applicant:

1) Starts CCW pump, verifies pump amp stabilize ~ 230 amps.

2) Takes appropriate actions to close the pump discharge valve when CCW pump trips In Accordance With 1-ARI-159-165.

Validation Time: 5 minutes Time Critical: Yes No X Page 2 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 406

3. ENSURE the following information appears on the Director Summary Screen:

Key Event Cw01d Circ Water Pump D trip HS-27-39a to start 21 override HS-27-39a to OFF light override HS-27-39a to ON light D CCW Pump to CLOSE 22 override HS-27-39a to OFF light override HS-27-39a to ON light

4. Place simulator in RUN and acknowledge any alarms.

6. ENSURE a copy of 1-SOI-27.01, Condenser Circulating Water System, Section 5.4, Placing CCW Pumps in Service is available for each applicant.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-SOI-27.01 1-ARI-159-165 Page 5 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Reactor power is 100%

3 CCW pumps are operating It is desired to start CCW pump 1D All prerequisites are complete Amertap balls have been collected 1-SOI-27.01, Condenser Circulating Water System, Section 5.4, Placing CCW Pumps in Service, is complete through Step 4 INITIATING CUES:

You have been directed to start CCW Pump 1D in accordance with 1-SOI-27.01, Condenser Circulating Water System, Section 5.4, Placing CCW Pumps in Service Notify the Unit Supervisor when Section 5.4 is complete Page 6 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Start Time:

Step # 1. 1-SOI-27.01, Section 5.4 Critical Step? [5] PERFORM the following for CCWP(s) to be started, (N/A remaining pumps):

Y Applicant rotates 1-HS-27-39A to the START/OPEN position. Verifies Red lights Standard:

become lit, Green lights become dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If directed as AUO to verify pump ready to start. Acknowledge and inform the Cue:

applicant that all parameters are normal and that the pump is ready to start Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 2. 1-SOI-27.01, Section 5.4 Critical Step? [6] CHECK CCWP amps less than 256 [1-M-15]:

1-EI-27-1, CCWP 1A AMPS 1-EI-27-2, CCWP 1B AMPS N

1-EI-27-7, CCWP 1C AMPS 1-EI-27-8, CCWP 1D AMPS Standard: Applicant verifies CCWP 1D amps < 256.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. 1-SOI-27.01, Section 5.4 Critical Step?

[7] IF operating with less than 4 CCW Pumps, THEN N

Standard: Applicant determines that all 4 CCW pumps are now operating.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: CCW Pump 4 will trip resulting in CCW/HPFP/RCW MOTOR TRIPOUT annunciator.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 4. 1-ARI-159-165, 165-B Critical Step?

N Standard: Applicant refers to CCW/HPFP/RCW MOTOR TRIPOUT.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 5. 1-ARI-159-165, 165-B Critical Step?

[1] DETERMINE which motor tripped.

N Standard: Applicant determines that CCWP 1D tripped.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Applicant may note that CCWP 1D discharge valve (1-FCV-27-41) did not close.

Cue:

Comments:

Step # 6. 1-ARI-159-165, 165-B Critical Step?

[2] REFER TO 0-GOI-7, Generic Equipment Operating Guidelines.

N Standard: Applicant directs another operator to address 0-GOI-7.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Inform the applicant that another operator will address 0-GOI-7.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 7. 1-ARI-159-165, 165-B Critical Step?

[3] ENSURE adequate pumps in service to replace tripped pump and start N additional pumps, if necessary.

Standard: Applicant determines that no other pumps are available.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 8. 1-ARI-159-165, 165-B Critical Step?

[4] IF a Fire Pump has tripped, THEN N

Standard: Applicant determines that no Fire Pump has tripped, marks step as N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 9. 1-ARI-159-165, 165-B Critical Step?

[5] IF a Raw Cooling Water Pump has tripped, THEN N

Standard: Applicant determines that no RCW pump has tripped. Marks step as N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. 1-ARI-159-165, 165-B Critical Step? [6] IF Condenser Circulating Water Pump tripped, THEN Y [6.1] ENSURE affected pump handswitch in PULL TO STOP [1-M-15].

Applicant pulls 1-HS-27-39A to PULL TO STOP/CLOSE. 1-FCV-27-41 will not Standard:

close.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Alternate Path starts here.

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Step # 11. 1-ARI-159-165, 165-B Critical Step? [6] IF Condenser Circulating Water Pump tripped, THEN

[6.2] ENSURE affected pump discharge valve shut (REFER TO SOI-Y 27.01, as necessary).

Applicant places 1-HS-27-39A to the CLOSE VLV position. Verifies that 1-FCV Standard:

41 closes by observing the green light lit and red light dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue:

The JPM can be terminated when the applicant has closed 1-FCV-27-41, discharge valve for CCW Pump 4.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE g

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Reactor power is 100%

3 CCW pumps are operating It is desired to start CCW pump 1D All prerequisites are complete Amertap balls have been collected 1-SOI-27.01, Condenser Circulating Water System, Section 5.4, Placing CCW Pumps in Service, is complete through Step 4 INITIATING CUES:

You have been directed to start CCW Pump 1D in accordance with 1-SOI-27.01, Condenser Circulating Water System, Section 5.4, Placing CCW Pumps in Service.

Notify the Unit Supervisor when Section 5.4 is complete

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM i

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Task: Thermal Overload Reset Operation Alternate Path: No Facility JPM #: 3-OT-J1E-2CB-E11 Safety Function: 3

Title:

Reactor Pressure Control K/A E02 Ability to operate and/or monitor the following as they apply to SI Termination: Components, and functions of control and safety systems, EA1.1 including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Rating(s): 4.0/3.9 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator In-Plant X Classroom

References:

2-ES -1.1 R2 Task Number: AUO-113-ES-1.1-001

Title:

Perform Appendix A of ES-1.1, Thermal Overload Reset Operation Task Standard: The applicant:

1) Performs 2-ES-1.1 Appendix A to reset Thermal Overload Protection Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Hard hat, Safety Glasses and approved shoes 2-ES-1.1 R2 Page 4 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 2 Conditions:

An inadvertent SI occurred while operating at 100% power 2-ES-1.1, SI Termination, is in progress You are the support AUO on shift INITIATING CUES:

The Unit 2 Unit Operator has directed you to:

Perform 2-ES-1.1, Appendix A, Thermal Overload Reset Operation Notify the MCR when complete Page 5 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Start Time:

Step # 1. 2-ES-1.1, Appendix A Critical Step? NOTE The following thermal overloads MUST be performed in order.

RESET the following thermal overloads in order:

RESET BOARD COMPT NOMENCLATURE Y

ORDER 1 480 V Reactor MOV 4F 2-BKR-213-A001/4F Board 2A1-A THERMAL OVERLOAD BYPASS 2A1 Standard: Reactor MOV board 2A1-A compartment 4F hand switch is turned to reset and allowed to spring return back to normal.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If asked, the red light is ON prior to resetting the switch or OFF after resetting the switch.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Step # 2. 2-ES-1.1, Appendix A Critical Step? RESET the following thermal overloads in order:

RESET BOARD COMPT NOMENCLATURE ORDER Y

2 480 V Reactor MOV 6D 2-BKR-213-A002/6D Board 2A2-A THERMAL OVERLOAD BYPASS 2A2 Standard: Reactor MOV board 2A2-A compartment 6D hand switch is turned to reset and allowed to spring return back to normal.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If asked, the red light is ON prior to resetting the switch or OFF after resetting the switch.

Comments:

Step # 3. 2-ES-1.1, Appendix A Critical Step?

RESET BOARD COMPT NOMENCLATURE ORDER Y 3 480 V Reactor MOV 16D 2-BKR-213-B001/16D Board 2B1-B THERMAL OVERLOAD BYPASS 2B1 Reactor MOV board 2B1-B compartment 16D hand switch is turned to reset and Standard: allowed to spring return back to normal.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If asked, the red light is ON prior to resetting the switch or OFF after resetting the switch.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Step # 4. 2-ES-1.1, Appendix A Critical Step?

RESET BOARD COMPT NOMENCLATURE ORDER Y 4 480 V Reactor MOV 6F 2-BKR-213-B2/6F Board 2B2-B THERMAL OVERLOAD BYPASS 2B2 Standard: Reactor MOV board 2B2-B compartment 6F hand switch is turned to reset and allowed to spring return back to normal.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If asked, the red light is ON prior to resetting the switch or OFF after resetting the switch.

Comments:

Step # 5. 2-ES-1.1, Appendix A Critical Step? Notify the MCR that the thermal overloads have been reset.

N Standard: The MCR has been notified that the thermal overloads have been reset.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Acknowledge the report.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Terminating Cue:

The JPM can be terminated when Appendix A is complete.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE i

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 2 Conditions:

An inadvertent SI occurred while operating at 100% power 2-ES-1.1, SI Termination, is in progress You are the support AUO on shift INITIATING CUES:

The Unit 2 Unit Operator has directed you to:

Perform 2-ES-1.1, Appendix A, Thermal Overload Reset Operation Notify the MCR when complete

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM j

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Task: Vent 2A-A and 2B-B AFW Pump Alternate Path: No Facility JPM #: New Safety Function: 4S

Title:

Heat Removal from the Reactor Core (Secondary System)

K/A E05 Ability to operate and/or monitor the following as they apply to Loss of Secondary Heat Sink: AFW system EA1.19 Rating(s): 4.3 CFR: 41.5 to 41.8/ 45.5 to 45.8 Evaluation Method: Simulator In-Plant X Classroom

References:

2-SOI-3.02 R10 Task Number: AUO-003-SOI-3.02-013

Title:

Vent Auxiliary Feedwater Pumps.

Task Standard: The applicant performs 2-SOI-3.02:

1) Section 8.7.1 to vent the 2A-A AFW Pump.

2) Section 8.7.2 to vent the 2B-B AFW Pump.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Hard hat, Safety Glasses and approved shoes 2-SOI-3.02 R10 Page 4 of 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 2 Conditions:

A loss of Main Feedwater has occurred Both MD AFW Pumps experienced cavitation and were secured Mechanical Maintenance has been dispatched to remove the caps on the Unit 2 MD AFW pump casing vents You are a support AUO on shift INITIATING CUES:

The Unit 2 Unit Operator has directed you to:

Vent both MD AFW pumps in accordance with 2-SOI-3.02, Auxiliary Feedwater System, Section 8.7.1 and 8.7.2 Inform the control room when complete Page 5 of 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Start Time:

Step # 1. 2-SOI-3.02, Section 8.7 Critical Step? CAUTION Be prepared to close the vent valve at all times during the venting process.

NOTES

1) Source Notes C.1, C.2, C.4, C.6, C.7 apply to this section.

2) IF venting due to vapor binding, it may also be necessary to vent AFW Pump Discharge Header using Section 8.8 to ensure system is returned N to Standby condition.

3) Evaluate Technical Specification 3.7.5, Auxiliary Feedwater System, if performing this section in Modes 1, 2, 3, or 4.

8.7.1 VENTING 2A-A AFW Pump

[1] NOTIFY UO of intention to vent AFW PUMP 2A-A.

Standard: Applicant informs UO of intention to vent AFW Pump 2A-A Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: As the UO, acknowledge the notification.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Step # 2. 2-SOI-3.02, Section 8.7.1 Critical Step? [2] ENSURE 2-HS-3-118A, AFW PMP 2A-A, is in PULL-TO-LOCK

[2-M-4].

N Standard: Applicant directs the UO to ensure that AFW Pump 2A-A is in PULL TO LOCK.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: As UO, inform the applicant that the 2A-A AFW Pump is in PULL TO LOCK.

Comments:

Step # 3. 2-SOI-3.02, Section 8.7.1 Critical Step?

[3] OPEN 2-VTV-3-931, AUX FEEDWATER PMP 2A-A CASING VENT.

Y Standard: Applicant simulates turning 2-VTV-3-931 counter clockwise.

Performance: SATISFACTORY UNSATISFACTORY The applicant should ask about the status of the cap on the vent piping (it is installed in the plant). If the applicant does not ask about the status of the cap, simulate that the Examiner Notes:

cap is installed, and no steam water mixture will come out of the vent until the applicant inquires about the status of the cap.

If the applicant asks if the cap on the vent piping is installed, inform the applicant that Mechanical Maintenance has removed the cap.

Cue:

Inform applicant that valve handwheel turns and a steam water mixture is coming out of the vent. After 20 seconds have passed, inform the applicant that a solid stream of water is issuing from the vent.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Step # 4. 2-SOI-3.02, Section 8.7.1 Critical Step?

[4] WHEN solid stream of water exists, THEN CLOSE 2-VTV-3-931, AUX Y FEEDWATER PMP 2A-A CASING VENT.

Standard: Applicant rotates the handwheel for 2-VTV-3-931 in the clock wise direction until valve handwheel comes to a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 2-VTV-3-931 is at a hard stop.

IF applicant asks for an IV, inform them that an IV has been performed.

Comments:

Step # 5. 2-SOI-3.02, Section 8.7.1 Critical Step? [5] IF AFW PMP 2A-A is to be aligned for STANDBY PLACE 2-HS-3-118A, AFW PMP 2A-A, in A-P AUTO [2-M-4].

N [6] NOTIFY UO that AFW PUMP 2A-A casing is VENTED.

Applicant notifies the US that AFW PUMP 2A-A casing has been vented and if AFW Standard:

Pump 2A-A is to be aligned for STBY, they are to place 2-HS-3-118A, in A-P AUTO Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Acknowledge as the UO.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Step # 6. 2-SOI-3.02, Section 8.7 Critical Step? 8.7.2 VENTING 2B-B AFW Pump N [1] NOTIFY UO of intention to vent AFW PUMP 2B-B.

Standard: Applicant informs UO of intention to vent AFW Pump 2B-B Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: As the UO, acknowledge the notification.

Comments:

Step # 7. 2-SOI-3.02, Section 8.7.1 Critical Step? [2] ENSURE 2-HS-3-128A, AFW PMP 2B-B, is in PULL-TO-LOCK

[2-M-4].

N Standard: Applicant directs the UO to ensure that AFW Pump 2B-B is in PULL TO LOCK.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: As UO, inform the applicant that the 2B-B AFW Pump is in PULL TO LOCK.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Step # 8. 2-SOI-3.02, Section 8.7.1 Critical Step?

[3] OPEN 2-VTV-3-932, AUX FEEDWATER PMP 2B-B CASING VENT.

Y Standard: Applicant simulates turning 2-VTV-3-932 counter clockwise.

Performance: SATISFACTORY UNSATISFACTORY The applicant should ask about the status of the cap on the vent piping (it is installed in the plant). If the applicant does not ask about the status of the cap, simulate that the Examiner Notes:

cap is installed, and no steam water mixture will come out of the vent until the applicant inquires about the status of the cap.

If the applicant asks if the cap on the vent piping is installed, inform the applicant that Mechanical Maintenance has removed the cap.

Cue:

Inform applicant that valve handwheel turns and a steam water mixture is coming out of the vent. After 20 seconds have passed, inform the applicant that a solid stream of water is issuing from the vent.

Comments:

Step # 9. 2-SOI-3.02, Section 8.7.1 Critical Step?

[4] WHEN solid stream of water exists, THEN CLOSE 2-VTV-3-932, AUX Y FEEDWATER PMP 2B-B CASING VENT.

Standard: Applicant simulates rotating the handwheel for 2-VTV-3-932 in the clock wise direction until the valve comes to a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 2-VTV-3-932 comes to a hard stop.

IF applicant asks for an IV, inform them that an IV has been performed.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Step # 10. 2-SOI-3.02, Section 8.7.1 Critical Step? [5] IF AFW PMP 2B-B is to be aligned for STANDBY PLACE 2-HS-3-128A, AFW PMP 2B-B, in A-P AUTO [2-M-4].

N [6] NOTIFY UO that AFW PUMP 2B-B casing is VENTED.

Applicant notifies the US that AFW PUMP 2B-B casing has been vented and if AFW Standard:

Pump 2B-B is to be aligned for STBY, they are to place 2-HS-3-128A, in A-P AUTO Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Acknowledge as the UO.

Comments:

Terminating Cue:

The JPM can be terminated when venting of both MD AFW pumps is complete.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE j

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 2 Conditions:

A loss of Main Feedwater has occurred Both MD AFW Pumps experienced cavitation and were secured Mechanical Maintenance has been dispatched to remove the caps on the Unit 2 MD AFW pump casing vents You are a support AUO on shift INITIATING CUES:

The Unit 2 Unit Operator has directed you to:

Vent both MD AFW pumps in accordance with 2-SOI-3.02, Auxiliary Feedwater System, Section 8.7.1 and 8.7.2 Inform the control room when complete

Watts Bar Nuclear Plant 2020301 NRC EXAM Sim JPM k

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Task: Isolate RCP Seals Alternate Path: No Facility JPM #: New Safety Function: 8

Title:

Plant Service Systems K/A 008 Ability to (a) predict the impacts of the following on the Component Cooling Water System and (b) based on those predictions, use A2.01 procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of CCW pump Rating(s): 4.3 CFR: 41.5 / 43.5 / 45.3 / 45.13 Evaluation Method: Simulator In-Plant X Classroom

References:

1-AOI-15 R9 Task Number: AUO-113-ECA-0.0-001

Title:

Isolate RCP Seals and Thermal Barrier.

Task Standard: The applicant performs 1-AOI-15, Attachment 3 to:

1) Isolate RCP Seals.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Hard hat, Safety Glasses and approved shoes 1-AOI-15 R9 Page 4 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

A loss of CCS flow and RCP seal injection occurred While performing 1-AOI-15 (Loss of Component Cooling Water), RCP Lower Bearing temperatures rose to greater than 225 oF The reactor was tripped 1-FCV-62-61 and 1-FCV-62-63, RCP Seal Return Valves, can NOT be closed from the control room 1-FCV-70-133 and 1-FCV-70-134, CCS Thermal Barrier Supply Valves [M-27B],

were CLOSED from the control room You are a support AUO on shift INITIATING CUES:

The Unit 1 Unit Operator has directed you to:

Perform 1-AOI-15, Attachment 3 (RCP Seals and Thermal Barrier Isolation, Section 2.0, Local Actions-Performed By Assistant Unit Operator, to isolate the RCP Seals Page 5 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Start Time:

Step # 1. 1-AOI-15, Attachment 3, Section 2.0 Critical Step? 2.0 LOCAL ACTIONS-PERFORMED BY ASSISTANT UNIT OPERATOR NOTES

1) These steps may be performed in any order.

2) Step 2.0A must always be performed.

Y A. ISOLATE RCP seal injection [reach rods outside seal water injection filter cubicles]:

CLOSE 1-ISV-62-549, CVCS SEAL WTR INJ FLTR B OUT ISOL

[A5T/713]

Standard: Applicant simulates rotating 1-ISV-62-549 handwheel in the clockwise direction until at a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 1-ISV-62-549 handwheel is at a hard stop.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Step # 2. 1-AOI-15, Attachment 3, Section 2.0 Critical Step? A. ISOLATE RCP seal injection [reach rods outside seal water injection filter cubicles]:

Y CLOSE 1-BYV-62-546, CVCS SEAL WTR INJ FLTR BYP [A5T/713]

Standard: Applicant simulates rotating 1-BYV-62-546 handwheel in the clockwise direction until at a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 1-BYV-62-546 handwheel is at a hard stop.

Comments:

Step # 3. 1-AOI-15, Attachment 3, Section 2.0 Critical Step? A. ISOLATE RCP seal injection [reach rods outside seal water injection filter cubicles]:

Y CLOSE 1-ISV-62-550, CVCS SEAL WTR INJ FLTR A OUT ISOL

[A5T/713 Standard: Applicant simulates rotating 1-ISV-62-550 handwheel in the clockwise direction until at a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 1-ISV-62-550 handwheel is at a hard stop.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Step # 4. 1-AOI-15, Attachment 3, Section 2.0 Critical Step? NOTE Step 2.0B to be performed only if MCR unable to CLOSE either 1-FCV 61 or 1-FCV 63.

B. ISOLATE RCP seal return valves [reach rod outside seal return filter Y cubicle]:

CLOSE 1-ISV-62-642, CVCS SEAL WTR RETURN FILTER INLET ISOL [A5T/713]

Applicant simulates rotating 1-ISV-62-642 handwheel in the clockwise direction until Standard:

at a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Initial conditions state that 1-FCV-62-61 or 1-FCV 63 cannot be operated from Examiner Notes:

the CR.

Cue: 1-ISV-62-642 handwheel is at a hard stop.

Comments:

Step # 5. 1-AOI-15, Attachment 3, Section 2.0 Critical Step? B. ISOLATE RCP seal return valves [reach rod outside seal return filter cubicle]:

Y CLOSE 1-BYV-62-643, CVCS SEAL WTR RETURN FILTER BYPASS

[A5T/713].

Standard: Applicant simulates rotating 1-BYV-62-643 handwheel in the clockwise direction until at a hard stop.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: 1-BYV-62-643 handwheel is at a hard stop.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Terminating Cue: The JPM can be terminated when applicant has completed isolating the RCP Seals.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE k

2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

A loss of CCS flow and RCP seal injection occurred While performing 1-AOI-15 (Loss of Component Cooling Water), RCP Lower Bearing temperatures rose to greater than 225 oF The reactor was tripped 1-FCV-62-61 and 1-FCV-62-63, RCP Seal Return Valves, can NOT be closed from the control room 1-FCV-70-133 and 1-FCV-70-134, CCS Thermal Barrier Supply Valves [M-27B],

were CLOSED from the control room You are a support AUO on shift INITIATING CUES:

The Unit 1 Unit Operator has directed you to:

Perform 1-AOI-15, Attachment 3 (RCP Seals and Thermal Barrier Isolation, Section 2.0, Local Actions-Performed By Assistant Unit Operator, to isolate the RCP Seals

Watts Bar Nuclear Plant 2020301 NRC EXAM Administrative JPM 1S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Task: Calculate Shutdown Margin and Determine Corrective Actions Alternate Path: N/A Facility JPM #: N/A Safety Function: N/A

Title:

Conduct of Operations K/A 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Rating(s): 4.4 / 4.7 CFR: 41.5 / 43.5 / 45.12 / 45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

1-SI-0-10, Shutdown Margin R34 WBN 1 NOB, R 611 Technical Specifications 3.1.5, Rod Group Alignment Limits Amendment 120 Unit 1 COLR, R 1, Cycle 16 NuPOP, Unit1, R 0, Cycle 16 Task Number: RO-047-SOI-47-003

Title:

Calculate SDM Task Standard: The applicant:

1. Calculates SDM.

2. Determines that SDM is inadequate.

3. Recommends actions IAW TS 3.1.5, Rod Group Alignment Limits.

Validation Time: 15 minutes Time Critical: Yes No X

==================================================================================

Page 2 of 26

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 26

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

1-SI-0-10 TS 3.1.5 U1 COLR U1 NOB U1 NuPOP Page 4 of 26

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM READ TO OPERATOR DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

Unit 1 is at full power (600 EFPH) with all control systems in automatic except rod control, which is in manual.

Core average burnup = 998 MWD/MTU Boron concentration was 1200 ppm 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.

Control Bank D is at 210 steps.

RCS Tave is 587 °F.

Minimum Tcold will be 547 oF 5 minutes ago rods M-4 and M-12 were declared inoperable and immovable due to failure to move during the Movable Control Assembly Surveillance.

Rods M-4 and M-12 are aligned 4 steps from the rest of the rods in their group.

Prerequisites of Section 4.0 are complete.

Dilution protection via boron analysis is NOT required.

INITIATING CUES:

As the SRO, you are directed to:

Perform the Shutdown Margin Surveillance in accordance with 1-SI-0-10 Section 6.2 (Use NOB Values).

Determine ALL (if any) actions required due to plant conditions.

Page 5 of 26

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Start Time:

Step # 1. 1-SI-0-10 Section 6.2 Critical Step? NOTE Due to the amount of conservatism factored into this calculation, this instruction may NOT pass acceptance criteria. If the performance of this section results in SDM not passing the criteria, then perform Section 6.3, N 6.4, or 6.5 instead, as applicable.

[1] ENSURE Precautions and Limitations in Section 3.0 have been reviewed.

Standard: Determines that Section 3.0 is complete per initial conditions.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If asked how to rotate computer screen, inform applicant to Right Click on Cue:

form and select Rotate Clockwise.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 2. 1-SI-0-10 Section 6.2 Critical Step?

[2] ENSURE Prerequisite Actions in Section 4.0 have been met.

N Standard: Determines that Section 4.0 is complete per initial conditions.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. 1-SI-0-10 Section 6.2 Critical Step? [3] OBTAIN the NuPOP for the applicable fuel cycle AND RECORD:

A. The NuPOP Report Number, Revision, Unit, and Cycle number (front N

cover of NuPOP):

Report___________ Rev____ Unit ____ Cycle_____

Standard: Report WCAP-18390 Rev_0__ Unit _1__ Cycle_16__

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 4. 1-SI-0-10 Section 6.2 Critical Step? [4] IF there is one or more rods not fully inserted, THEN RECORD:

A. The Maximum Stuck Rod Worth.

Appendix D Table D-1 (Coeffs.xls at the bottom of the N Shutdown Data tab), for Mode 2 below nuclear heating through Mode 5:

________pcm Standard: Applicant determines 1136 ppm from Table D-1.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 5. 1-SI-0-10 Section 6.2 Critical Step? NOTES

1) It is permissible to use a conservative RCS temperature to bound a potential plant cooldown. Remember that the Mode 4 SDM requirement is more limiting than the Mode 5 SDM requirement.

2) Number of immovable/untrippable rods refers to the actual number of immovable/untrippable rods, NOT the one that is assumed to be fully withdrawn from the definition of SDM N

[5] DETERMINE the following plant conditions:

A. Core average burnup: ________MWD/MTU (ICS computer point U7981)

B. Number of immovable/untrippable rods: ________

C. Minimum Tcold for the desired condition: ________oF D. RCS Boron Concentration CB: ________ppm A. Core average burnup: _998____MWD/MTU (ICS computer point U7981)

B. Number of immovable/untrippable rods: ___2____

Standard:

C. Minimum Tcold for the desired condition: ___547__oF D. RCS Boron Concentration CB: __1200___ppm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 6. 1-SI-0-10 Section 6.2 Critical Step? NOTE The conditions at which the Differential Boron Worth (DBW) value obtained in the following step (HZP, No Xe) might be different from the actual conditions. The use of this value results in a more conservative SDM requirement that will not match an equivalent REACTINW calculation, which is more exact.

[6] IF there are immovable/untrippable rods, THEN A. RECORD the Differential Boron Worth using burnup from Y

Step 6.2[5]A and RCS CB from Step 6.2[5]D:

Differential Boron Worth: ________pcm/ppm (See NuPOP Figure 6-22a

[Reactivity_Coefficients_and_Defects.xls on the Specific HZP DBW Point tab])

Step 6.2[5]A and RCS CB from Step 6.2[5]D:

Differential Boron Worth: _-5.66 (-5.6 to -5.7)___pcm/ppm (See NuPOP Standard:

Figure 6-22a [Reactivity_Coefficients_and_Defects.xls on the Specific HZP DBW Point tab])

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 7. 1-SI-0-10 Section 6.2 Critical Step? 6] IF there are immovable/untrippable rods, THEN B. CALCULATE the absolute value stuck rod correction

________ X ________ pcm / _________pcm/ ppm Y

(Step 6.2[5]B) (Step 6.2[4]A ) (Step 6.2[6]A)

Stuck rod correction (absolute value) = _________ ppm

___2___ X __1136__ pcm / ___-5.66 (-5.6 to -5.7)___pcm/ ppm Standard:

Stuck rod correction (absolute value) = __401.4 (405.1 to 398.6)__ ppm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 8. 1-SI-0-10 Section 6.2 Critical Step? [7] RECORD the (M-P)SDM from Unit 1 NOB Sheet A-3.

(M-P)SDM = ___________ ppm N

Standard: __120______ ppm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 9. 1-SI-0-10 Section 6.2 Critical Step? [8] CALCULATE required RCS CB A. DETERMINE UNCORRECTED Minimum Required CB for Shutdown Margin, from NuPOP Table 7-4 (Shutdown_Margin.xls from the Specific Point tab) using burnup of Y Step 6.2[5]A and temperature of Step 6.2[5]C:

UNCORRECTED Min Required CB = ________ppm Standard: UNCORRECTED Min Required CB = __832 (801 to 859)___ppm Performance: SATISFACTORY UNSATISFACTORY 832 ppm was extrapolated. The difference between stated values on table 7-4 ranged Examiner Notes: from 37 to 62 ppm. The band (+/- 31 ppm) was established at half the largest value (62 ppm).

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 10. 1-SI-0-10 Section 6.2 Critical Step? [8] CALCULATE required RCS CB B. CALCULATE the Required CB:

__________ + _________ + ________

Y (Step 6.2[6]B ) (Step 6.2[7]) (Step 6.2[8]A)

Required CB = _________ ppm B. CALCULATE the Required CB:

_401.4 (405.1 to 398.6)_ + ___120___ + __832 (801 to 859)___

Standard: (Step 6.2[6]B ) (Step 6.2[7]) (Step 6.2[8]A)

Required CB = __1353.4 (1319 to 1384)___ ppm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 11. 1-SI-0-10 Section 6.2 Critical Step? [8] CALCULATE required RCS CB C. VERIFY that RCS CB in Step 6.2[5]D is greater than or equal to the Required CB in Step 6.2[8]B (Acc Crit. 5.1A or 5.1B).

Y ________

Standard: Examinee determines that RCS CB is less than Required CB.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 12. 1-SI-0-10 Section 6.2 Critical Step? NOTE It is the responsibility of Operations to ensure that dilution protection is adequate for plant conditions Dilution protection is ensured by either

1) Maintaining a Reactor Coolant Pump (RCP) in operation for RCS mixing,

2) Performing 1-SI-62-1, Uncontrolled Boron Dilution, to isolate dilution flow paths,

3) Stopping ALL Primary Water pumps and issuing a HOLD ORDER for administrative control,

4) When at 0 MWD/MTU, maintaining RCS boron concentration greater N than the Refueling Boron Concentration specified in the COLR (keff <

0.95),

5) Maintaining Shutdown Banks fully withdrawn (> 1000 pcm), or

6) Maintaining RCS boron concentration greater than or equal to the value calculated within Attachment 1.

[9] IF dilution protection is needed via boron analysis, THEN PERFORM Attachment 1.

Dilution protection via boron analysis is NOT required in accordance with initial Standard:

conditions.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 13. 1-SI-0-10 Section 6.2 Critical Step?

[10] OBTAIN review of calculations, results, and Acceptance Criteria by a Y task qualified individual. An STA, SRO, or RXE may perform this review.

Applicant reviews acceptance criteria. Determines that SDM does not meet Standard: minimum requirements of TS 3.1.5 as referenced to the COLR ( > 1.6% k/k.) in modes 1 & 2.

Performance: SATISFACTORY UNSATISFACTORY A note prior to step 1 directs performance of section 6.3, 6.4 or 6.5 if section 6.2 Examiner Notes:

doesnt pass acceptance criteria.

IF the examinee determines that the acceptance criteria is not met (it will not be),

Cue: inform them that for this JPM, Section 6.2 will be the only procedure section of 1-SI-0-10 performed. Base all actions on results received.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Step # 14. TS 3.1.5 Critical Step? Applicant determines that TS 3.1.5, Rod Group Alignment Limits, Condition A. is applicable.

Verify SDM within the limits of the COLR (does not).

OR Y Initiate boron to restore SDM within 1 hr.

AND Be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In accordance with TS 3.1.5, the applicant determines that Boration must be initiated Standard:

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the plant must be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Unless specified otherwise below, the JPM is terminated when the examinee returns the JPM Briefing sheet to the examiner.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM KEY NuPOP

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM NuPOP

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM NuPOP

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM 1-SI-0-10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM NOB

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM COLR

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM TS 3.1.5

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

Unit 1 is at full power (600 EFPH) with all control systems in automatic except rod control, which is in manual.

Core average burnup = 998 MWD/MTU Boron concentration was 1200 ppm 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.

Control Bank D is at 210 steps.

RCS Tave is 587 °F.

Minimum Tcold will be 547 oF 5 minutes ago rods M-4 and M-12 were declared inoperable and immovable due to failure to move during the Movable Control Assembly Surveillance.

Rods M-4 and M-12 are aligned 4 steps from the rest of the rods in their group.

Prerequisites of Section 4.0 are complete.

Dilution protection via boron analysis is NOT required.

INITIATING CUES:

As the SRO, you are directed to:

Perform the Shutdown Margin Surveillance in accordance with 1-SI-0-10 Section 6.2 (Use NOB Values).

Determine ALL (if any) actions required due to plant conditions.

Watts Bar Nuclear Plant 2020301 NRC EXAM Administrative JPM 2S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Task: Determine Shift Staffing Requirements Alternate Path: N/A Facility JPM #: N/A Safety Function: N/A

Title:

Conduct of Operations K/A 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations. (Reference Potential)

Rating(s): 3.9 CFR: 41.10 / 43.5 / 45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

OPDP-1 R 46 Task Number: OPDP-1

Title:

Conduct of Operations Task Standard: The applicant:

1. Determines minimum operations staffing for a shift based on plant conditions.

Validation Time: 15 minutes Time Critical: Yes No X Page 2 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

OPDP-1 R46 Page 4 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM READ TO OPERATOR DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

Unit 1 is at 100% power Unit 2 is in Mode 6 and currently moving fuel The shift consists of the following personnel:

o 3 Senior Reactor Operators, one of which is the Shift Manager o 1 STA (Non-licensed) o 4 Unit Operators o 9 Non-Licensed Operators INITIATING CUES:

As the SRO, you are directed to:

Determine if the Operations MINIMUM shift staffing requirements for the current plant conditions are met, and if not, explain why.

Page 5 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Start Time:

Step # 1. OPDP-1 Critical Step?

Operator selects the correct procedure to determine shift staffing levels.

N Standard: Operator locates OPDP-1, Conduct of Operations Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Step # 2. OPDP-1 Critical Step?

Operator determines minimum staffing IAW OPDP-1, Attachment 1 Y

Standard:

Operator determines that the shift requires an additional SRO to fill the Incident Commander position AND an additional SRO to act as the Fuel Handling Supervisor for Unit 2.

Performance: SATISFACTORY UNSATISFACTORY Examiner Total number of required SROs = 5 Notes: (1 Shift Manager, 2 NUSOs, 1 Incident Commander, 1 Fuel Handling Supervisor)

Cue:

Comments:

Terminating Cue: Unless specified otherwise below, the JPM is terminated when the examinee returns the JPM Briefing sheet to the examiner.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM KEY

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S 2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

Unit 1 is at 100% power Unit 2 is in Mode 6 and currently moving fuel The shift consists of the following personnel:

o 3 Senior Reactor Operators, one of which is the Shift Manager o 1 STA (Non-licensed) o 4 Unit Operators o 9 Non-Licensed Operators INITIATING CUES:

As the SRO, you are directed to:

Determine if the Operations MINIMUM shift staffing requirements for the current plant conditions are met, and if not, explain why.

Watts Bar Nuclear Plant 2020301 NRC EXAM Administrative JPM 3S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Task: Determine a Technical Specification Completion Time Extension Alternate Path: N/A Facility JPM #: Bank Safety Function: N/A

Title:

Equipment Control K/A 2.2.37 Ability to determine operability or availability of safety related equipment.

Rating(s): 4.6 CFR: 43.2 / 43.5 / 45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

Technical Specifications Task Number: SRO-113-TI-12-011

Title:

Based on the event in progress, take corrective actions to mitigate the consequences of the abnormal/emergency condition utilizing the proper procedures.

Task Standard: Applicant determines:

1.) The 1B-B SI pump must be declared OPERABLE by 6/6/2020 at 0700 in order to prevent a unit shutdown.

2.) Assuming the 1B-B SI pump is NOT repaired the unit must be in Mode 4 by 6/6/2020 at 1900.

Validation Time: 15 minutes Time Critical: Yes No X

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Laptop Computer NRC Reference Disk Technical Specifications Note: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM READ TO OPERATOR DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

1. Unit 1 is at 100% power.

2. Todays date is June 4, 2020. The time is 1000.

3. On June 2, 2020 at 0700, the 1A-A Safety Injection (SI) pump was declared INOPERABLE.

4. LCO Action Statement 3.5.2 Condition A, One or more trains inoperable AND at least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.

5. The 1B-B SI pump was declared INOPERABLE today at 0800, and LCO 3.0.3 was entered.

6. 1A-A Safety Injection pump was declared OPERABLE today at 0900.

INITIATING CUES:

You are directed to determine the following:

1. What is the latest time that the 1B-B SI pump can be declared OPERABLE to prevent entry into LCO 3.5.2 Condition B?

DATE:_____________________ TIME: _________________________

2. Assuming the 1B-B SI pump was NOT able to be repaired, what is the latest time that the unit must be in MODE 4?

DATE:_____________________ TIME: _________________________

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Start Time:

Step # 1. Technical Specification Critical Step? The applicant date and time at which the 1B-B SI pump must be declared OPERABLE.

Y Applicant determines from Tech Spec 1.3, Completion Times, that the total Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is added to the initial entry into LCO 3.5.2 Standard: Condition A. Initial entry occurred on June 2, 2020 at 0700.

The1B-B SI pump must be restored to OPERABLE status before 0700 on 6/6/2020.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Step # 2. Technical Specification Critical Step?

The applicant determines the time when Unit 1 must be in Mode 4.

Y If the 1B-B SI pump cannot be restored to OPERABLE status, the Unit must Standard:

be in Mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or before 1900 on 6/6/2020.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Unless specified otherwise below, the JPM is terminated when the examinee returns the JPM Briefing sheet to the examiner.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM 3S Key DO NOT HAND TO APPLICANT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Key

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 Conditions:

1. Unit 1 is at 100% power.

2. Todays date is June 4, 2020. The time is 1000.

3. On June 2, 2020 at 0700, the 1A-A Safety Injection (SI) pump was declared INOPERABLE.

4. LCO Action Statement 3.5.2 Condition A, One or more trains inoperable AND at least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.

5. The 1B-B SI pump was declared INOPERABLE today at 0800, and LCO 3.0.3 was entered.

6. 1A-A Safety Injection pump was declared OPERABLE today at 0900.

INITIATING CUES:

You are directed to determine the following:

1. What is the latest time that the 1B-B SI pump can be declared OPERABLE to prevent entry into LCO 3.5.2 Condition B?

DATE:_____________________ TIME: _________________________

2. Assuming the 1B-B SI pump was NOT able to be repaired, what is the latest time that the unit must be in MODE 4?

DATE:_____________________ TIME: _________________________

Watts Bar Nuclear Plant 2020301 NRC EXAM Administrative JPM 4S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Task: Calculate The Maximum Permissible Stay Time Within Emergency Dose Limits Alternate Path: N/A Facility JPM #: Bank Safety Function: N/A

Title:

Radiation Control K/A 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation or radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits.

Rating(s): 3.8 CFR: 43.4 / 45.10 Evaluation Method: Simulator In-Plant Classroom X

References:

EPIP-15, Emergency Exposure Guidelines, R 20 Task Number: AUO-119-SSP-5.01-001

Title:

Control personnel radiation exposure Task Standard:

The applicant:

1. Calculates the dose expected for Task #1 through Task #3.

2. Determines that Tasks #1 through #3 can be performed without exceeding equipment protection emergency dose limits.

3. Calculates the maximum allowable stay time for Task #4 to be 18 minutes.

Validation Time: 15 minutes Time Critical: Yes No X

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Laptop Computer.

NRC REFERENCE DISK.

• NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM READ TO OPERATOR DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A GENERAL EMERGENCY has been declared on Unit 1.

2. 1A-A RHR Pump is air bound and must be vented per 1-AOI-14, Loss of RHR Shutdown Cooling.

3. The TSC has requested that 1B-B RHR Pump motor bearing oil levels be checked and filled as required after restoring 1A-A RHR Pump, suggests using the same Repair Team.

4. The tasks are listed in the table below, and estimated times (including transit to and from location) and dose rates have been provided.

5. Each Task must be performed in the order listed.

6. You have been selected to perform the task.

(Continued on next page)

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM INITIATING CUES:

The Site Emergency Director (SED) directs you to perform the following with the information provided:

1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE.

Time Dose Expected Task # Location/Task Description allowed/reqd Rate Dose (minutes) (R/hr) 1 Elevation 676 1A-A RHR Pump Room /Close RHR pump 10 3 discharge isolation valve 1-ISV-74-520 2 #4 Accumulator Room / Vent common suction piping 1-TV 20 18 543, 1-TV-74-504 3 Elevation 676 1A-A RHR Pump Room /Vent 1A-A RHR Pump 40 3 discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 4 Elevation 676 1B-B RHR Pump Room / Inspect 1B-B RHR pump 5 motor bearing oil levels and fill as required.

2. Answer the following:

Can you perform Tasks #1 through #3 without exceeding the equipment protection emergency dose limit? (Circle one)

YES / NO IF YES, then enter the permitted stay time for Task #4.

IF NO, then state the task #s that can be performed, if any

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Start Time:

Step # 1.

Critical Step?

Applicant calculates the EXPECTED DOSE for Tasks #1 Through #3.

Y Applicant determines the following:

EXPECTED DOSE for TASK # 1 (10 minutes/60 minutes/hour) x 3 R/hr = 0.5 R EXPECTED DOSE for TASK #2 (20 minutes/60 minutes/hr) x 18 R/hr = 6.0 R Standard:

EXPECTED DOSE for TASK #3 (40 minutes/60 minutes/hr) x 3 R/hr = 2.0 R TOTAL EXPECTED DOSE for TASKS #1, #2 and #3 is 8.5 R.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Step # 2. EPIP-15 Critical Step?

Applicant answers the question Can you perform Tasks #1 through #3 Y without exceeding the equipment protection emergency dose limit?

Applicant determines that the total expected dose of 8.5 REM is less Standard: than the 10 Rem limit for saving equipment. Circles YES on the APPLICANT CUE SHEET.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Step # 3.

Critical Step?

Applicant determines stay time limit for Task #4.

Y Applicant subtracts 8.5 R from the limit of 10 R and determines the remaining dose to be 1.5 R.

Applicant divides 1.5 R by 5 R/hr (the expected dose for Task #4) and Standard:

determines the stay time to be 0.3 hrs. Applicant multiplies 0.3 hr x 60 minutes/hr and determines a maximum stay time of 18 minutes for Task #4.

Applicant enters 18 minutes for permitted stay time for Task #4.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Unless specified otherwise below, the JPM is terminated when the examinee returns the JPM Briefing sheet to the examiner.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM 4S Key DO NOT HAND TO APPLICANT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Key

1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE.

Time Dose Expected Task # Location/Task Description allowed/reqd Rate Dose (minutes) (R/hr) 1 Elevation 676 1A-A RHR Pump Room /Close RHR pump 10 3 0.5 discharge isolation valve 1-ISV-74-520 2 #4 Accumulator Room / Vent common suction piping 1-TV 20 18 6 543, 1-TV-74-504 3 Elevation 676 1A-A RHR Pump Room /Vent 1A-A RHR Pump 40 3 2 discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 4 Elevation 676 1B-B RHR Pump Room / Inspect 1B-B RHR pump 18 5 1.5 motor bearing oil levels and fill as required.

2. Answer the following:

Can you perform Tasks #1 through #3 without exceeding the equipment protection emergency dose limit? (Circle one)

YES / NO IF YES, then enter the permitted stay time for Task #4. 18 MINUTES .

IF NO, then state the task #s that can be performed, if any. N/A.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A GENERAL EMERGENCY has been declared on Unit 1.

2. 1A-A RHR Pump is air bound and must be vented per 1-AOI-14, Loss of RHR Shutdown Cooling.

3. The TSC has requested that 1B-B RHR Pump motor bearing oil levels be checked and filled as required after restoring 1A-A RHR Pump, suggests using the same Repair Team.

4. The tasks are listed in the table below, and estimated times (including transit to and from location) and dose rates have been provided.

5. Each Task must be performed in the order listed.

6. You have been selected to perform the task.

(Continued on next page)

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4S 2020-301 NRC EXAM INITIATING CUES:

The Site Emergency Director (SED) directs you to perform the following with the information provided:

1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE.

Time Dose Expected Task # Location/Task Description allowed/reqd Rate Dose (minutes) (R/hr) 1 Elevation 676 1A-A RHR Pump Room /Close RHR pump 10 3 discharge isolation valve 1-ISV-74-520 2 #4 Accumulator Room / Vent common suction piping 1-TV 20 18 543, 1-TV-74-504 3 Elevation 676 1A-A RHR Pump Room /Vent 1A-A RHR Pump 40 3 discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 4 Elevation 676 1B-B RHR Pump Room / Inspect 1B-B RHR pump 5 motor bearing oil levels and fill as required.

2. Answer the following:

Can you perform Tasks #1 through #3 without exceeding the equipment protection emergency dose limit? (Circle one)

YES / NO IF YES, then enter the permitted stay time for Task #4.

IF NO, then state the task #s that can be performed, if any

Watts Bar Nuclear Plant 2020301 NRC EXAM Administrative JPM 5S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Task: REP Classification and State Notification on River Level Low - NOUE Alternate Path: N/A Facility JPM #: 3-OT-J1G-0-1AS-R2 Safety Function: N/A

Title:

Emergency Plan K/A 2.4.29 Knowledge of the emergency plan implementing procedures.

Rating(s): 4.4 CFR: 41.10 / 43.5 / 45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

EPIP-1, Emergency Plan Classification Logic, R 51 EPIP-2, Notification of Unusual Event, R 41 Task Number: SRO-113-EPIP-001

Title:

Classify emergency events requiring Emergency Plan implementation Task Standard: The applicant:

1. Classifies the event as an NOUE based on EAL 5.5 - River Level LOW.

2. Declares the event within 15 minutes of task start.

3. Completes EPIP-2, Appendix A within 15 minutes of declaration.

Validation Time: 30 minutes Time Critical: Yes X No Page 2 of 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==================================================================================

COMMENTS Page 3 of 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Tools/Equipment/Procedures Needed:

Laptop Computer NRC REFERENCE DISK

• NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

Page 4 of 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM READ TO OPERATOR DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 and Unit 2 Conditions:

1. Both Units = 100% power

2. It has not rained for 6 months

3. You are the Unit 1 US

4. Security notifies the Control Room that tremors have been felt within the protected area.

5. OBE SPECTRA EXCEEDED, Window 166-D is DARK.

6. You receive a phone call on the SM phone from River System Operations: They tell you that a River Level Control system has failed downstream of WBN and that River Reservoir level has dropped rapidly in the past hour to 670 ft.

INITIATING CUES:

1. Classify the event per the REP EPIPs and fill out Appendix A using the appropriate procedure.

2. Do not use Emergency Coordinator Discretion in determination.

This JPM is "Time Critical" Page 5 of 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Start Time:

Step # 1. EPIP-1 Critical Step?

Refers to EPIP-1 to determine the level of the event.

Y Performer refers to EPIP-1 and declares an NOUE based on HU3 (5) - River Reservoir Standard: level < 673 feet as reported by River Operations and implements EPIP-2, Notification of Unusual Event.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM EPIP-1 Wallboard HOT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Step # 2. EPIP-2 Critical Step? NOTES

1) Procedure steps can be performed concurrently.

2) All steps within this procedure can be delegated unless otherwise specified.

3) A STA or SRO should perform a peer review of Appendix A completion.

Y 3.1 State of Tennessee Notification and Confirmation

[1] NOTE time of Notification of Unusual Event classification _________

Examinee records the time at which the NOUE was declared (Critical) and proceeds Standard:

to Appendix A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Step # 3. EPIP-2, Appendix A Critical Step? 3.1 State of Tennessee Notification and Confirmation

[2] COMPLETE Appendix A, Notification of Unusual Event Initial Y Notification Form Appendix A (Page 1 of 1)

Notification of Unusual Event Initial Notification Form

1. X This is a Drill This is an Actual Event - Repeat - This is an Actual Event

2. The SED at Watts Bar has declared a NOTIVICATION OF UNUSUAL EVENT.

3. IC DESIGNATOR: ___HU3 (5)_______ (USE ONLY ONE IC DESIGNATOR)

4. Radiological conditions: (Check one under both Airborne and Liquid column.)

Airborne Releases Offsite Liquid Releases Offsite X Minor releases within federally X Minor releases within federally approved Standard: approved limits limits Releases above federally approved Releases above federally approved limits limits Release information not known (Tech Release information not known (Tech Specs/ODCM) Specs/ODCM)

5. Event Declared: Time: _Step 1 Time_____ Date: __Todays Date____

Eastern Time

6. Protective Action Recommendation: X None Completed By (SED) ___Performers Signature________

Peer Review By: ___________________________________

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: All data in RED in the Key must be accurately marked to pass this JPM.

Cue: If asked for peer check, then reply: a peer check has been performed.

Comments:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Terminating Cue: The JPM is terminated when the examinee completes EPIP-2, Appendix A.

Stop Time:

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM Handout Package for Applicant

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2020-301 NRC EXAM APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

Unit 1 and Unit 2 Conditions:

1. Both Units = 100% power

2. It has not rained for 6 months

3. You are the Unit 1 US

4. Security notifies the Control Room that tremors have been felt within the protected area.

5. OBE SPECTRA EXCEEDED, Window 166-D is DARK.

6. You receive a phone call on the SM phone from River System Operations: They tell you that a River Level Control system has failed downstream of WBN and that River Reservoir level has dropped rapidly in the past hour to 670 ft.

INITIATING CUES:

1. Classify the event per the REP EPIPs and fill out Appendix A using the appropriate procedure.

2. Do not use Emergency Coordinator Discretion in determination.

This JPM is "Time Critical"