Text

CP-2021-08-FINAL Written Exam
	ML21285A038
Person / Time
Site:	Comanche Peak
Issue date:	09/23/2021
From:	Heather Gepford; Operations Branch IV
To:	; Vistra Energy
References
	Download: ML21285A038 (557)
	v • d • e

ANSWER KEY CPNPP 2021 NRC SRO Exam 1 B 26 D 51 D 76 B 2 A 27 C 52 D 77 A 3 D 28 B 53 A 78 D 4 A 29 D 54 A 79 C 5 D 30 D 55 D 80 D 6 B 31 C 56 A 81 C 7 C 32 A 57 D 82 C 8 A 33 B 58 B 83 C 9 C 34 B 59 C 84 B 10 A 35 A 60 C 85 C 11 B 36 D 61 B 86 B 12 D 37 A 62 C 87 A 13 B 38 B 63 C 88 B 14 B 39 B 64 D 89 C 15 C 40 C 65 D 90 B 16 A 41 C 66 D 91 B 17 D 42 B 67 B 92 B 18 D 43 A 68 C 93 D 19 A 44 C 69 A 94 D 20 A 45 C 70 C 95 A 21 C 46 A 71 C 96 D 22 B 47 A 72 B 97 D 23 D 48 A 73 A 98 D 24 D 49 D 74 D 99 A 25 D 50 C 75 D 100 C RO Overall SRO A - 19 A - 23 A-4 B - 16 B - 23 B-7 C - 18 C - 25 C-7 D - 22 D - 29 D-7 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 003.G.2.2.39 Level of Difficulty: 3 Importance Rating 3.9 Reactor Coolant Pump: Knowledge of less than or equal to one hour Technical Specification action statements for systems.

Question # 1 Given the following conditions:

Unit 1 is in MODE 3, with the RCS temperature at 400oF Reactor Trip Breakers are closed Rod Drive MG sets are operating An RCS dilution is in progress In accordance with TS 3.4.5, RCS Loops - MODE3, a MINIMUM of __(1)__ RCPs must be in operation.

If one of the minimum number of operating RCPs were to trip, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months __(2)__.

A. (1) two (2) commence Emergency Boration B. (1) two (2) make the Rod Control System incapable of withdrawal C. (1) four (2) commence Emergency Boration D. (1) four (2) make the Rod Control System incapable of withdrawal Answer: B Page 1 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of a one-hour TS associated with the operation of the RCPs.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since various TS require boration be commenced in response to actions not being met.

B. Correct. First part is correct. Under the given conditions, with a dilution in progress, two RCS loops are required to be operating. Second part is correct. If one of the two operating loops stops operating, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore it to operating or make the rod control system incapable of withdrawal.

C. Incorrect. First part is incorrect, but plausible (see D). Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible since MODES 1 and 2, TS 3.4.4, require all four loops operating. Second part is correct (see B).

Technical Reference(s) TS 3.4.5 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given RCS parameter indications and plant conditions, ASSESS from memory any required TS/TR entries, including any actions which must be completed within one hour in accordance with Technical Specifications or TRM.

(SYS.RC1.OB06)

Question Source: Bank #

Modified Bank # 62575 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 62575 Revision:

Page 3 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 62575 Revision:

Page 4 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.4.5 Revision: 156 Page 5 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.4.5 Revision: 156 Page 6 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 004.K3.04 Level of Difficulty: 3 Importance Rating 3.7 Chemical and Volume Control: Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: RCPS Question # 2 Given the following conditions:

Unit 1 Reactor power is 3%

ANY RCP SEAL WTR INJ FLO LO (5A-1.6) is in alarm RCP SEAL WTR INJ FILT 1 P HI (5A-2.6) is in alarm Seal injection flow is 0 gpm ABN-101, REACTOR COOLANT PUMP TRIP/MALFUNCTION, has been initiated RCPs are required to be tripped if CCW Thermal Barrier heat exchanger flow is not a MINIMUM of __(1)__.

Seal injection is isolated in order to prevent thermal shock to the seals which could directly result in __(2)__.

A. (1) 35 gpm (2) excessive RCS leakage B. (1) 35 gpm (2) voiding the CCW system C. (1) 64 gpm (2) excessive RCS leakage D. (1) 64 gpm (2) voiding the CCW system Answer: A Page 7 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of a loss of seal injection flow from CVCS to the RCPs Explanation:

A. Correct. First part is correct. Per ABN-101, Section 7 (Loss of Seal Injection), if CCW is less than 35 gpm, you are directed to section 9 which will direct tripping the reactor, tripping RCPs and isolating seal injection and CCW thermal barrier return from the RCPs. Second part is correct.

Thermal shocking the seals could result in seal damage (not seating correctly) which could result in excessive leakage.

B. Incorrect. First part is correct (See A). Second part is incorrect, but plausible because the CCW return valve from the RCPs, HV-4709, is manually closed on a loss of seal injection and CCW to the RCPs to prevent voiding in the CCW system.

C. Incorrect. First part is incorrect, but plausible because CCW flow at 64 gpm will result in isolating the CCW thermal barrier HX. Second part is correct (See A).

D. Incorrect. First part is incorrect but plausible (see C). Second part is incorrect but plausible (see B).

Technical Reference(s) ABN-105 Attached w/ Revision # See ABN-101 Comments / Reference RCS Study Guide Proposed references to be provided during examination:

Learning Objective: DISCUSS the response for a Loss of Seal Injection in accordance with ABN-101, Reactor Coolant Pump Trip/Malfunction. (ABN.101.OB07)

Question Source: Bank #

Modified Bank # 58153 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 8 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 58153 Revision:

Page 9 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 58153 Revision:

Page 10 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-105 Revision: 8 Page 11 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-105 Revision: 8 Page 12 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-101 Revision: 13 Page 13 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-101 Revision: 13 Page 14 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

RCS Study Guide Revision: 00-0000 Page 15 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 005.A1.02 Level of Difficulty: 2 Importance Rating 3.3 Residual Heat Removal: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: RHR flow rate Question # 3 Given the following conditions:

RHR is in service in Mode 5 Instrument Air is lost to 2-FCV-618, RHR HX 1 BYP FLO ABN-104, Residual Heat Removal System Malfunction, Section 4.0, Mode 4, 5 or 6 Loss of RCS Temperature/flow Control RCS Filled, is in progress 2-FCV-618 fails __(1)__ when air is lost.

ABN-104 directs manual control of the RHR HX Bypass and Outlet valves to maintain a MINIMUM design RHR flow of __(2)__ gpm.

A. (1) OPEN (2) 2900 B. (1) OPEN (2) 3800 C. (1) CLOSED (2) 2900 D. (1) CLOSED (2) 3800 Answer: D Page 16 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of flow requirements for the RHR system.

Explanation:

A. Incorrect. First part is incorrect because the valve fails closed. It is plausible because if it were the RHR HX Outlet Valve, it would be correct. Second part is incorrect because the minimum design flow to be established is 3800 gpm. It is plausible because it were asking about the minimum CCW flow through the HX, it would be correct.

B. Incorrect. First part is incorrect but plausible (see A). Second part is correct. ABN-104 directs establishing between 3800 and 4000 gpm RHR flow.

C. Incorrect. First part is correct. The RHR HX Bypass Valve fails closed upon a loss of air.

Second part is incorrect but plausible (see A).

D. Correct. First part is correct (see C). Second part is correct (see B).

Technical Reference(s) ABN-301 Attached w/ Revision # See ABN-104 Comments / Reference DBD ME-260 Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Loss of RCS Temperature/Flow Control in accordance with ABN-104, Residual Heat Removal System Malfunctions.

(ABN.104.OB04)

Question Source: Bank # 81933 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 17 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-301 Revision: 14 Page 18 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-104 Revision:

Page 19 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

DBD ME-260 Revision: 30 Page 20 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 006.K1.02 Level of Difficulty: 3 Importance Rating 4.3 Emergency Core Cooling: Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: ESFAS Question # 4 Given the following conditions:

Unit 1 is operating at 100% power Train A equipment is running A slow transfer of both safeguards busses to their alternate power supply occurs

__(1)__ will be started as a result of the transfer.

The PDP cannot be started following actuation of the Blackout Sequencers until the BOS

__(2)__ clears.

A. (1) Both CCPs (2) Operator Lockout B. (1) Both CCPs (2) Automatic Lockout C. (1) ONLY CCP 1-01 (2) Operator Lockout D. (1) ONLY CCP 1-01 (2) Automatic Lockout Answer: A Page 21 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the relationship between the ESFAS blackout sequencer and the CCPs.

Explanation:

A. Correct. First part is correct. Both CCPs are started by the sequencers. Second part is correct.

The PDP is locked out from starting until the operator lockout clears.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible because the PDP is prevented from starting by the operator lockout, not the automatic lockout. The operator lockout clears when the sequence completes timing and the automatic lockout clears when the operator resets the BOS.

C. Incorrect. First part is incorrect, but plausible since only CCP 1-01 was running prior to the transfer and it could be thought that only previously operating equipment would be started.

Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-602 Attached w/ Revision # See SI and BO Sequencer Study Guide Comments / Reference CVCS Study Guide ABN-601 Proposed references to be provided during examination:

Learning Objective: PREDICT the response of the instrumentation and controls of the Safety Injection and Blackout Sequencers in accordance with CP-0575-001, Solid State Safeguards Sequencers and associated Automation Industries drawings. (SYS.

ES3.OB05)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 22 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-602 Revision: 8 Page 23 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SI and BO Sequencer Study Guide Revision: 6-10-2011 Page 24 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SI and BO Sequencer Study Guide Revision: 6-10-2011 Page 25 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

CVCS Study Guide Revision: 00-0000 Page 26 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-601 Revision: 16 Page 27 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 007.K5.02 Level of Difficulty: 2 Importance Rating 3.1 Pressurizer Relief/Quench Tank: Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR Question # 5 Given the following conditions:

After being used to draw a vacuum in the RCS, the PRT has been isolated from the PRZR RCS pressure is 5 psia RCS and PRZR temperatures are equalized at 130ºF Actual PRZR level is 50%

Which of the following describes the PREFERRED method of establishing a steam bubble in the PRZR in accordance with SOP-101A, Reactor Coolant System?

Adjust Charging and Letdown to __(1)__.

Energize PRZR heaters to heat up the PRZR, establishing a steam bubble at approximately

__(2)__ in the PRZR.

A. (1) raise PRZR level to 100%

(2) 212ºF B. (1) raise PRZR level to 100%

(2) 162ºF C. (1) maintain PRZR level constant (2) 212ºF D. (1) maintain PRZR level constant (2) 162ºF Answer: D Page 28 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the method used to establish a bubble in the pressurizer.

Explanation:

A. Incorrect. First part is incorrect, but plausible since this is similar to an alternate method of establishing a bubble while solid. Second part is incorrect, but plausible since 212oF is saturation temperature for normal atmospheric pressure.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. Per SOP-101, during vacuum fill of the RCS a bubble in the PRZR is established while the RCS is at a vacuum. Charging and Letdown are adjusted as needed to maintain level and pressure constant in preparation for establishing a bubble. Second part is correct. The bubble is formed at 162oF which is saturation for the 5 psia condition established.

Technical Reference(s) SOP-101 Attached w/ Revision # See Steam Tables Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: DISCUSS the steps required to fill the RCS and establish a pressurizer bubble in accordance with SOP-101A, Reactor Coolant System. (IPO.001.OB01)

Question Source: Bank # 23551 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 29 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-101A Revision: 18 Page 30 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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SOP-101A Revision: 18 Page 31 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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SOP-101A Revision: 18 Page 32 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Steam Tables Revision:

Page 33 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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SOP-101 Revision: 18 Page 34 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 008.A2.03 Level of Difficulty: 2 Importance Rating 3.0 Component Cooling Water: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low CCW temperature Question # 6 Given the following conditions:

Reactor power = 100%

1-ALB-1, 1.7, SSW TRN A/B HDR PRESS LO, alarms ABN-501, Station Service Water System Malfunction, is entered for the low SSW header pressure condition CCW 1-01 HX outlet temperature is slowly rising In accordance with ABN-501, when CCW HX Outlet Temperature FIRST reaches __(1)__,

CCW Pump 1-01 is placed in PULL-OUT.

A subsequent trip of SSW Pump 1-02 would require __(2)__.

A. (1) 122oF (2) a Reactor Trip ONLY B. (1) 122oF (2) a Reactor Trip and Trip of ALL RCPs C. (1) 140oF (2) a Reactor Trip ONLY D. (1) 140oF (2) a Reactor Trip and Trip of ALL RCPs Answer: B Page 35 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the CCW temperature limits and the actions to be taken in the event the limits are exceeded.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since CCW Pump 1-02 remains running supplying the RCPs but with no SSW flow on the same train the plant is required to be tripped and the RCPs secured.

B. Correct. First part is correct. If CCW HX 1-01 outlet temperature reaches 122oF during these conditions, CCW pump 1-01 is to be stopped. Second part is correct. If both CCW pump 1-01 and SSW pump 1-02, opposite trains, are not operating, cooling is lost to CCW loads and the Reactor and RCPs are to be tripped.

C. Incorrect. First part is incorrect, but plausible, because 140oF is from the design of the system (to lower RCS temperature from 350oF to 140oF in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ). Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) ALM-0011A Attached w/ Revision # See ABN-501 Comments / Reference ABN-502 Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to Station Service Water Header Pressure Low in accordance with ABN-501, Station Service Water System Malfunction.

(ABN.501.OB102)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 36 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0011A Revision: 10 Page 37 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-501 Revision: 10 Page 38 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-501 Revision: 10 Page 39 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-502 Revision: 11 Page 40 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 010.K5.01 Level of Difficulty: 3 Importance Rating 3.5 Pressurizer Pressure Control: Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:

Determination of condition of fluid in PZR, using steam tables Question # 7 Given the following conditions:

PRZR Pressure indicates 335 psig A malfunction in CVCS causes an insurge to the PRZR, resulting in level rising 4%

PRZR liquid space temperature indicates 400ºF during the insurge During the insurge, the PRZR liquid space is subcooled by approximately __(1)__.

Any pressure rise during the insurge into the PRZR is limited by __(2)__.

A. (1) 23oF (2) steam condensing into a liquid B. (1) 23oF (2) liquid flashing to steam C. (1) 32oF (2) steam condensing into a liquid D. (1) 32oF (2) liquid flashing to steam Answer: C Page 41 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring ability to determine the amount of subcooling in the pressurizer using steam tables.

Explanation:

A. Incorrect. First part is incorrect, but plausible since this value would be obtained if 335 psig is converted incorrectly to a value of 320 psia which has a saturation temperature of 423oF. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since this is the dynamics that occur on an outsurge and not an insurge.

C. Correct. First part is correct. 335 psig is equivalent to approximately 350 psia and saturation temperature for this pressure is approximately 432oF. With temperature indication of 400oF, it is subcooled by 32oF. Second part is correct. A pressure rise from an insurge into the Pressurizer is limited by steam condensing into liquid.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) Steam Tables Attached w/ Revision # See Pressurizer Pressure/Level Study Guide Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: DESCRIBE the instrumentation and controls of the Pressurizer Pressure Control System including the system response in accordance with the CPNPP FSAR and DBD-ME-250, Reactor Coolant System. (SYS.PP1.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 42 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Steam Tables Revision:

Page 43 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Pressurizer Pressure/Level Study Guide Revision: 00-0000 Page 44 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 012.K6.06 Level of Difficulty: 2 Importance Rating 2.7 Reactor Protection: Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Sensors and detectors Question # 8 Given the following conditions:

PRZR level transmitter LT-459 failed high (100%)

70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months later the channel is being tripped The NCT switch LS/0459 BS-1 is in NORMAL When the I&C Technician takes the Master Test Card (NMT) switch to CLOSED for LT-459:

LI-459, PRZR Level Channel I will indicate __(1)__.

The TSLB for PRZR LVL HI LB-459 will __(2)__.

A. (1) 0%

(2) remain LIT B. (1) 0%

(2) change from DARK to LIT C. (1) 100%

(2) remain LIT D. (1) 100%

(2) change from DARK to LIT Answer: A Page 45 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how a failed transmitter will affect the reactor protection system indication.

Explanation:

A. Correct. First part is correct. Per ABN-706, indication will go to 0% as the transmitter is disconnected from the circuitry. Second part is correct. TSLB would light if dark, but TSLB PRZR LVL HI LB-459 was already lit from the failure high >92%.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible because TSLB PRZR LVL HI LB-459 would light if dark, but it is already lit from the high failure.

C. Incorrect. First part is incorrect, but plausible because the indication was at 100% already, but will go to 0% when NMT is closed. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-706 Attached w/ Revision # See 7300 Process Lesson Plan Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the 7300 Process Control system and PREDICT the system response in accordance with DBD-EE-021, Reactor Protection and NSSS Related Control Systems and Westinghouse Drawings 7247D05. (SYS.IC3.OB04)

Question Source: Bank # 19173 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 46 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-706 Revision: 8 Page 47 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-706 Revision: 8 Page 48 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

7300 Process Lesson Plan Revision: 00-0000 Page 49 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

7300 Process Lesson Plan Revision: 00-0000 Page 50 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 013.K2.01 Level of Difficulty: 3 Importance Rating 3.6 Engineered Safety Features Actuation: Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control Question # 9 What effect does a loss of 2EC1 have on the Emergency Diesel Generators?

A. Train A EDG will not start following a Safety Injection.

B. Train B EDG will not start following a Safety Injection.

C. If Train A EDG is running due to a loss of offsite power, an 86-2 lockout will actuate, causing the DG to trip.

D. If Train B EDG is running due to a loss of offsite power, an 86-2 lockout will actuate, causing the DG to trip.

Answer: C Page 51 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the power supplies to the controls for the EDGs and the effect of a loss of power.

Explanation:

A. Incorrect. Plausible as the DG will not start on a bus UV signal, but will start following a safety injection.

B. Incorrect. Plausible (see A) and it is thought that the 2 in 2EC1 indicates a Train B power supply.

C. Correct. The loss of 2EC1 will cause a loss of power to the EDG UV start relay and an 86-2 lockout will actuate due to loss of power to the generator outboard bearing high temperature relay and the DG will trip.

D. Incorrect. Plausible (see C) and if it is thought that the 2 in 2EC1 indicates a Train B power supply.

Technical Reference(s) ABN-603 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Loss of Instrument Bus in accordance with ABN-603, Loss of Protection or Instrument Bus. (ABN.603.OB02)

Question Source: Bank # 21915 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 52 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-603 Revision: 8 Page 53 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 022.A4.05 Level of Difficulty: 4 Importance Rating 3.8 Containment Cooling: Ability to manually operate and/or monitor in the control room: Containment readings of temperature, pressure, and humidity system Question # 10 (1) When determining if Adverse Containment Conditions exist, which of the following Containment Pressure indications on the Control Board are to be used?

(2) When determining Containment Temperature for TS 3.6.5, Containment Air Temperature, the meter reading used on the Control Board is the __(2)__ of:

TE-5400, CNTMT TEMP DOME EL 1001'-9" TE-5401, CNTMT TEMP EL 1001'-2 1/2" TE-5403, CNTMT TEMP EL 905'-9" TE-5404, CNTMT TEMP EL 863'-6" A. (1) Intermediate Range (PT-934, 935, 936 and 937)

(2) average B. (1) Narrow Range (PT-5470A and 5470B)

(2) average C. (1) Intermediate Range (PT-934, 935, 936 and 937)

(2) highest D. (1) Narrow Range (PT-5470A and 5470B)

(2) highest Answer: A Page 54 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the indications of containment temperature and pressure on the control board.

Explanation:

A. Correct. First part is correct. Intermediate range channels are used for determining adverse containment conditions as narrow range indications have a maximum value of 2.5 psig. Second part is correct. Containment temperature indicator is TI-5400A, CNTMT AVE TEMP, using average temperature.

B. Incorrect. First part is incorrect, but plausible since narrow range are typically read to ensure compliance with TS limits on pressure. Second part is correct (see A).

C. Incorrect. First part is correct (see A). Second part is incorrect, but plausible as a high failure of any of the four containment temperature inputs will result in a high Containment temperature alarm.

D. Incorrect. First part is incorrect, but plausible (see B). Second part is incorrect, but plausible (see C).

Technical Reference(s) ALM-0031A Attached w/ Revision # See ODA-407 Comments / Reference Containment Systems Study Guide Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Containment system including interrelations with other systems to include interlocks and control loops as described in DBD-ME-008 Containment Analysis. (SYS.CY1.OB02)

Question Source: Bank #

Modified Bank # 21668 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 55 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 21668 Revision:

Page 56 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0031A Revision: 8 Page 57 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 58 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Containment Systems Study Guide Revision: 5-2-2011 Page 59 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 026.A1.06 Level of Difficulty: 3 Importance Rating 2.7 Containment Spray: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment spray pump cooling Question # 11 Given the following conditions:

Both trains of Containment Spray have just actuated on HI-3 Train B CCW Pump has tripped Train B Containment Spray Pumps must be stopped due to a loss of cooling to the __(1)__.

Prior to stopping any equipment, Train B Containment Spray Pump room temperatures will

__(2)__.

A. (1) Seal Coolers (2) be unaffected B. (1) Seal Coolers (2) approach design limits C. (1) Bearing Coolers (2) be unaffected D. (1) Bearing Coolers (2) approach design limits Answer: B Page 1 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the operation of the containment spray pump controls to prevent exceeding design room temperature limits.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since chilled water would be supplied by CCW if a Hi-3 condition had not occurred, which splits the two CCW trains.

In this case Train B CT Pump room temperatures would be unaffected.

B. Correct. First part is correct. CCW supplies cooling to the pump seal coolers. Second part is correct. Upon a loss of CCW, due to the trip of the Train B CCW Pump and the split of the CCW trains, the chilled water system loses cooling and the room temperatures will approach limits due to the pump running.

C. Incorrect. First part is incorrect, but plausible since bearing coolers require cooling, but they are cooled by SSW, not CCW. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) SOP-204A Attached w/ Revision # See ABN-503 Comments / Reference ABN-502 Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Containment Spray system including interrelations with other systems to include interlocks and control loops in accordance with the FSAR and DBD-ME-0232. (SYS.CT1.OB03)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 2 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-204A Revision: 15 Page 3 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-503 Revision: 2 Page 4 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-502 Revision: 11 Page 5 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 039.K4.05 Level of Difficulty: 4 Importance Rating 3.7 Main and Reheat Steam: Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following: Automatic isolation of steam line Question # 12 Given the following conditions:

A plant cooldown and depressurization is in progress RCS pressure is 1925 psig The RO has taken both 1/1-PPSIRBA, PRZR PRESS SI RESET / BLOCK, and 1/1-PPSIRBB, PRZR PRESS SI RESET / BLOCK, to the Block position The BOP has taken both 1/1-SLSIRBA, MSL ISOL SI RESET / BLOCK, and 1/1-SLSIRBB, MSL ISOL SI RESET / BLOCK, to the Block position Assuming NO further operator actions, if a large steam break were to subsequently occur outside Containment:

Safety Injection __(1)__ occur.

A Main Steamline Isolation will occur on __(2)__.

A. (1) will (2) Low Steamline pressure B. (1) will (2) Negative Steamline pressure high rate C. (1) will NOT (2) Low Steamline pressure D. (1) will NOT (2) Negative Steamline pressure high rate Answer: D Page 6 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the conditions which will cause a main steam line isolation.

Explanation:

A. Incorrect. First part is incorrect. Plausible since an SI could occur if the break were inside containment. Second part is incorrect. Plausible since action is taken to block the steamline low pressure isolation, but the blocking enables a negative pressure rate signal to close the MSIVs.

B. Incorrect. First part is incorrect (See A). Second part is correct (See D).

C. Incorrect. First part is correct (See D). Second part is incorrect (See A).

D. Correct. First part is correct. SI will not occur on low steamline pressure when blocked. Second part is correct. Blocking enables a negative pressure rate signal to close the MSIVs.

Technical Reference(s) ALM-0065A Attached w/ Revision # See IPO-005 Comments / Reference Reactor Protection Study Guide Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Reactor Protection and Engineered Safeguard Actuation Systems and predict the system response in accordance with DBD-EE-021, Reactor Protection and NSSS Related Control Systems and Westinghouse Drawings 7247D05. (SYS.ES1.OB04)

Question Source: Bank # 23049 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 7 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0065A Revision: 4 Page 8 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

IPO-005A Revision: 27 Page 9 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

IPO-005A Revision: 27 Page 10 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Reactor Protection Study Guide Revision: 5-4-2011 Page 11 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Reactor Protection Study Guide Revision: 5-4-2011 Page 12 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 059.A4.11 Level of Difficulty: 2 Importance Rating 3.1 Main Feedwater: Ability to manually operate and monitor in the control room: Recovery from automatic feedwater isolation Question # 13 Given the following conditions:

Unit 1 tripped from 100% power due to a P-14 on SG 1-02 As the crew is working through the ERG network all AFW is lost and cannot be restored FRH-0.1A, Response to Loss of Secondary Heat Sink has been entered All S/G NR levels are ~ 2%

During attempts to re-establish a MFW flow path by resetting the FWI, which of the following will be required IF the Reactor trip breakers are unable to be cycled?

A. Reset both trains of SI Sequencer, then reset the FWI signal B. Pull universal logic card A213 from both trains of SSPS, then replace both cards C. Cycle the FWIV hand switches to the closed and open position to allow a FWI reset D. Open 1B3-1 and 1B4-1 breakers to remove control power from the reactor trip breakers Answer: B Page 13 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the actions required to reset feedwater isolation signal.

Explanation:

A. Incorrect. Plausible as this is part of step 7 RNO but this by itself will not reset the FWI signal.

B. Correct. Per FRH-0.1 step 7.b RNO 1.b if the breakers cannot be cycled then if card A213 is pulled on both trains this will allow power to be removed from the circuit and therefor resetting the FWI signal to allow feeding with the feedwater system.

C. Incorrect. Plausible as FRH-0.1 step 7 does have the operator place FWIV handswitches in auto after closed but this will not reset the FWI.

D. Incorrect. Plausible as this is performed by FRH-0.1 for restoration of condensate flow but without cycling the trip breakers it will not reset the FWI.

Technical Reference(s) FRH-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1 in accordance with FRH-0.1, Loss of Heat Sink. (ERG.FH1.OB04)

Question Source: Bank # 24393 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 14 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1A Revision: 9 Page 15 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1A Revision: 9 Page 16 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1A Revision: 9 Page 17 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 061.A3.03 Level of Difficulty: 4 Importance Rating 3.9 Auxiliary/Emergency Feedwater: Ability to monitor automatic operation of the AFW, including: AFW S/G level control on automatic start Question # 14 Given the following conditions:

Both MDAFWPs are operating, maintaining SG levels at 67%, with flow to each SG being controlled in MAN at 200 gpm The TDAFWP is secured An AFW autostart signal is received which starts the TDAFWP MDAFWP flow control valves will __(1)__.

TDAFWP flow control valves will __(2)__.

A. (1) trip to AUTO and go full open (2) trip to AUTO and go full open B. (1) trip to AUTO and go full open (2) remain in MAN at the current position C. (1) trip to AUTO and throttle to maintain program SG level (2) trip to AUTO and go full open D. (1) trip to AUTO and throttle to maintain program SG level (2) remain in MAN at the current position Answer: B Page 18 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge how an automatic start of the AFW system effects the flow control valves.

Explanation:

A. Incorrect. First part is correct. MDAFWP flow control valves trip to AUTO and go full open.

Second part is incorrect, but plausible since the MDAFWP valves trip to AUTO and go full open, it might be considered that the TDAFWP valves would respond the same.

B. Correct. First part is correct (see A). Second part is correct. The TDAFWP valves remain in their current, fully open position on an autostart.

C. Incorrect. First part is incorrect, but plausible if thought that MDAFWP FCVs tripped to Auto and controlled at program level similar to the MFW FCVs. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) AFW Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Auxiliary Feedwater system and the system response in accordance with DBD-ME-206. (SYS.AF1.OB04)

Question Source: Bank #

Modified Bank # 73907 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 19 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 73907 Revision:

Page 20 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 73907 Revision:

Page 21 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

AFW Study Guide Revision: 00-0000 Page 22 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

AFW Study Guide Revision: 00-0000 Page 23 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 062.A2.08 Level of Difficulty: 3 Importance Rating 2.7 AC Electrical Distribution: Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Consequences of exceeding voltage limitations Question # 15 Given the following conditions:

Unit 1 and Unit 2 Safeguards 6.9 KV Buses are aligned normally A low voltage condition on Unit 1 6.9 KV Buses occurs Assuming the plant responds as designed, which of the following identifies the response of Unit 1 to the low voltage?

Unit 1 transfers from transformer A. XST1 to XST2 and Unit 1 EDGs are NOT running.

B. XST1 to XST2 and Unit 1 EDGs are running unloaded.

C. XST2 to XST1 and Unit 1 EDGs are NOT running.

D. XST2 to XST1 and Unit 1 EDGs are running unloaded.

Answer: C Page 24 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the response of Unit 1 to a low voltage condition.

Explanation:

A. Incorrect. Plausible since the Unit 1 EDGs will not be running and also if thought that the normal alignment is Unit 1 being supplied by XST1. This would be the correct response for Unit 2.

B. Incorrect. Plausible since it may be thought that the normal alignment is Unit 1 being supplied by XST1 and that the Unit 1 EDGs will be running.

C. Correct. The normal power source to Unit 1 is XST2 so a transfer to XST1 will occur. A time delay of approximately one second will prevent the EDG from starting, allowing the buses to first be powered from XST1, the alternate supply.

D. Incorrect. Plausible since a transfer to XST1 from XST2 will occur and if there were no time delay to prevent the EDG from starting.

Technical Reference(s) 6.9Kv and 480V Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the 6.9 KV and 480 V Electrical Distribution system and PREDICT the system response in accordance with SOP-603, 604 and ABN-602. (SYS.AC2.OB05)

Question Source: Bank #

Modified Bank # 20740 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 25 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Exam Bank 20740 Revision:

Page 26 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Exam Bank 20740 Revision:

Page 27 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

6.9Kv and 480V Study Guide Revision: 10-03-2013 Page 28 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

6.9Kv and 480V Study Guide Revision: 10-03-2013 Page 29 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 063.G.2.2.38 Level of Difficulty: 3 Importance Rating 3.6 DC Electrical Distribution: Knowledge of conditions and limitations in the facility license.

Question # 16 With Unit 1 in Mode 3 and Battery Charger BC1ED1-2 INOPERABLE, which of the following would require entry into TS 3.8.4, DC Sources - Operating, action statements?

A. Battery BT1ED2 voltage is 125 VDC.

B. Battery BT1ED3 float current is 0 amps.

C. Battery Charger BC1ED1-1 EQUALIZE push button is depressed.

D. Battery Charger BC1ED4-1 is placed under clearance after placing Battery Charger BC1ED4-2 in service.

Answer: A Page 30 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of TS entry conditions for DC electrical systems.

Explanation:

A. Correct. Each battery is required to have a minimum float voltage of 2.13 volts per cell or 128 volts total.

B. Incorrect. Plausible since 0 amps may indicate that the battery is not performing its function, but a float current of 0 amps indicates that the battery charger has fully charged the battery and the battery charger is supplying all bus loads.

C. Incorrect. Plausible since battery charger BC1ED1-2 is already out of service, but depressing the equalize push button causes battery charger output voltage to be 138 - 140 VDC which is an operable condition.

D. Incorrect. Plausible since one battery charger is already out of service, but BC1ED4-1 is a different train and BC1ED4-2 would be placed in service prior to placing BC1ED4-1 under clearance.

Technical Reference(s) TS 3.8.4 Attached w/ Revision # See MSE-S0-5000 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given system parameter indications and plant conditions, ASSESS from memory any required TS/TR entries, including any actions which must be completed within one hour in accordance with Technical Specifications or TRM.

(SYS.DC1.OB05)

Question Source: Bank # 19161 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 31 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.8.4 Revision: 170 Page 32 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.8.4 Revision: 82 Page 33 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

MSE-S0-5000 Revision: 7 Page 34 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 064.K6.07 Level of Difficulty: 2 Importance Rating 2.7 Emergency Diesel Generator: Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers Question # 17 Given the following conditions:

DG 1-01 in normal alignment 1-ALB-10B Window 2.8, DG1 Trouble, annunciates NEO reports the following:

Low Press Starting Air Left Bank in alarm Low Press Starting Air Right Bank in alarm Starting air pressure in both banks 160 psig and lowering Per TS 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air, the required minimum starting air pressure __(1)__ satisfied.

DG 1-01 will start __(2)__ start signal.

A. (1) is (2) ONLY on an emergency B. (1) is (2) on BOTH an emergency and normal C. (1) is NOT (2) ONLY on an emergency D. (1) is NOT (2) on BOTH an emergency and normal Answer: D Page 35 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of low air receiver pressure on the EDG operations.

Explanation:

A. Incorrect. First part is incorrect. The minimum air pressure required by TS 3.8.3 is 180 psig, therefore the minimum starting air pressure is not satisfied. Second part is incorrect, but plausible because this is a common misconception that the emergency start would be available at lower air pressures than a normal manual start. However, with air pressure greater than approximately 90 psig the normal start signal is available and the emergency start will be blocked below 150 psig.

B. Incorrect. First part is incorrect (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect (see A).

D. Correct. First part is correct. The minimum air pressure required by TS 3.8.3 is not met. Second part is correct. The DG will start on both an emergency and normal start because only 90 psig of air is required for a normal start and 150 psig of air is required for an emergency start.

Technical Reference(s) TS 3.8.3 Attached w/ Revision # See OPT-214A Comments / Reference EDG Study Guide Proposed references to be provided during examination:

Learning Objective: Given Emergency DG parameters and indications, ASSESS from memory any required TS/TR entries, including any actions which must be completed within one hour in accordance with Technical Specifications or TRM (SYS.ED1.OB24)

Question Source: Bank # 67832 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 36 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.8.3 Revision: 150 Page 37 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.8.3 Revision: 156 Page 38 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OPT-214A Revision: 25 Page 39 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OPT-214A Revision: 25 Page 40 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EDG Study Guide Revision: 00-0000 Page 41 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EDG Study Guide Revision: 00-0000 Page 42 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 073.K1.01 Level of Difficulty: 2 Importance Rating 3.6 Process Radiation Monitoring: Knowledge of the physical connections and/or cause-effect relationships between the PRM system and the following systems: Those systems served by PRMs Question # 18 A MSL Radiation Monitor trend has initially increased above the normal reading following a 1.0 gpm SG tube leak.

Assuming all procedures are implemented:

The trend on the MSL Radiation Monitor will __(1)__ as power is decreased; and, When the MSIV is closed, the trend on the MSL Radiation Monitor will __(2)__.

A. (1) stabilize (2) increase rapidly to a RED alarm B. (1) stabilize (2) decrease to a value above the normal reading C. (1) decrease (2) increase rapidly to a RED alarm D. (1) decrease (2) decrease to a value above the normal reading Answer: D Page 43 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of radiation monitor trends following actions taken due to high radiation levels.

Explanation:

A. Incorrect. First part is incorrect, but plausible since lowering load causes less steam flow to leave steam line, so it could be thought that leakage is being contained in the area of the rad monitor causing rad levels to stabilize. Second part is incorrect, but plausible (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible since it could be thought that containing all the leakage upstream of the MSIV after it is closed will cause rad levels to increase.

D. Correct. First part is correct. As power lowers for the same size leak the trend decreases due to less activity. Second part is correct. When the MSIV is closed no flow goes past the rad monitor so the rad monitor decreases back towards normal.

Technical Reference(s) ABN-106 Attached w/ Revision # See Main Steam Study Guide Comments / Reference DRMS Study Guide Proposed references to be provided during examination:

Learning Objective: PREDICT the response of the instrumentation and controls of the Digital Radiation Monitoring System in accordance with DBD-EE-023.

(SYS.RM1.OB04)

Question Source: Bank # 17676 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 11 55.43 Page 44 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 45 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 46 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 47 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 48 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Main Steam Study Guide Revision: 00-0000 Page 49 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

DRMS Study Guide Revision: 4-28-2011 Page 50 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 076.K4.06 Level of Difficulty: 3 Importance Rating 2.8 Service Water: Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Service water train separation Question # 19 Given the following conditions:

Unit 1 is in MODE 6 with the Refueling Cavity flooded Unit 1 PDP is supplying RCP seal injection Unit 2 has tripped and during post-trip actions lost both trains of SSW The only available Unit 1 SSW Pump, 1-01, has been aligned to supply Unit 2 SSW Train B Which of the following describes the flowpath for this alignment per SOP-501A, Station Service Water System?

Unit 1 SSWP 1-01 is running with its discharge valve full open. Flow to Unit 2 is adjusted by throttling the __(1)__.

In this configuration, the Unit 2 Train B CCP lube oil cooler __(2)__ be supplied with SSW.

A. (1) Unit 2 SSWP (2-02) Discharge Valve (2) can B. (1) Unit 2 SSWP (2-02) Discharge Valve (2) cannot C. (1) Unit 1 to Unit 2 cross-tie valve (2) can D. (1) Unit 1 to Unit 2 cross-tie valve (2) cannot Answer: A Page 51 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how SSW trains, normally maintained separated, can be cross-connected.

Explanation:

A. Correct. First part is correct. Per ABN-501, flow is from Unit 1 SSW Pump 1-01 through full open discharge, crosstie line and Unit 2 SSW Pump 2-02 discharge which is at 15% on initial pump start and then throttled full open or until pump runout flow of 18,600 gpm. Second part is correct.

Unit 1 Train A CCW Heat Exchanger, Unit 2 Train B CCW Heat Exchanger, and Unit 2 Train B Centrifugal Charging Pump are aligned for flow.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible since the Unit 1 CCP cannot be supplied, but the Unit 2 CCP can be supplied.

C. Incorrect. First part is incorrect, but plausible (see D). Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible since flow is through cross-tie, but valve is opened fully. Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-501 Attached w/ Revision # See SOP-501 Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to a Loss of All Unit u Station Service Water in accordance with ABN-501, Station Service Water System Malfunction.

(ABN.501.OB104)

Question Source: Bank # 36001 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 52 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-501 Revision: 10 Page 53 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 54 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 55 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 56 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 57 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 58 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-501A Revision: 20 Page 59 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 078.A3.01 Level of Difficulty: 3 Importance Rating 3.1 Instrument Air: Ability to monitor automatic operation of the IAS, including: Air pressure Question # 20 Given the following conditions:

IAC 1-01 is running in LEAD IAC 1-02 is in BACKUP with the Automatic Operation light ON An INSTR AIR HDR PRESS LO alarm is received at 85 psig The NEO isolates the leak, and IA header pressure is approximately 107 psig rising Which of the choices below describes the compressor status?

A. Both compressors are running loaded B. Both compressors are running unloaded C. IAC 1-01 is running loaded; IAC 1-02 is running unloaded D. IAC 1-01 is running unloaded; IAC 1-02 is running loaded Answer: A Page 60 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of starting and loading air pressure setpoints for IA compressors.

Explanation:

A. Correct. Lead started at 105, backup at 100 psig. Both will run loaded until 115 psig.

B. Incorrect. Plausible since both will be running, but compressors will not unload until 115 psig. Could think unload occurs at 105 psig.

C. Incorrect. Plausible since lead started at 105, backup at 100 psig, but both will continue to run loaded until 115 psig. Could think unload occurs at 105 psig.

D. Incorrect. Plausible since lead started at 105, backup at 100 psig, but both will continue to run loaded until 115 psig. Could think unload occurs at 105 psig.

Technical Reference(s) ABN-301 Attached w/ Revision # See SOP-509A Comments / Reference Instrument Air Study Guide Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Instrument Air system and the system response in accordance with DBD-ME-218. (SYS.IA1.OB04)

Question Source: Bank # 21692 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 61 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-301 Revision: 14 Page 62 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-509A Revision: 24 Page 63 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

IA Study Guide Revision: 5-7-2011 Page 64 of 64 CPNPP 2021-08 NRC Written Exam Worksheet 11-20 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 103.K3.03 Level of Difficulty: 3 Importance Rating 3.7 Containment: Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations Question # 21 Per TS 3.9.4, Containment Penetrations, which of the following constitutes a loss of Containment Integrity during Refueling Operations and requires immediate termination of Core Alterations?

A. The Emergency Airlock outer door is closed with the inner door open.

B. The Steam Generator 1-01 manway cover is open with nozzle dam installed.

C. The Equipment Hatch is open, capable of being installed and held in place with 3 bolts.

D. The Personnel Airlock inner and outer doors are open with personnel staged to close either door.

Answer: C Page 1 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of containment integrity requirements during refueling operations with effect of the loss requiring termination of core alterations.

Explanation:

A. Incorrect. Plausible because one door of the Emergency Airlock is open, however, in accordance with TS 3.9.4, the Emergency Airlock is required to have one door closed, therefore the other door may be open.

B. Incorrect. Plausible because with the SG manway open it could be thought this created an opening from the primary to the secondary side and result in a direct air to air breach.

C. Correct. In accordance with TS 3.9.4, the equipment hatch must be closed or capable of being closed with 4 bolts holding it in place. With only 3 bolts available this would constitute a loss of containment integrity during refueling operations.

D. Incorrect. Plausible because both doors of the Personnel Airlock are open resulting in a direct air to air breach of containment, however, per TS 3.9.4 this is allowed as long as one door of the PAL is capable of being closed.

Technical Reference(s) TS 3.9.4 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS specific outage items related to reduced inventory in accordance with IPO-010. (IPO.010.OB05)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.9.4 Revision: Amd 150 Page 3 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 004.K2.02 Level of Difficulty: 3 Importance Rating 2.9 Chemical and Volume Control: Knowledge of bus power supplies to the following: Makeup pumps Question # 22 Which of the following accurately states the bus power supply for Boric Acid Transfer Pump 1/1-APBA1?

A. 1B1-1 B. 1EB1-1 C. XB1-1 D. XEB1-1 Answer: B Page 4 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of power supplies to the BAT pumps for CVCS makeup.

Explanation:

A. Incorrect. Plausible since the power supply is unit related and the pump is not needed for emergency boration on an SI, so it could be a non-safeguards unit supply.

B. Correct. This is the correct power supply per SOP-105.

C. Incorrect. Plausible since the pump takes a suction off the X-01 tank and the pump is not needed for emergency boration on an SI, so it could be a non-safeguards common supply.

D. Incorrect. Plausible since the pump takes a suction off the X-01 tank and the pump is safety related, so it could be a safeguards common supply.

Technical Reference(s) SOP-105 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the components of the Reactor Makeup system including interrelations with other systems to include interlocks and control loops IAW SOP-103, -104, and -105. (SYS.CS2.OB03)

Question Source: Bank # 52512 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 5 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-105 Revision: 11-29-04 Page 6 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 008.A1.01 Level of Difficulty: 2 Importance Rating 2.8 Component Cooling Water: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: CCW flow rate Question # 23 Given the following conditions:

Unit 1 at 100%

RCP 1-01 Thermal Barrier cooler leak CCW Surge Tank level 80% increasing slowly CCW flow from RCP 1-01 Thermal Barrier is 85 gpm increasing CCW Thermal Barrier return temperature is 170ºF increasing 1-HS-4691, RCP 1-01 THBR CLR CCW RET TEMP CTRL VLV, and 1-HV-4709, U1 THBR CLR CCW RET ISOL VLV ORC, are currently __(1)__.

1-HV-4696, THBR CLR CCW RET ISOL VLV IRC, is currently __(2)__.

A. (1) closed (2) open B. (1) closed (2) closed C. (1) open (2) open D. (1) open (2) closed Answer: D Page 7 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the flow rate which will cause the CCW valves to automatically close.

Explanation:

A. Incorrect. First part is incorrect, but plausible (see B). Second part is incorrect, but plausible since flow remaining below a high setpoint will not close the valve, but setpoint not recalled.

B. Incorrect. First part is incorrect, but plausible since valves 4691 and 4709 close if temperature exceeds a high setpoint, but setpoint not recalled. Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. Valves 4691 and 4709 close if temperature exceeds 182.5°F, so they remain open. Second part is correct. Valve 4696 will close if flow is greater than 64 gpm.

Technical Reference(s) ALM-0032A Attached w/ Revision # See ABN-502A Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to Leakage Into the CCW System in accordance with ABN-502, Component Cooling Water System Malfunction. (ABN.501.OB106)

Question Source: Bank # 31261 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 8 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Revision:

Page 9 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-502A Revision: 11 Page 10 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 012.K5.01 Level of Difficulty: 3 Importance Rating 3.3 Reactor Protection: Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB Question # 24 The OT N-16 Reactor Trip provides protection to prevent __(1)__.

Assuming the Reactor Trip setpoint is at its nominal value with the plant at NOP/NOT, if reactor power rises to 112%, the OT N-16 Reactor Trip __(2)__ actuate.

A. (1) exceeding the allowable Heat Generation Rate (2) would B. (1) exceeding the allowable Heat Generation Rate (2) would NOT C. (1) DNB (2) would D. (1) DNB (2) would NOT Answer: D Page 11 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of DNB reactor protection and setpoint.

Explanation:

A. Incorrect. 1st part is incorrect but plausible (see B). 2nd part is incorrect but plausible (see C).

B. Incorrect. 1st part is incorrect because the Overtemperature N 16 trip prevents DNB from occurring. It is plausible because if it were the Overpower N 16 trip, it would be correct. 2nd part is correct (see D).

C. Incorrect. 1st part is correct (see D). 2nd part incorrect because the nominal setpoint for Overtemperature N 16 trip is 115%. It is plausible because if it were the Overpower N 16 trip it would be correct.

D. Correct. 1st part correct. The Overtemperature N 16 trip prevents DNB from occurring. 2nd part is correct. The nominal setpoint for Overtemperature N 16 trip is 115%.

Technical Reference(s) TSB 3.3.1 Attached w/ Revision # See COLR Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Reactor Protection and Engineered Safeguard Actuation Systems and predict the system response in accordance with DBD-EE-021, Reactor Protection and NSSS Related Control Systems and Westinghouse Drawings 7247D05. (SYS.ES1.OB04)

Question Source: Bank # 73903 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6 55.43 Page 12 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.3.1 Revision: 156 Page 13 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.3.1 Revision: 156 Page 14 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

U1 COLR Revision: 0 Page 15 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 026.K4.09 Level of Difficulty: 2 Importance Rating 3.7 Containment Spray: Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following: Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover)

Question # 25 Given the following conditions:

Unit 1 100% power in a normal alignment CS actuation occurs due to a LOCA Subsequently:

The CS system is aligned for containment sump recirculation Following the CS actuation, but prior to placing the system in containment sump recirculation, the CS Pump Recirculation Valves will be__(1)__.

Following realignment of the system for containment sump recirculation, these valves will

__(2)__.

A. (1) open (2) close B. (1) open (2) remain open C. (1) closed (2) open D. (1) closed (2) remain closed Answer: D Page 16 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the interlock associated with the CS recirc valves preventing flow from containment to the RWST.

Explanation:

A. Incorrect. First part is incorrect since the valves close upon the opening of the CS HX outlet valves, but plausible since the valves will not open on an SI or CS actuation signal directly.

Second part is correct (see D).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since CS signal may be reset prior to going to recirculation, but valve operation is based on position of CS HX outlet or sump recirculation valve position.

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see B).

D. Correct. First part is correct. These recirc valves are normally in automatic and close automatically when the CS HX outlet valve opens on the CS actuation signal. Second part is correct. When the containment spray system is aligned for recirculation the valves will remain closed due to the heat exchanger outlet valves open, as well as the sump suction valves being opened.

Technical Reference(s) ALM-0022A Attached w/ Revision # See Containment Spray Lesson Plan Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the instrumentation and controls of the Containment Spray System and predict the system response in accordance with FRZ-0.1A/B and EOS-1.3A/B. (SYS.CT1.OB04)

Question Source: Bank #

Modified Bank # 66447 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 17 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 66447 Revision:

Page 18 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 66447 Revision:

Page 19 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0022A Revision: 10 Page 20 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

CS Lesson Plan Revision: 00-0001 Page 21 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 039.K3.03 Level of Difficulty: 4 Importance Rating 3.2 Main and Reheat Steam: Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: AFW pumps Question # 26 Given the following conditions:

Unit 2 90% power 2-HS-2452-1, AFWPT STM SPLY VLV - MSL 4 fails open TDAFWP speed is increasing Crew has entered ABN-305, Auxiliary Feedwater System Malfunction, for an Inadvertent Turbine Driven AFW Pump Start Based on plant conditions, turbine load __(1)__ required to be reduced by 50 MW.

To stop the TDAFWP, ABN-305 INITIALLY directs __(2)__ .

A. (1) is (2) tripping the TDAFW pump B. (1) is (2) closing 2-HS-2452-1 by placing in PULLOUT C. (1) is NOT (2) tripping the TDAFW pump D. (1) is NOT (2) closing 2-HS-2452-1 by placing in PULLOUT Answer: D Page 22 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the requirements regarding the operation of the TDAFWP following a failure of the MS supply valves.

Explanation:

A. Incorrect. First part is incorrect, but plausible. With the unit at 90% power, a power reduction is not required. If the unit was at 100%, a power reduction would be required. Second part is incorrect, but plausible because the operators are directed to trip the TDAFWP at Step 4 if the Steam Supply valve failed to close B. Incorrect. First part is incorrect, but plausible (see A). The second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. With the unit at 90%, a 50 MW load reduction is not required to maintain power below 100%. Second part is correct. Operators are directed to close the steam supply valves for any steam admission valve that would not close at Step 1 of the ABN.

Technical Reference(s) ABN-305 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Inadvertent Turbine Driven AFW Pump Start in accordance with ABN-305, Auxiliary Feedwater System Malfunction.

(ABN.305.OB06)

Question Source: Bank #

Modified Bank # 72044 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 23 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 72044 Revision:

Page 24 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 72044 Revision:

Page 25 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-305 Revision: 8 Page 26 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 061.K6.02 Level of Difficulty: 2 Importance Rating 2.6 Auxiliary/Emergency Feedwater: Knowledge of the effect of a loss or malfunction of the following will have on the AFW components:

Pumps Question # 27 Given the following conditions:

Reactor failed to trip when required A transition has been made to FRS-0.1A, Response to Nuclear Power Generation/ATWT MDAFWP 1-02 trips shortly after starting All SG NR levels are off-scale LOW Placing 1-HS-2451A, MD AFWP 2 in the STOP or PULL-OUT position will reset the __(1)__

relay and may result in an automatic restart if the handswitch is returned to AUTO.

Per FRS-0.1A, the MINIMUM total AFW flow to be established is greater than __(2)__.

A. (1) 86M lockout (2) 460 gpm B. (1) 50/51 overcurrent (2) 460 gpm C. (1) 86M lockout (2) 860 gpm D. (1) 50/51 overcurrent (2) 860 gpm Answer: C Page 27 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the AFW pump operation.

Explanation:

A. Incorrect. 1st part is correct (see C). 2nd part is incorrect, but plausible (see B).

B. Incorrect. 1st part is incorrect, but plausible (see D). 2nd part is incorrect because per FRS-0.1A, you are to establish > 860 gpm. It is plausible because if you were in EOP-0.0A, it would be correct C. Correct. 1st part is correct, per ABN-305 if the handswitch is taken to STOP or PULL-OUT and then returned to the AUTO position the 86M relay will reset and could result in an automatic pump re-start if there are no other dropped relays on the breaker. 2nd part is correct (see D).

D. Incorrect. 1st part is incorrect but plausible because this pump does have a 50/51 overcurrent relay, however, in order to reset this relay it must be performed locally at the breaker. 2nd part is correct. FRS-0.1A directs verify that greater than 860 gpm AFW flow exists at all times until SG NR levels have reached 43% (50% adverse containment).

Technical Reference(s) ABN-305 ing FRS-0.1A Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Motor Driven Auxiliary Feedwater Pump Malfunction in accordance with ABN-305, Auxiliary Feedwater System Malfunction.

(ABN.305.OB03)

Question Source: Bank #

Modified Bank # 81934 (Note changes or attach parent)

New Question History: Last NRC Exam LC26 (Original Question)

Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 28 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 81934 Revision:

Page 29 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 81934 Revision:

Page 30 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-305 Revision: 8 Page 31 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRS-0.1A Revision: 9 Page 32 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 064.A2.03 Level of Difficulty: 2 Importance Rating 3.1 Emergency Diesel Generator: Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Parallel operation of ED/Gs Question # 28 Given the following conditions:

Operators are in the process of conducting OPT-214A, Diesel Generator Testing They have started and loaded EDG 1-01 in accordance with the loading schedule After reaching the full load value required for the test, an SI occurs due to a technician error on an SSPS OPT Which of the following describes the expected response of EDG 1-01 output breaker?

A. The output breaker will open and immediately reclose due to the safeguards sequencer B. The output breaker will open and remain open with the EDG running unloaded C. The output breaker will remain closed until opened by the operator per the SI recovery procedures D. The output breaker will remain closed due to the control switch alignment of the diesel for the OPT Answer: B Page 33 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of events occurring while the EDG is paralleled with offsite power.

Explanation:

A. Incorrect. Plausible since the breaker will immediately open, but it will remain open unless needed to power the bus.

B. Correct. If the EDG is paralleled with offsite when an SI occurs, the EDG breaker opens and remains open unless needed to carry the bus.

C. Incorrect. Plausible since it may be incorrectly assumed that it is desirable to keep the safeguards bus energized by the EDG.

D. Incorrect. Plausible since it may be incorrectly assumed that it is desirable to keep the safeguards bus energized by the EDG.

Technical Reference(s) ABN-602 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Emergency Diesel Generator system including the system response in accordance with DBD-ME-011.

(SYS.ED1.OB22)

Question Source: Bank # 19341 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 34 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OPT-214A Revision: 25 Page 35 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 002.K6.07 Level of Difficulty: 2 Importance Rating 2.5 Reactor Coolant: Knowledge of the effect or a loss or malfunction on the following RCS components: Pumps Question # 29 A loss of RCP ______ results in the greatest loss of RCS pressure control.

A. 2-01 B. 2-02 C. 2-03 D. 2-04 Answer: D Page 36 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of an RCP trip on RCS pressure control.

Explanation:

A. Incorrect. Plausible because RCP 2-01 is connected to an RCS Spray valve, however, it is not as effective as RCP 2-04 as it is also connected to the PRZR surge line.

B. Incorrect. Plausible because it will provide some spray flow with RCP 2-02 and RCP 2-03 running using either spray valve but not as effective as RCP 2-01 or RCP 2-04.

C. Incorrect. Plausible because it will provide some spray flow with RCP 2-02 and RCP 2-03 running using either spray valve but not as effective as RCP 2-01 or RCP 2-04.

D. Correct. RCP 2-04 is the most effective at providing spray flow and thus RCS pressure control as it is directly connected to a spray valve and the PRZR Surge Line.

Technical Reference(s) EOS-0.2B Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the ERG background for performing Natural Circulation cooldown per EOS-0.2 Natural Circulation cooldown (ERG.E02.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 37 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2B Revision: 9 Page 38 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2B Revision: 9 Page 39 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2B Revision: 9 Page 40 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 011.K1.04 Level of Difficulty: 2 Importance Rating 3.8 Pressurizer Level Control: Knowledge of the physical connections and/or cause-effect relationships between the PZR LCS and the following systems: RPS Question # 30 Unit 1 is in MODE 3 with rods referenced in preparation for a Reactor Startup.

Which of the following failures will enable a Reactor Trip on PRZR High Water Level if level reaches the trip setpoint?

A. Failure low of N-43, Power Range Channel B. Failure high of N-43, Power Range Channel C. Failure low of PT-505, First Stage Turbine Pressure D. Failure high of PT-505, First Stage Turbine Pressure Answer: D Page 41 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the P-7 interlock associated with pressurizer high water level reactor trip.

Explanation:

A. Incorrect. Plausible since PR NIS input to P-10 which provides P-7, but the coincidence for P-10 is 2/4 above 10% power, although it may be confused because the associated PCIP window comes on when power is below 10%.

B. Incorrect. Plausible since PR NIS input to P-10 which provides P-7, but the coincidence for P-10 is 2/4 above 10% power.

C. Incorrect. Plausible since either first stage turbine pressure will give P-13 and P-7, but the failure low will not cause the turbine to be at power, although it may be confused because the associated PCIP window comes on when power is below 10%.

D. Correct. Pressurizer high level trip is enabled above P-7 which receives an input from P-10 or P-

13. Either first stage turbine pressure above 10% turbine load provides the at power condition for the turbine, providing P-13, and thus P-7, enabling the high level trip.

Technical Reference(s) ALM-0065A Attached w/ Revision # See Reactor Protection/ESFAS Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Reactor Protection and Engineered Safeguard Actuation Systems and predict the system response in accordance with DBD-EE-021, Reactor Protection and NSSS Related Control Systems and Westinghouse Drawings 7247D05. (SYS.ES1.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 42 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0065A Revision: 4 Page 43 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0065A Revision: 4 Page 44 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0065A Revision: 4 Page 45 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Reactor Protection/ESFAS Study Guide Revision: 5-4-2011 Page 46 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Reactor Protection/ESFAS Study Guide Revision: 5-4-2011 Page 47 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Reactor Protection/ESFAS Study Guide Revision: 5-4-2011 Page 48 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 21-30 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 2 K/A 015.K5.04 Level of Difficulty: 2 Importance Rating 2.6 Nuclear Instrumentation: Knowledge of the operational implications of the following concepts as they apply to the NIS: Factors affecting accuracy and reliability of calorimetric calibrations Question # 31 During the performance of OPT-309, Unit Calorimetric, if the LEFM is NOT available to be used, the LEFM Main Display will have the symbol in __(1)__.

If FW temperature points utilized for the calorimetric are reading 10ºF LOWER than actual FW temperature and PR NI adjustments are performed per the OPT, INDICATED power will be __(2)__ ACTUAL power.

A. (1) yellow (2) greater than B. (1) yellow (2) less than C. (1) red (2) greater than D. (1) red (2) less than Answer: C Page 1 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how an inaccuracy in the calorimetric calibration affects the indication of power range channels.

Explanation:

A. Incorrect. First part is incorrect, but plausible since yellow is the color used for many other indications to show an alert status. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible (see D).

C. Correct. First part is correct. A red check mark indicates that the LEFM is not available to be used and the feedwater venturis should be used. Second part is correct. Using a lower feedwater temperature indicates that more heat must be added to the feedwater to raise it to saturation due to having a lower enthalpy, so the indicated power will be greater than actual power.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible if thought that lower feedwater temperature used would cause the actual power to be greater than indicated.

Technical Reference(s) OPT-309 Attached w/ Revision # See Heat Transfer Generic Fundamentals Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS IPO-003, Power Operations, to include the following: Applicability; Precautions; Limitations; Notes; Instructions. (IPO.03B.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 2 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OPT-309 Revision: 18 Page 3 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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OPT-309 Revision: 18 Page 4 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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OPT-309 Revision: 18 Page 5 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Heat Transfer Generic Fundamentals Revision:

Page 6 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 2 K/A 016.K3.02 Level of Difficulty: 2 Importance Rating 3.4 Non-nuclear Instrumentation: Knowledge of the effect that a loss or malfunction of the NNIS will have on the following: PZR LCS Question # 32 Given the following conditions Unit 2 100% power 1/2-LS-459D, PRZR LVL CTRL CHAN SELECT switch, is selected to 459/460 The reference leg for level transmitter 2-LT-459A, PRZR LVL CHAN I, develops a leak 2-FCV-121, CCP Flow Control Valve will throttle __(1)__ in response to the erroneous level indication.

Pressurizer level transmitter __(2)__ will be selected for control on 1/2-LS-459D, PRZR LVL CTRL CHAN SELECT switch.

A. (1) closed (2) 2-LT-461 B. (1) closed (2) 2-LT-462 C. (1) open (2) 2-LT-461 D. (1) open (2) 2-LT-462 Answer: A Page 7 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how a failure of a detector effects pressurizer level control system.

Explanation:

A. Correct. 1st part is correct. As level in the reference leg lowers, DP will lower. In the Przr level detector, this will result in indicated Przr level rising. FCV-0121 will throttle close in an attempt to reduce Przr level. 2nd part is correct. LT-461 is the only option as a substitute for LT-459. LT-462 is cold calibrated and used for indication only.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because LT-461 is the only option as a substitute for LT-459. It is plausible because there are 4 pressure transmitters for Pressurizer pressure with each channel having its own standby transmitter. Level is different in that there is only one back which can be substituted for either LT-459 or LT-460.

C. Incorrect. 1st part is incorrect because a leak in the reference leg will cause FCV-0121 to close due to indicated Przr level rising. It is plausible because the effects of a reference leg leak are commonly mistaken. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) PRZR Press & Lvl Control Study Guide Attached w/ Revision # See ABN-706 Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Pressurizer Level Instrument Malfunction in accordance with ABN-706, Pressurizer Level Instrument Malfunction.

(ABN.705.OB02)

Question Source: Bank # 74093 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 8 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

PRZR Press & Lvl Control Study Guide Revision: 00-0000 Page 9 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-706 Revision: 8 Page 10 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-706 Revision: 8 Page 11 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 001.A4.06 Level of Difficulty: 2 Importance Rating 2.9 Control Rod Drive System: Ability to manually operate and/or monitor in the control room: Control rod drive disconnect/connect Question # 33 Given the following conditions:

Control Rod M-4 in CBD is misaligned by 18 steps Actions are being performed to realign the rod IAW ABN-712, Rod Control System Malfunction, using the DRPI method Control Rod M-4 is realigned to the remaining rods in Control Bank D by placing the Rod Selector Switch to the __(1)__ position and opening the lift coil disconnect switch(es) for

__(2)__.

A. (1) CBD (2) control rod M-4 B. (1) CBD (2) the remaining rods in Control Bank D C. (1) MAN (2) control rod M-4 D. (1) MAN (2) the remaining rods in Control Bank D Answer: B Page 12 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the operation of the rod disconnect switches when realigning a misaligned rod.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since opening only disconnect switch M4 would allow the other rods in the group to be realigned to the misaligned rod, but procedure has only the misaligned rod move.

B. Correct. First part is correct. Per ABN-712, the misaligned rod is selected by using the individual bank position, CBD. Second part is correct. The disconnect switches for all other Bank D rods are opened to assure only the misaligned rod moves.

C. Incorrect. First part is incorrect, but plausible since the switch is in the MAN position when the rod is determined to be misaligned, but is placed in CBD when aligning the rod. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) ABN-712 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to a Dropped or Misaligned Rod in MODE 1 or 2.

(ABN.712.OB02)

Question Source: Bank # 20872 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 13 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-712 Revision: 13 Page 14 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-712 Revision: 13 Page 15 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-712 Revision: 13 Page 16 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 033.G.2.1.28 Level of Difficulty: 4 Importance Rating 4.1 Spent Fuel Pool Cooling: Knowledge of the purpose and function of major system components and controls.

Question # 34 Given the following conditions:

SFP Cooling Water Pump X-02 and HX X-02 are aligned to and cooling the X-01 SFP Level is lowering in the X-01 SFP due to a pipe rupture downstream of SFP Cooling Water Pump X-02 discharge valve After SFP Cooling Water Pump X-02 loses suction, draining the pool via the break will be terminated by A. uncovering the X-01 SFP suction piping anti-siphon hole.

B. uncovering the X-01 SFP discharge piping anti-siphon hole.

C. closure of the discharge valve on SFP Cooling Water Pump X-02.

D. tripping SFP Cooling Water Pump X-02 on a low level in X-01 Spent Fuel Pool.

Answer: B Page 17 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the function of the anti-siphon holes on the discharge piping located in the SFPs.

Explanation:

A. Incorrect. Plausible based on the location of the leak once the pump loses suction water will continue to drain out the SFP until the anti-siphon hole is uncovered on the discharge piping.

B. Correct. The pump must first lose suction, with no discharge pressure the SFP water will backflow through the discharge piping until the anti-siphon hole is uncovered.

C. Incorrect. Plausible since closing the discharge valve would prevent forward flow out of the downstream break, but the valve is upstream of the leak and would have no effect since the leak is downstream siphoning water out from the bottom of the pool.

D. Incorrect. Plausible because the pump will trip on low level in its associated SFP.

Technical Reference(s) SFP Cooling and Cleanup Study Guide Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the function of the Spent Fuel Pool Cooling and Cleanup system IAW FSAR. (SYS.SF1.OB01)

Question Source: Bank # 34602 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 18 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SFP Cooling and Cleanup Study Guide Revision: 5-2-2011 Page 19 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SFP Cooling and Cleanup Study Guide Revision: 5-2-2011 Page 20 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 045.A3.08 Level of Difficulty: 3 Importance Rating 3.3 Steam Dump/Turbine Bypass Control: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including: Steam pressure Question # 35 Given the following conditions:

Unit 1 is performing a cooldown RCS loop Tave:

o Loop 1: 552ºF o Loop 2: 553ºF o Loop 3: 552ºF o Loop 4: 550ºF Steam Dump Mode Selector switch - STM PRESS MODE Steam Dump Controller - MAN set at 50% demand All Steam Dump valves closed The operator momentarily places the Train A and Train B Steam Dump Bypass Interlock switches to Bypass and then releases them What is the status of the Steam Dump valves following the operator's actions?

A. ONLY Bank 1 valves fully open.

B. Bank 1 and 2 valves go 50% open.

C. ONLY Bank 1 valves go 50% open.

D. Bank 1 and Bank 2 valves fully open.

Answer: A Page 21 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the steam dump system controls when operating in the steam pressure mode.

Explanation:

A. Correct. Bypassing the P-12 interlock allows the Bank 1 valves to open. With demand at 50%,

the Bank 1 valves will be fully open (at 25%), all others are prevented from opening.

B. Incorrect. Plausible since this would be the condition above P-12 and since the controller is set to 50% demand it could be thought the valves will only open to 50%.

C. Incorrect. Plausible since only Bank 1 valves open below P-12 and since the controller is set to 50% demand it could be thought the valves will only open to 50%.

D. Incorrect. Plausible since this would be the condition above P-12, but only the Bank 1 valves can be opened below P-12.

Technical Reference(s) IPO-005A Attached w/ Revision # See ALM-0065A Comments / Reference Steam Dumps Study Guide Proposed references to be provided during examination:

Learning Objective: PREDICT the response of the instrumentation and controls of the Steam Dump system in accordance with ABN-304, 704 and 709. (SYS.SD1.OB04)

Question Source: Bank # 19303 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 22 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

IPO-005A Revision: 27 Page 23 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0065A Revision: 4 Page 24 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Steam Dumps Study Guide Revision: 5-4-2011 Page 25 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 045.A3.07 Level of Difficulty: 2 Importance Rating 3.5 Main Turbine Generator: Ability to monitor automatic operation of the MT/G system, including: Turbine stop/governor valve closure on turbine trip Question # 36 Given the following conditions:

Unit 1 100% power when a Reactor Trip occurs EOP-0.0A, Reactor Trip or Safety Injection, entered While performing Immediate Operator Actions, Main Turbine HP Stop Valve 2 indicates both RED and GREEN lights lit All other Main Turbine HP Stop Valves indicate GREEN Lights lit and RED lights extinguished All Main Turbine Control Valves indicate 0% open on the Turbine Digital Control system Based on the above plant conditions, the turbine is __(1)__.

The reason for ensuring the turbine is tripped is to __(2)__.

A. (1) tripped (2) prevent steaming the SGs dry B. (1) tripped (2) prevent an excessive RCS cooldown C. (1) NOT tripped (2) prevent steaming the SGs dry D. (1) NOT tripped (2) prevent an excessive RCS cooldown Answer: D Page 26 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the indications to verify the turbine has tripped.

Explanation:

A. Incorrect. First part is incorrect because EOP-0.0 step 2 requires that all HP turbine stop valves are closed. It is plausible because with the control valves closed virtually all steam flow to the turbine is stopped. Second part is incorrect because the reason for tripping the turbine is to stop the cooldown which would add positive reactivity and possibly initiate SI. It is plausible because analysis during an ATWT has shown that a turbine trip is necessary within 30 seconds to conserve SG inventory.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. Turbine is verified tripped by ALL HP stop valves indicating closed. Second part is correct. The reason for tripping the turbine on a Reactor Trip is to prevent excessive RCS cooldown.

Technical Reference(s) EOP-0.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the immediate operator actions of EOP-0.0, Reactor Trip or Safety Injection. (ERG.E0A.OB02)

Question Source: Bank # 58149 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 27 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-0.0A Revision: 9 Page 28 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-0.0A Revision: 9 Page 29 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 075.A2.02 Level of Difficulty: 4 Importance Rating 2.5 Circulating Water: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps Question # 37 Given the following conditions:

Unit 1 18% power ALB-9A, Window 8.9 - CNDSR PIT LVL TRIP/TRIP BYP, has just alarmed The Turbine Building NEO has just reported that leakage from a CW expansion joint has resulted in flooding in the condenser pit and level is rising ALL Circulating Water Pumps have tripped Per ABN-304, Main Condenser and Circulating Water Malfunction, the __(1)__ is to be tripped and the MSIVs are to __(2)__.

A. (1) Reactor (2) be closed B. (1) Reactor (2) remain open C. (1) Turbine ONLY (2) be closed D. (1) Turbine ONLY (2) remain open Answer: A Page 30 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the actions to be taken in the event of a loss of all circ water pumps.

Explanation:

A. Correct. First part is correct. With reactor power above 10%, the reactor is to be tripped.

Second part is correct. With no circ water pumps available, the condenser is not available for steam dumps so the MSIVs are closed to control steam demand with the ARVs.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible (see D).

C. Incorrect. First part is incorrect, but plausible (see D). Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible since for all other conditions only a turbine trip is required up to P-9, 50% power. Second part is incorrect, but plausible since MSIVs are typically left open following a reactor or turbine trip.

Technical Reference(s) ABN-304 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Circulating Water Pump Trip in accordance with ABN-304, Main Condenser and Circulating Water System Malfunction.

(ABN.304.OB01)

Question Source: Bank # 17645 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 31 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-304 Revision: 9 Page 32 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 017.K4.01 Level of Difficulty: 2 Importance Rating 3.4 In-Core Temperature Monitor System (ITM): Knowledge of ITM design feature(s) and/or interlock(s) which provide for the following: Input to subcooling monitors Question # 38 Concerning the Subcooled Margin Monitor:

(1) Which of the following CET temperatures are an input to the monitor; and, (2) Assuming all other parameters remain stable, which of the following will cause RCS Subcooling Margin to be a smaller value?

A. (1) Highest CET temperature (2) Rising RCS pressure B. (1) Highest CET temperature (2) Rising RCS temperature C. (1) Average CET temperature (2) Rising RCS pressure D. (1) Average CET temperature (2) Rising RCS temperature Answer: B Page 33 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the temperature inputs to the subcooling monitor.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible if thought that being further from boiling would cause subcooling margin to get larger.

B. Correct. First part is correct. Along with RCS loop pressure, Pressurizer pressure, and RCS loop RTD temperatures, the Highest CET temperature is also an input. Second part is correct. Higher temperature indicates closer to boiling, so subcooling margin gets smaller.

C. Incorrect. First part is incorrect, but plausible as it could be thought that the average CET would be used as a general indication of the temperature of the RCS. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) Core Cooling Monitor/RVLIS Study Guide Attached w/ Revision # See Core Cooling Monitor/RVLIS LP Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Core Cooling Monitor/Reactor Vessel Level Indication System (RVLIS) IAW DBD-EE-004. (SYS.RC3.OB04)

Question Source: Bank # 19377 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 34 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Core Cooling Monitor/RVLIS Study Guide Revision: 4-27-2011 Page 35 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Core Cooling Monitor/RVLIS LP Revision: 00-0000 Page 36 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 000009.EA2.36 Level of Difficulty: 2 Importance Rating 4.2 Small Break LOCA: Ability to determine or interpret the following as they apply to a small break LOCA: Difference between overcooling and LOCA indications Question # 39 Given the following conditions:

EOP-1.0A, Loss of Reactor or Secondary Coolant, is being performed RCS WR Pressure 800 psig stable RCS WR Thot Temperatures 520°F stable RCS WR Tcold Temperatures 520°F stable SG Pressures 800 psig stable SG NR Levels 35% rising CCP SI Injection flow 350 gpm stable SI Pump flow 600 gpm each stable RHR Pump flow 0 gpm stable The event causing the above indications is a _______.

A. LBLOCA B. SBLOCA C. Feedline Break D. Steamline Break Answer: B Page 37 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the difference in RCS and secondary parameters during a SBLOCA events to properly diagnose the event.

Explanation:

A. Incorrect. Plausible because a LOCA is in progress, however, not a LBLOCA because RCS pressure is above the pressure at which RHR pumps begin injecting.

B. Correct. SBLOCA is in progress as RCS pressure has stabilized at a pressure above RHR injection flow. A secondary break is not evident by indications provided because SG pressures have stabilized.

C. Incorrect. Plausible because a Feedline break will cause a resultant drop in RCS pressures and temperatures and on a Feedline Break SG pressure will remain elevated until the break is uncovered, however, on a Feedline Break when the break is uncovered continued depressurization of the SGs will occur.

D. Incorrect. Plausible because RCS pressures and temperatures will drop below normal no-load values on a Steamline break, however, a Steamline Break will result in continued depressurization of the SGs.

Technical Reference(s) EOP-1.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions from EOP-1.0 in accordance with EOP-1.0, Loss of Reactor or Secondary Coolant.

(ERG.E1A.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 38 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-1.0A Revision: 9 Page 39 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-1.0A Revision: 9 Page 40 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-1.0A Revision: 9 Page 41 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-1.0A Revision: 9 Page 42 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 000040.AK1.02 Level of Difficulty: 3 Importance Rating 3.2 Steam Line Rupture: Knowledge of the operational implications of the following concepts as they apply to the Steam Line Rupture: Leak rate versus pressure change Question # 40 Unit 1 is in Mode 3. A Safety Valve has failed open on SG 1-02.

RCS pressure indicates 2200 psig SG 1-02 pressure indicates 1000 psig Main Steam flow on SG 1-02 indicates 200,000 lbm/hr Subsequently:

A complete MSL Isolation has occurred RCS pressure lowers to 1700 psig SG 1-02 pressure lowers to 500 psig Neglecting any change in steam density, Main Steam flow on SG 1-02 will indicate approximately __(1)__.

In accordance with EOP-2.0A, Faulted Steam Generator Isolation, AFW flow to SG 1-02 should be reduced to __(2)__.

A. (1) 100,000 lbm/hr (2) 0 gpm B. (1) 100,000 lbm/hr (2) 100 gpm C. (1) 141,000 lbm/hr (2) 0 gpm D. (1) 141,000 lbm/hr (2) 100 gpm Answer: C Page 43 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring the ability to determine the reduction in leak rate of a SG as SG pressure lowers.

Explanation:

A. Incorrect. 1st part is incorrect but plausible because the square root of the SG DP is not taken into account (500/1000) x 200 = 100. 2nd part is correct (See C).

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is incorrect but plausible because if all SGs were Faulted ECA-0.2A, Uncontrolled Depressurization of All SGs would direct reducing AFW flow to 100 gpm.

C. Correct. 1st part is correct, the DP between SG 1-02 and atmospheric pressure has dropped from 1000 psid to 500 psid. Taking the square root of this ratio results in a leak rate of 141 gpm (500/1000)1/2 x 200 = 141. 2nd part is correct, EOP-2.0A directs reducing AFW flow to zero on a faulted SG.

D. Incorrect. 1st part is correct (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) Generic Fundamentals Attached w/ Revision # See EOP-2.0A Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given an event that results in an excessive increase in secondary steam flow transient, DISCUSS accident analysis assumptions, predicted plant response, and analysis conclusions as described in the Final Safety Analysis Report.

(MCO.TA8.OB02)

Question Source: Bank #

Modified Bank # 23157 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 44 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23157 Revision:

Page 45 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23157 Revision:

Page 46 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Generic Fundamentals Revision: 3.5 Page 47 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-2.0A Revision: 9 Page 48 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 31-40 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 4 Tier 1 Group 1 K/A 000015.AK1.01 Level of Difficulty: 3 Importance Rating 4.4 Reactor Coolant Pump Malfunctions: Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Natural circulation in a nuclear reactor power plant Question # 41 Given the following conditions:

While operating at 100% power all RCPs tripped EOS-0.1A, Reactor Trip Response, is being performed SG levels are 40%

SG pressure is 1047 psig Indication that Natural Circulation flow is NOT ADEQUATE is supported by RCS cold leg temperatures indicating __(1)__.

To enhance Natural Circulation flow, SG __(2)__ should be raised.

A. (1) 552oF (2) level B. (1) 552oF (2) pressure C. (1) 561oF (2) level D. (1) 561oF (2) pressure Answer: C Page 1 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of indications of natural circulation flow flowing a loss of all RCPs.

Explanation:

A. Incorrect. First part is incorrect, but plausible since the RCS must be subcooled by more than 25oF, but that is based on RCS pressure, not SG pressure. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since changing SG pressure could enhance natural circulation, but by lowering it due to increasing steaming rate.

C. Correct. First part is correct. To support indication of natural circulation, RCS cold leg temperatures should be at saturation temperature for SG pressure, so cold leg temperature being 9oF above saturation is indication that natural circulation does not exist. Saturation temperature for 1047 psig is 552F. Second part is correct. Raising SG level adds cold water to the SG, increasing the difference in temperature between the heat source and heat sink, increasing the likelihood of natural circulation.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B)

Technical Reference(s) EOS-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: ANALYZE the Natural Circulation generic issue in the ERG network and proper operator response per the applicable Executive Volume. (ERG.XD5.OB04)

Question Source: Bank #

Modified Bank # 23172 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23172 Revision:

Page 3 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.1A Revision: 9 Page 4 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.1A Revision: 9 Page 5 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 4 Tier 1 Group 1 K/A 000025.G.2.4.4 Level of Difficulty: 3 Importance Rating 4.5 Loss of Residual Heat Removal System: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Question # 42 Given the following conditions:

RCS in Mid-Loop operations in preparation for Refueling Outage RCS cooldown on Train A RHR in progress RCS temperature 150°F stable Mansell indication 78 above core plate lowering RCS leakage has been reported Based on the above conditions, which of the following procedures should be entered?

A. ABN-103, Excessive Reactor Coolant Leakage B. ABN-104, Residual Heat Removal System Malfunction C. ABN-108, Shutdown Loss of Coolant D. ABN-909, Spent Fuel Pool/Refueling Cavity Malfunction Answer: B Page 6 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of entry conditions to ABNs for an RCS leak occurring while operating on RHR.

Explanation:

A. Incorrect. Plausible since ABN-103 is entered for an RCS leak in MODES 1, 2, and 3 with pressure above 1000 psig, but the unit is in MODE 5 or 6.

B. Correct. ABN-104 is entered for an RCS leak in MODE 5 with the RCS not filled or any time at reduced inventory.

C. Incorrect. Plausible since the RCS is Mode 5 or 6 and ABN-108 would be the correct procedure for an RCS leak if the RCS was still full.

D. Incorrect. Plausible since ABN-909 would be entered if the Refueling Cavity was filled and refueling activities were actually in progress.

Technical Reference(s) ABN-103 Attached w/ Revision # See ABN-104 Comments / Reference ABN-108 ABN-909 Proposed references to be provided during examination:

Learning Objective: DETERMINE the appropriate procedural section of ABN-104, Residual Heat Removal System Malfunction or ABN-108, Shutdown Loss of Coolant for an RCS or RHR malfunction. (ABN.104.OB01)

Question Source: Bank # 32761 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 7 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2018 NRC Exam Q91 Revision:

Page 8 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-103 Revision: 10 Page 9 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-104 Revision: 9 Page 10 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-108 Revision: 4 Page 11 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-909 Revision: 9 Page 12 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 000026.G.2.2.44 Level of Difficulty: 3 Importance Rating 4.2 Loss of Component Cooling Water: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Question # 43 Given the following conditions:

The Unit is in MODE 5 RCS temperature is 165ºF PRZR is solid RCS pressure is being maintained between 260 and 285 psig RHR System is in service at this time CCW to the RHR System is lost RCS temperature begins to rise ABN-104, Residual Heat Removal System Malfunction, in progress Based on conditions above, PCV-131, Letdown Pressure Control Valve, will throttle __(1)__

to maintain RCS pressure constant.

In accordance with ABN-104, the crew must stop all running RHR Pumps and isolate RHR if RCS temperature exceeds __(2)__.

A. (1) OPEN (2) 350°F B. (1) OPEN (2) 400°F C. (1) CLOSED (2) 350°F D. (1) CLOSED (2) 400°F Answer: A Page 13 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how the plant components will respond to a loss of CCW water and understanding of what is required per the procedure when RCS temperature exceeds a certain value.

Explanation:

A. Correct. First part is correct. Loss of CCW to the RHR System will cause RCS temperature to rise which will cause pressure to rise. When solid plant pressure control in progress, PCV-131 must be opened to maintain Reactor Coolant System pressure constant. Second part is correct, per ABN-104, Section 4, Step 3 and RNO, RHR pumps must be secured and RHR isolated when RCS temperature exceeds 350°F.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible because per ABN-104 RCS pressure is required to be maintained below 400 psig. 350°F and 400 psig could be easily confused.

C. Incorrect. First part is incorrect, but plausible if thought PCV-131 throttles to control pressure downstream of the valve instead of upstream. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-104 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a loss of RCS Temperature/Flow Control in accordance with ABN-104, RHR System Malfunctions. (ABN.104.OB03)

Question Source: Bank #

Modified Bank # 23349 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 Page 14 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23349 Revision:

Page 15 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 23349 Revision:

Page 16 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-104 Revision: 9 Page 17 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-104 Revision: 9 Page 18 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000027.AK2.03 Level of Difficulty: 2 Importance Rating 2.6 Pressurizer Pressure Control System Malfunction: Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners Question # 44 Given the following conditions:

Unit 1 100% power RCS Pressure 2190 psig lowering RC Loop 1 PRZR Spray Valve 455B RED light extinguished and GREEN light lit RC Loop 4 PRZR Spray Valve 455C RED Light lit and GREEN light lit PRZR Master Pressure Controller demand 40% lowering All PRZR Backup and Control Heaters ON Per ABN-705, Pressurizer Pressure Malfunction the Reactor Operator should take manual control of __(1)__.

if RCS pressure continues to lower, trip the Reactor and __(2)__.

A. (1) 1-PK-455A, PRZR Master Pressure Controller (2) stop RCPs B. (1) 1-PK-455A, PRZR Master Pressure Controller (2) initiate Safety Injection C. (1) 1-PK-455C, RC Loop 4 PRZR Spray Valve Controller (2) stop RCPs D. (1) 1-PK-455C, RC Loop 4 PRZR Spray Valve Controller (2) initiate Safety Injection Answer: C Page 19 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of actions required in the ABN for a Pressurizer Pressure malfunction related to a failed Spray valve controller.

Explanation:

A. Incorrect. First part is incorrect, but plausible (see B). Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible if thought that the Master Pressurizer Pressure Controller had failed, however, in this case the Master controller has responded to turn on all PRZR heaters in response to the lowering RCS pressure. Second part is incorrect, but plausible because with RCS pressure lowering it is reasonable to believe the ABN would direct SI initiation, however, the ABN directs stopping of RCPs as necessary to stop RCS Spray flow.

C. Correct. First part is correct. With only one spray valve indicating in the intermediate position and all PRZR heaters on the failure is an indication of an individual spray valve controller failure.

The ABN directs taking manual control of the failed spray valve controller and attempting to close.

Second part is correct. Step 1 RNO of the ABN directs stopping RCPs as necessary to stop RCS spray flow and stop the pressure reduction.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-705 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Pressurizer Pressure Instrument Malfunction in accordance with ABN-705, Pressurizer Pressure Malfunction. (ABN.705.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 20 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-705 Revision: 13 Page 21 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-705 Revision: 13 Page 22 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000029.EK1.03 Level of Difficulty: 2 Importance Rating 3.6 Anticipated Transient Without Scram: Knowledge of the operational implications of the following concepts as they apply to the ATWS:

Effects of boron on reactivity Question # 45 Unit 1 100% power when a Turbine Trip occurs without a Reactor Trip.

The RO adds negative reactivity by Emergency Borating per __(1)__.

The boration is achieved utilizing __(2)__ Boric Acid Transfer Pump(s).

A. (1) ABN-107, Emergency Boration (2) BOTH B. (1) ABN-107, Emergency Boration (2) EITHER C. (1) FRS-0.1A, Response to Nuclear Power Generation/ATWT (2) BOTH D. (1) FRS-0.1A, Response to Nuclear Power Generation/ATWT (2) EITHER Answer: C Page 23 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the operational requirements to add negative reactivity (effects of boron on reactivity) from an emergency boration during an ATWT.

Explanation:

A. Incorrect. First part is incorrect, but plausible because ABN-107 would be utilized to Emergency Borate in all other conditions except during an ATWT. Second part is incorrect, but plausible because two pumps are available and it could be thought that ABN-107 requires both pumps the same as FRS-0.1A.

B. Incorrect. First part is incorrect, but plausible (see A) . Second part is incorrect, but plausible because ABN-107 only requires one pump, however, ABN-107 is not the correct procedure to execute the emergency boration.

C. Correct. First part is correct , during an ATWT, the US will direct Emergency Boration via FRS-0.1A, Attachment 1.F, Initiation Emergency Boration. This is the only time Emergency Boration is initiated not using ABN-107. Second part is correct, FRS-0.1A, Attachment 1.F requires the use of all available Boric Acid Transfer Pumps to initiate Emergency Boration.

D. Incorrect. First part is correct (see C). Second part is incorrect , but plausible because the 1-02 Boric Acid Transfer Pump is normally in Pull-Out as it is aligned to draw suction from the X-02 Boric Acid Tank which is dedicated to Unit 2. It could be thought that this pump would only be used during a failure of the 1-01 Boric Acid Pump.

Technical Reference(s) FRS-0.1A Attached w/ Revision # See ABN-107 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRS-0.1A/B, Response to Nuclear Generation/ATWT in accordance with FRS-0.1. (ERG.FS1.OB04)

Question Source: Bank # 77177 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Page 24 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRS-0.1A Revision: 9 Page 25 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRS-0.1A Revision: 9 Page 26 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRS-0.1A Revision: 9 Page 27 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-107 Revision: 9 Page 28 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 000038.EA1.16 Level of Difficulty: 2 Importance Rating 4.4 Steam Generator Tube Rupture: Ability to operate and monitor the following as they apply to a SGTR: S/G atmospheric relief valve and secondary PORV controllers and indicators Question # 46 Given the following conditions:

A SGTR has occurred The crew has identified the affected SG The ruptured SG ARV controller setpoint is being adjusted The SG ARV controller setpoint should be set to __(1)__ to prevent __(2)__.

A. (1) 1160 psig (2) challenging the code safety valves while minimizing atmospheric releases B. (1) 1160 psig (2) the ruptured SG from depressurizing during the RCS maximum rate cooldown C. (1) 1125 psig (2) challenging the code safety valves while minimizing atmospheric releases D. (1) 1125 psig (2) the ruptured SG from depressurizing during the RCS maximum rate cooldown Answer: A Page 29 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how to control the SG ARV during a SGTR event.

Explanation:

A. Correct. First part is correct. 1160 psig is the setpoint selected. Second part is correct. The setpoint should be greater than no-load pressure to minimize atmospheric releases from the ruptured steam generator and less than the minimum safety valve setpoint to prevent lifting of the code safety valves.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible since it is desirable to prevent the SG from depressurizing as a result of the cooldown, but this is accomplished by isolating the SG from the intact SGs.

C. Incorrect. First part is incorrect, but plausible since this is the setpoint normally maintained on the ARVs except during SGTRs and cooldowns. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) EOP-3.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from EOP-3.0, STATE the purpose/basis for the step(s), in accordance with EOP-3.0, Steam Generator Tube Rupture. (ERG.E3A.OB04)

Question Source: Bank # 18507 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 30 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-3.0A Revision: 9 Page 31 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-3.0A Revision: 9 Page 32 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A WE12.EA2.02 Level of Difficulty: 3 Importance Rating 3.4 Uncontrolled Depressurization of all Steam Generators: Ability to determine and interpret the following as they apply to the Uncontrolled Depressurization of all Steam Generators: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments Question # 47 Given the following conditions:

Unit 2 was at full power when a MSL Break occurred OUTSIDE Containment MSIVs will NOT close from the control room An Operator was dispatched to locally close the MSIVs per EOP-0.0B, Reactor Trip or Safety Injection ECA-2.1B, Uncontrolled Depressurization of All Steam Generators, is entered A CAUTION statement before Step 2 of ECA-2.1B directs the operator to control AFW flow to maintain a minimum flow of 100 gpm to __(1)__SG with less than a setpoint value of

__(2)__.

A. (1) Each (2) 10% NR level B. (1) Each (2) 18% NR level C. (1) ONLY one (2) 10% NR level D. (1) ONLY one (2) 18% NR level Answer: A Page 33 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the actions to be taken in response to all SGs depressurizing in an uncontrolled manner.

Explanation:

A. Correct. First part is correct. All SGs to be fed at a minimum of 100 gpm with all SGs faulted.

Second part is correct. With no indication of adverse containment conditions, with the break outside containment, the level required is 10%.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible if adverse containment conditions existed, but with break outside containment, no adverse conditions should exist.

C. Incorrect. First part is incorrect, but plausible since any SG level above the minimum value meets heat sink requirements, but all SGs are to be fed. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ECA-2.1B Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions in ECA-2.1 in accordance with ECA-2.1. (ERG.C21.OB05)

Question Source: Bank # 82372 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC26 Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 34 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 82372 Revision:

Page 35 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

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Bank 82372 Revision:

Page 36 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

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ECA-2.1B Revision: 9 Page 37 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-2.1B Revision: 9 Page 38 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000054.AA1.02 Level of Difficulty: 3 Importance Rating 4.4 Loss of Main Feedwater: Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW): Manual startup of electric and steam-driven AFW pumps Question # 48 Given the following conditions:

Unit 1 20% power MDAFWP 1-01 out of service for maintenance Reactor is tripped due to trip of BOTH MFPs SG NR Levels are 40%

Upon entry into EOP-0.0A, Reactor Trip or Safety Injection, the TDAFWP __(1)__ started.

While performing the step to Verify AFW Alignment in EOP-0.0A, if AFW flow cannot be maintained > 460 gpm, go to FRH-0.1A, Response to a Loss of Secondary Heat Sink

__(2)__.

A. (1) must be manually (2) immediately B. (1) must be manually (2) upon completion of Attachment 2, Safety Injection Actuation Alignment C. (1) should have automatically (2) immediately D. (1) should have automatically (2) upon completion of Attachment 2, Safety Injection Actuation Alignment Answer: A Page 39 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of which AFW pumps require a manual start during a loss of MFW pumps event.

Explanation:

A. Correct. First part is correct. The TDAFWP does not automatically start on a trip of both MFPs. It will require a manual start under the given SGWLs provided. Second part is correct, per EOP-0.0A, Step 6 RNO, if AFW flow cannot be maintained greater than 460 gpm and no SG NR levels are greater than 43% then a transition to FRH-0.1A is required immediately.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible because a direct entry into FRH-0.1A did not exist in the CPNPP ERGs at EOP-0.0 step 6 until Rev 9 of the ERGs (current rev). In Rev 8 and previous an entry into FRH-0.1A could not be performed until Att 2 was complete.

C. Incorrect. First part is incorrect, but plausible because an automatic start signal to the MDAFWPs will exist due to a trip of BOTH MFPs, often the MDAFWP and TDAFWP auto start signals are confused. Additionally, because since SG NR levels are below 43% it could be thought that an auto start signal would be present to the TDAFWP. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) EOP-0.0A Attached w/ Revision # See ODA-407 Comments / Reference AFW Study Guide Proposed references to be provided during examination:

Learning Objective: EXPLAIN the instrumentation and controls of the Auxiliary Feedwater system and the system response in accordance with DBD-ME-206. (SYS.AF1.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 40 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-0.0A Revision: 9 Page 41 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

AFW Study Guide Revision: 00-0000 Page 42 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 9 Page 43 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 000055.G.2.4.35 Level of Difficulty: 2 Importance Rating 3.8 Station Blackout: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Question # 49 During a Station Blackout, an NEO is directed to locally perform additional load shedding per ECA-0.0A, Loss of All AC Power, Attachment 2C, DC Load Shed when DC Voltage Less than 110V.

This attachment is performed to allow for __(1)__ and __(2)__.

A. (1) battery charger restoration with portable generator (2) Containment Phase A isolation capability B. (1) battery charger restoration with portable generator (2) Safeguards Bus supply breaker closure C. (1) Diesel Generator field flashing (2) Containment Phase A isolation capability D. (1) Diesel Generator field flashing (2) Safeguards Bus supply breaker closure Answer: D Page 44 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of local actions taken during a station blackout.

Explanation:

A. Incorrect. Plausible because Attachments 2.A and 2.B when performed ensure sufficient time to restore battery chargers using a portable generator, however this is not what is accomplished by Attachment 2.C. The second part is incorrect but plausible (See C).

B. Incorrect. First part is incorrect but plausible (See A). Second part is correct (See D).

C. Incorrect. First part is correct (See D). The second part is incorrect but plausible because load shedding per Attachment 2.B is not performed until Phase A is verified, but Phase A does not require DC power to perform, only to verify.

D. Correct. If battery voltage lowers to less than 110 volts the associated bus is further load shed to ensure adequate voltage remains for flashing the diesel generator field or closing safeguards bus supply breakers for power restoration.

Technical Reference(s) ECA-0.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from ECA-0.0, DISCUSS the purpose/basis for the step(s) in accordance with ECA-0.0. (ERG.C00.OB05)

Question Source: Bank # 75812 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC24 Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 45 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 75812 Revision:

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Bank 75812 Revision:

Page 47 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

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ECA-0.0A Revision: 9 Page 48 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-0.0A Revision: 9 Page 49 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-0.0A Revision: 9 Page 50 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000056.AK3.02 Level of Difficulty: 2 Importance Rating 4.4 Loss of Offsite Power: Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power Question # 50 Given the following conditions:

LOOP has occurred Bus 1EA1 de-energized EOS-0.1A, Reactor Trip Response, in progress RCS temperature 561ºF stable Letdown has been lowered to 45 gpm with CCP 1-02 charging and FCV-121, Charging Flow Control Valve, full open RCS pressure 1920 psig trending down slowly Pressurizer level 5% slowly lowering Which of the following actions is required per EOS-0.1A, Reactor Trip Response, Fold Out Page?

A. Due to the loss of RCPs, verify Natural Circulation per EOS-0.1A, Reactor Trip Response.

B. Due to the loss of 1EA1, attempt to restore Bus 1EA1 per ABN-602, Response to a 6900V/480V System Malfunction.

C. Due to the low pressurizer level, manually actuate SI and return to EOP-0.0A, Reactor Trip or Safety Injection.

D. Due to the high RCS temperature, increase AFW flow to the Steam Generators per EOS-0.1A, Reactor Trip Response.

Answer: C Page 51 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the reason for actions required following a loss of offsite power.

Explanation:

A. Incorrect. Plausible because Natural Circulation would be verified if SI was not required per the Foldout Page.

B. Incorrect. Plausible because it would have been performed in EOP-0.0A, however, priority is Safety Injection (SI).

C. Correct. EOS-0.1A Foldout Page requires manual initiation of SI when PRZR level cannot be maintained greater than 6% and a transition back to EOP-0.0A.

D. Incorrect. Plausible because RCS temperature is above the no-load value of 557F, and increasing AFW flow would serve to cooldown the RCS, however, 561F RCS temperature is expected for the given conditions and this is not an action required per the FOP of EOS-0.1A.

Technical Reference(s) EOS-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.1, Reactor Trip Response. (ERG.E01.OB02)

Question Source: Bank # 34861 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC21 Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 52 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 34861 Revision:

Page 53 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 34861 Revision:

Page 54 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.1A Revision: 9 Page 55 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.1A Revision: 9 Page 56 of 56 CPNPP 2021-08 NRC Written Exam Worksheet 41-50 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000058.AA2.03 Level of Difficulty: 3 Importance Rating 3.5 Loss of DC Power: Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems Question # 51 Given the following conditions:

Unit 2 100% power Steam Break occurs outside containment Reactor Trip and Safety Injection initiated Battery Charger 2D2 load sheds Crew is performing EOP-2.0B, Faulted Steam Generator Isolation, Step 6 Verify Faulted SG(s) Break Inside Containment.

Per Step 6, the crew will direct an NEO to align Battery Charger __(1)__ to DC Bus 2D2 to ensure the __(2)__ remain closed.

A. (1) 2D4 (2) ARVs B. (1) 2D4 (2) MSIVs C. (1) 2D24 (2) ARVs D. (1) 2D24 (2) MSIVs Answer: D Page 1 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of a loss of a component supporting DC power (load shed of BC 2D2) on equipment monitored in the control room (MSIVs).

Explanation:

A. Incorrect. First part is incorrect, it is plausible to think BC 2D4 could supply DC Bus 2D2 since BC 2D24 may supply DC Bus 2D2, however, BC 2D4 cannot supply DC Bus 2D2. Second part is incorrect, but plausible since the ARVs are located within the same room, however, their DC solenoids are controlled by Safeguards DC power which are environmentally qualified.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. EOP-2.0B Attachment 2 directs alignment of BC 2D24 to DC Bus 2D2 after a Fault outside of containment to assure power is maintained to the batteries that supply power to the MSIV hydraulic oil pump solenoid operated valves. The SOVs open to align air to the hydraulic oil pump, which is required to open the MSIVs. Ensuring Battery 2D2 is powered from Battery Charger BC2D24 will ensure that the solenoids for the air to the oil pump remain closed. Second part is correct. The MSIVs are the affected component.

Technical Reference(s) EOP-2.0B Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: GIVEN a procedure step, or sequence of steps from EOP-2.0, state the purpose/bases for the step in accordance with EOP-2.0. (ERG.E2A.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 2 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-2.0B Revision: 9 Page 3 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-2.0B Revision: 9 Page 4 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-2.0B Revision: 9 Page 5 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 000062.AK3.03 Level of Difficulty: 2 Importance Rating 4.0 Loss of Nuclear Service Water: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water:

Guidance actions contained in EOP for Loss of nuclear service water Question # 52 Given the following conditions:

Unit 1 70% power 86-2 LOR fault occurs on Safeguards Bus 1EA2 Both 1EA2-1, INCOMING BKR, and 1EA2-2, INCOMING BKR trip open DG 1-02 automatically starts and DG 2 BKR 1EG2 automatically closes 1-ALB-1, Window 1.8 - SSWP 1/2 OVERLOAD/TRIP, alarms SSW Pump 1-02 handswitch indications are as follows:

o Amber MISMATCH light LIT o White TRIP light LIT Per ABN-501, Station Service Water System Malfunction, which of the following actions should be taken?

A. (1) Wait for the Blackout Sequencer to complete its timing and verify proper SSW flow to EDG 1-02 (2) Continue plant operations at approximately 70% power B. (1) Wait for the Blackout Sequencer to complete its timing and verify proper SSW flow to EDG 1-02 (2) Enter and perform the actions of EOP-0.0A, Reactor Trip or Safety Injection C. (1) Place DG 1-02 EMER STOP/START handswitch in PULL-OUT (2) Enter and perform the actions of EOP-0.0A, Reactor Trip or Safety Injection D. (1) Place DG 1-02 EMER STOP/START handswitch in PULL-OUT (2) Continue plant operations at approximately 70% power Answer: D Page 6 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the actions to be taken in the event of a loss of SSW.

Explanation:

A. Incorrect. First part is incorrect, but plausible because the BOS will fire to load the EDG and the SSW Pump will have an amber MISMATCH light until the sequencer sends a signal to start the pump, however, the white TRIP light is not expected and this is an indication that the pump has tripped and will not start on the sequencer timing. The immediate action per ABN-501 is to place the EDG in PULLOUT. Second part is correct (see D).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since the unit would be tripped if both buses were lost.

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see B)..

D. Correct. First part is correct. With the SSW Pump tripped, the EDG must be immediately tripped whether or not it is carrying the bus. Second part is correct. A loss of a single Safeguards Bus does not require the Unit be tripped.

Technical Reference(s) ABN-501A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to Station Service Water Pump Trip in accordance with ABN-501, Station Service Water System Malfunction. (ABN.501.OB101)

Question Source: Bank # 23103 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 7 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-501A Revision:

Page 8 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-501A Revision:

Page 9 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 000065.AK3.08 Level of Difficulty: 2 Importance Rating 3.7 Loss of Instrument Air: Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air Question # 53 Given the following conditions:

Unit 1 100% power After maintenance, the TDAFWP is recirculating to the CST at 2000 rpm per SOP-304A, AFW System, when:

o Unit 1 experiences a Loss of Instrument Air o Instrument Air pressure is 34 psig and lowering Which of the following:

(1) Identifies the impact on TDAFWP speed?

(2) What action should be taken to mitigate the situation?

A. (1) TDAFWP speed rises to maximum (2) Trip the Reactor and enter EOP-0.0A, Reactor Trip or Safety Injection B. (1) TDAFWP speed rises to maximum (2) Maintain plant conditions stable and manually control SG level by controlling the MFW Flow Control Valves C. (1) TDAFWP speed lowers to minimum (2) Trip the Reactor and enter EOP-0.0A, Reactor Trip or Safety Injection D. (1) TDAFWP speed lowers to minimum (2) Maintain plant conditions stable and manually control SG level by controlling the MFW Flow Control Valves Answer: A Page 10 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how the TDAFWP responds to a loss of instrument air and the actions needed to be taken as IA pressure lowers.

Explanation:

A. Correct. First part is correct. TDAFW Pump speed rises to maximum. Second part is correct.

Given the listed instrument air pressure, the Reactor should be tripped and EOP-0.0A entered B. Incorrect. First part is correct (see A). Second part is incorrect, plausible because it could be thought that the MFW Flow Control valves have accumulators to allow continued operation after a loss of instrument air similar to the accumulators for the AFW flow control valves.

C. Incorrect. First part is incorrect, but plausible since if thought that the TDAFW Pump speed will lower vice rise on a loss of air. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-301 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Loss of Instrument Air in accordance with ABN-301 Instrument Air System Malfunction. (ABN.301.OB04)

Question Source: Bank # 32803 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 11 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-301 Revision: 14 Page 12 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-301 Revision: 14 Page 13 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 4 Tier 1 Group 1 K/A 000077.AK2.06 Level of Difficulty: 3 Importance Rating 3.9 Generator Voltage and Electric Grid Disturbances: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Reactor power Question # 54 Given the following conditions:

Unit 2 90% power Main Generator load 1140 MWe Grid frequency has lowered from 60 Hz to 59.7 Hz When the Turbine Load Control system has restored Main Generator load to 1140 MWe, reactor power will be __(1)__ than 90%.

Per ABN-601, Response to a 138/345 KV System Malfunction, if Grid Frequency continues to lower, an IMMEDIATE Reactor Trip is FIRST required at __(2)__.

A. (1) higher (2) 57.5 Hz 57.2 Hz B. (1) higher (2) 59.4 Hz 58.5 Hz C. (1) lower (2) 57.5 Hz 57.2 Hz D. (1) lower (2) 59.4 Hz 58.5 Hz Answer: A Page 1 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of changing grid frequency on turbine load and reactor power.

Explanation:

A. Correct. First part is correct. Generator load will decrease with decreasing frequency (due to reduction in generator efficiency) and automatic load control will restore the load to the set load. This will result in increasing steam flow and increased reactor power.

Second part is correct. An immediate Reactor Trip will be required as Grid Frequency lowers to 57.5 57.2 Hz per ABN-601, Section 9, Step 3 table.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible because this is a recent change to ABN-601 in which continued operation at 59.4 Hz is now allowed automatic grid frequency relays provide for load shedding at frequency between 59.3 Hz and 58.5 Hz. In previous revisions a Reactor Trip was required if Grid Frequency had lowered to 59.4 Hz for 9 minutes. There are also significant actions taken in the ABN at this Hz level to divorce the Safeguards Busses from the grid.

C. Incorrect. First part is incorrect, but plausible because it could be thought Grid Frequency lowering would cause less load on the generator and therefore cause Reactor power to lower as Main Generator Control valves throttle down. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Attached w/ Revision #

Reference(s) ABN-601 See Comments /

Reference Proposed references to be provided during examination:

Learning ANALYZE the response to events described in accordance with ABN-Objective: 601, Response to 138/345 kV System Malfunction and ABN-602, Response to 6900/480 V System Malfunction. (ABN.601.OB00)

Question Source: Bank #

Modified Bank # 44282 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 Page 2 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 55.43 Comments /

Reference:

Bank 44282 Revision:

Page 3 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 44282 Revision:

Page 4 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-601 Revision: 16 17 Page 5 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Page 6 of 6 CPNPP 2021-08 NRC Written Exam Worksheet 54 As-Given

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A WE11.EA1.03 Level of Difficulty: 3 Importance Rating 3.7 Loss of Emergency Coolant Recirculation: Ability to operate and / or monitor the following as they apply to the Loss of Emergency Coolant Recirculation: Desired operating results during abnormal and emergency situations Question # 55 Given the following Unit 1 conditions:

ECA-1.1A, Loss of Emergency Coolant Recirculation, entered following a LOCA RCS subcooling margin 88ºF One Train of ECCS equipment has been secured RWST Make-up is being initiated Per ECA-1.1A, makeup to the RWST may be accomplished utilizing __(1)__.

Subsequently, ECA-1.1A directs the RCS be depressurized to establish a subcooling margin between 25ºF and 35ºF in order to __(2)__.

A. (1) RHUT X-01 (2) maximize CCP injection flow prior to RWST depletion B. (1) U2 RWST (2) maximize CCP injection flow prior to RWST depletion C. (1) RHUT X-01 (2) minimize RCS break flow D. (1) U2 RWST (2) minimize RCS break flow Answer: D Page 19 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of loss of coolant recirc procedures to obtain desired results.

Explanation:

A. Incorrect. First part is incorrect, but plausible because this is a borated makeup source utilized in other procedures to provide a makeup volume (i.e. SFPs). Second part is incorrect, but plausible since this would provide maximum makeup to RCS, but conflicts with objective to conserve RWST inventory.

B. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

C. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

D. Correct. First part is correct. ECA-1.1A, Attachment 3 allows use of U2 RWST as a source of makeup to the U1 RWST. Second part is correct. Depressurizing to minimize subcooling margin while cooling down ensures that the RCS is at the minimum pressure allowable while still maintaining the RCS subcooled. This minimizes RCS break flow and thereby minimizes the amount of makeup flow required to the RCS.

Technical Reference(s) ECA-1.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from ECA-1.1, STATE the purpose/basis for the step(s). (ERG.C11.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 20 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.1A Revision: 9 Page 21 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.1A Revision: 9 Page 22 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.1A Revision: 9 Page 23 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A WE05.EK2.01 Level of Difficulty: 3 Importance Rating 3.7 Loss of Secondary Heat Sink: Knowledge of the interrelations between the Loss of Secondary Heat Sink and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Question # 56 Given the following conditions:

Time = 0800:

Reactor power = 100%

Loss of all MFW occurs Time = 0820:

FRH-0.1A, Response to Loss of Secondary Heat Sink, in progress Condensate flow is to be established to the SGs CVCS Letdown is isolated In accordance with FRH-0.1A, before SG pressure is reduced, RCS pressure will be reduced to approximately __(1)__ to allow blocking of automatic SI actuation signals.

The PREFERRED method of RCS depressurization is to use __(2)__.

A. (1) 1910 psig (2) a Pressurizer PORV B. (1) 1910 psig (2) Auxiliary Spray C. (1) 1880 psig (2) a Pressurizer PORV D. (1) 1880 psig (2) Auxiliary Spray Answer: A Page 24 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the method of RCS depressurization during a loss of heat sink event.

Explanation:

A. Correct. 1st part is correct. RCS pressure is reduced to ~ 1910 psig to allow blocking of the low steam line pressure and low Przr pressure SI signals. 2nd part is correct. If letdown is not in service, the PORV is used to reduce pressure.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect because with letdown not in service, the PORV is used to reduce pressure. It is plausible because if letdown were in service, it would be correct.

C. Incorrect. 1st part is incorrect because FRH-0.1A directs you to reduce RCS pressure to ~ 1910 psig. It is plausible because 1880 psig is the trip value and above the value where the SI signal occurs. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) FRH-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1 in accordance with FRH-0.1, Loss of Heat Sink. (ERG.FH1.OB04)

Question Source: Bank # 77325 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 25 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1A Revision: 9 Page 26 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1A Revision: 9 Page 27 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A 000001.AK2.06 Level of Difficulty: 3 Importance Rating 3.0 Continuous Rod Withdrawal: Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: T-ave./ref.

deviation meter Question # 57 Given the following conditions:

Unit 1 60% power Rod Control in AUTO PT-505, First Stage Pressure Instrument fails, causing the Tave - Tref Deviation Meter to indicate -10oF Control rods begin stepping Crew enters ABN-709, Steam Line, Steam Header & Turbine 1st Stage Pressure &

Feed Header Pressure Instrument Malfunction Control rods are stepping __(1)__.

Per ABN-709, Control Rods should be placed in MANUAL and __(2)__.

A. (1) inward (2) are required to remain in MANUAL until the failed Turbine First Stage Pressure channel is repaired B. (1) inward (2) may be placed in AUTO after the alternate Turbine First Stage Pressure channel is selected C. (1) outward (2) are required to remain in MANUAL until the failed Turbine First Stage Pressure channel is repaired D. (1) outward (2) may be placed in AUTO after the alternate Turbine First Stage Pressure channel is selected Answer: D Page 28 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the relationship between the Tave-Tref deviation meter and rod movement.

Explanation:

A. Incorrect. First part is incorrect, but plausible since a Tave-Tref deviation will cause rod motion, but indication of -10oF will result in outward rod motion. Second part is incorrect, but plausible because other systems that utilize first stage pressure (i.e. Steam Dumps) are required to be maintained in off-normal condition (steam dumps must be maintained in Steam Pressure Mode vs Tave Mode). Also, on a Tcold failure the rods must remain in Manual until the failed Tcold channel is repaired.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D)

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct. Tave-Tref deviation meter indicating -10oF will result in outward rod motion. Second part is correct, per ABN-709 after selecting the alternate channel on 1-PS-505Z rods may be placed back in AUTO.

Technical Reference(s) ABN-709 Attached w/ Revision # See Rod Control Study Guide Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Turbine Impulse Pressure Instrument Malfunction in accordance with ABN-709 Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure and Feed Header Pressure Instrument Malfunction.

(ABN.710.OB07)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Page 29 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-709 Revision: 10 Page 30 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-709 Revision: 10 Page 31 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-709 Revision: 10 Page 32 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Rod Control Study Guide Revision: 00-0000 Page 33 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A 000024.AA1.10 Level of Difficulty: 2 Importance Rating 3.3 Emergency Boration: Ability to operate and / or monitor the following as they apply to Emergency Boration: Boric acid storage tank Question # 58 Given the following conditions:

Unit 1 Reactor has tripped During the Reactor Trip, the RO notes the following indications on DRPI:

o Control Rod F-14 at 212 steps o Control Rod H-2 at 228 steps o Control Rod M-12 at 6 steps o All other rods at bottom 1-ALB-6B, Window 3.1 - BAT 1 LVL LO-LO, in alarm Boric Acid Tank X-01 level 54%

The crew is required to Emergency Borate __(1)__ in response to these conditions.

BAT X-01 __(2)__ have the required Technical Specification MINIMUM level for the given plant conditions.

A. (1) 3600 gallons (2) does B. (1) 5400 gallons (2) does C. (1) 3600 gallons (2) does NOT D. (1) 5400 gallons (2) does NOT Answer: B Page 34 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the BAT operability requirements.

Explanation:

A. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

B. Correct. First part is correct. Three rods not fully inserted requires 5400 gallons of boric acid to ensure adequate SDM. Second part is correct. Minimum required volume is 50%.

C. Incorrect. First part is incorrect, but plausible since a rod stuck at 6 steps could be considered to be fully inserted, but the requirement is that 1800 gallons of boric acid is required for any rod not fully inserted. Second part is incorrect, but plausible since it could be thought that the LO-LO level alarm is indicative of the BAT being inoperable.

D. Incorrect. First part is correct (see B). Second part is incorrect, but plausible (see C).

Technical Reference(s) EOP-0.0A Attached w/ Revision # See OPT-104A-1 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given the Reactor Makeup system parameter indications and plant conditions, ASSESS from memory any required Technical Specification/TRM entries, including any actions which must be completed within one hour in accordance with Technical Specifications and TRM. (SYS.CS2.OB06)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 35 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-0.0A Revision: 9 Page 36 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OPT-104A-1 Revision: 21 Page 37 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A 000037.AK3.05 Level of Difficulty: 3 Importance Rating 3.7 Steam Generator Tube Leak: Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak:

Actions contained in procedures for radiation monitoring, RCS water inventory balance, S/G tube failure, and plant shutdown Question # 59 Given the following conditions:

Unit 1 100% power Current plant conditions as follows:

o PRZR level 60% stable o Letdown flow 130 gpm o CCP 1-01 in service o COG-182, Condenser Off-Gas Radiation Monitor, in RED alarm o N16-175, # 2 Main Steam Line N16 Radiation Monitor, in RED alarm o MSL-179, # 2 Main Steam Line Radiation Monitor, in RED alarm ABN-106, High Secondary Activity, in progress Subsequently:

Unit 1 performed a rapid shutdown in accordance with IPO-003A, Power Operations Based on indications provided, the primary-to-secondary leak rate is __(1)__.

Per ABN-106, the subsequent RCS cooldown is to be__(2)__.

A. (1) > 75 gpd, but < 3600 gpd (2.5 gpm)

(2) limited to a rate of 100oF per hour B. (1) > 75 gpd, but < 3600 gpd (2.5 gpm)

(2) established at maximum achievable rate without causing a MSLI C. (1) > 3600 gpd (2.5 gpm)

(2) limited to a rate of 100oF per hour D. (1) > 3600 gpd (2.5 gpm)

(2) established at maximum achievable rate without causing a MSLI Answer: C Page 38 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the indications of a SG tube leak and the reason for actions taken to recover.

Explanation:

A. Incorrect. First part is incorrect, but plausible since N16-175 minimum sensitivity is 1 gpd and has a range up to 150 gpd. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since the initial cooldown during a SGTR, during the performance of EOP-3.0, is at the maximum achievable rate.

C. Incorrect. First part is correct (see D). Second part is correct. The cooldown rate used in ABN-106 is limited to 100oF per hour.

D. Correct. First part is correct. MSL-179 minimum sensitivity and being in alarm indicates the leak is greater than 2.5 gpm (3600 gpd). Second part is incorrect (see B).

Technical Reference(s) ABN-106 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Steam Generator Tube Leakage greater than or equal to 75 gpd in accordance with ABN-106, High Secondary Activity.

(ABN.106.OB02)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 39 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 40 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 41 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-106 Revision: 11 Page 42 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A 000059.AA1.01 Level of Difficulty: 2 Importance Rating 3.5 Accidental Liquid Radwaste Release: Ability to operate and / or monitor the following as they apply to the Accidental Liquid Radwaste Release: Radioactive-liquid monitor Question # 60 PC-11, Digital Radiation Monitoring System is alarming and the display for 1-RE-5100, Turbine Building Sump 1-02 Radiation Detector is RED.

1-RE-5100, Turbine Building Sump 1-02 Radiation Detector has a(an) __(1)__ alarm.

In accordance with ALM-3200, Alarm Procedure DRMS, the Radwaste Operator should verify Turbine Building drains have shifted to the __(2)__.

A. (1) OPERATE FAILURE (2) Co Current Waste System B. (1) OPERATE FAILURE (2) Low Volume Waste Pond C. (1) HIGH (2) Co Current Waste System D. (1) HIGH (2) Low Volume Waste Pond Answer: C Page 43 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring the ability to monitor radiation monitor alarms during liquid waste releases.

Explanation:

A. Incorrect. First part is incorrect, but plausible because PC-11 can have an OPERATE FAILURE alarm with automatic actions but has a BLUE display. Second part is correct. Procedure ALM-3200 directs the crew to verify the proper automatic actions have occurred per Attachment

3. RE-5100 in alarm or with an OPERATE FAILURE diverts from LVW to Cocurrent Waste.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since the path is shifted between LVW and Cocurrent Waste, but from LVW to Cocurrent Waste, not the reverse.

C. Correct. First part is correct. Red alarm is indication of an actual high radiation condition. Second part is correct (see A).

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ALM-3200 Attached w/ Revision # See ABN-903 Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the response to an Accidental Release of Radioactive Liquid in accordance with ABN-903, Accidental Release of Radioactive Liquid.

(ABN.201.OB13)

Question Source: Bank # 36101 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2009 NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 44 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-903 Revision: 8 Page 45 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-903 Revision: 8 Page 46 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-3200 Revision: 5 Page 47 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-3200 Revision: 5 Page 48 of 48 CPNPP 2021-08 NRC Written Exam Worksheet 51-60 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A 000068.G.2.4.34 Level of Difficulty: 3 Importance Rating 4.2 Control Room Evacuation: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

Question # 61 Given the following conditions:

Both units 100% power A fire in the Control Room requires it to be evacuated ABN-803A, Response to a Fire in The Control Room or Cable Spreading Room is being performed In accordance with ABN-803A:

ONLY the ____(1)____ Safeguards Bus will be energized by its associated EDG when complete.

The EDG is started from the ____(2)____.

A. (1) Train A (2) RSP B. (1) Train A (2) EDG room C. (1) Train B (2) RSP D. (1) Train B (2) EDG room Answer: B Page 1 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of specific RO tasks performed outside the control room for control room evacuation as well as the resultant operational effect.

Explanation:

A. Incorrect. 1st part is correct. Only 1EA1 will be energized with the EDG. 2nd part is incorrect because the EDG is started locally. It is plausible because the EDG breaker and bus feeder breaker controls are located at the RSP.

B. Correct. 1st part is correct (see A). 2nd part is correct. The EDG is started locally before the operator at the RSP gains control of it.

C. Incorrect. 1st part is incorrect because ONLY the Train A EDG will be powering its respective bus. It is plausible because both 1EA1 and 1EA2 are de energized in the procedure prior to energizing Train A from its associated EDG. 2nd part is incorrect but plausible (see A).

A. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is correct (see B).

Technical Reference(s) ABN-803A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Fire in the Electrical or Control Building in accordance with ABN-803, Response To A Fire In The Control Room Or Cable Spreading Room. (ABN.803.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 2 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-803A Revision: 13 Page 3 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-803A Revision: 13 Page 4 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A 000076.AK2.01 Level of Difficulty: 2 Importance Rating 2.6 High Reactor Coolant Activity: Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors Question # 62 Given the following conditions:

Unit 1 in Mode 3 during a cool down for a mid-cycle outage to replace a damaged seal package on an RCP RCS temperature 390ºF and pressure 780 psig CCP 1-01 in operation with one 75 gpm orifice isolation valve open 1-RE-0406 (FFL160), Gross Failed Fuel Monitor, has alarmed Chemistry reports RCS specific activity has increased steadily over the past several days Per ABN-102, High Reactor Coolant Activity, letdown flow should be _____ to minimize personnel radiation exposure during the outage.

A. lowered to 0 gpm B. lowered to 45 gpm C. raised to 120 gpm D. raised to 195 gpm Answer: C Page 5 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the response of the radiation monitoring system to high RCS activity.

Explanation:

A. Incorrect. Plausible since isolating letdown will prevent the activity from circulating in the Auxiliary and Safeguards Buildings, but it will not reduce RCS activity impacting future dose.

B. Incorrect. Plausible since reducing letdown will minimize the activity circulating in the Auxiliary and Safeguards Buildings while still allowing some cleanup of the RCS, but it will not maximize the reduction in RCS activity impacting future dose.

C. Correct. Letdown flow should be increased to a maximum value, but less than 140 gpm, to allow mechanical filtration of the letdown flow via the mixed bed demineralizers, minimizing future dose.

D. Incorrect. Plausible as all letdown valves open would give this value but flow is limited to 140 gpm when RCS temp is 500 degrees.

Technical Reference(s) ABN-102 Attached w/ Revision # See SOP-103A Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the response to High Reactor Coolant Activity in accordance with ABN-102, High Reactor Coolant Activity. (ABN.103.OB01)

Question Source: Bank # 75843 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC-24 Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 6 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Exam Bank 75843 Revision:

Page 7 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Exam Bank 75843 Revision:

Page 8 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-102 Revision: 8 Page 9 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-103A Revision: 18 Page 10 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A WE02.EK1.02 Level of Difficulty: 2 Importance Rating 3.4 SI Termination: Knowledge of the operational implications of the following concepts as they apply to the SI Termination: Normal, abnormal and emergency operating procedures associated with SI Termination.

Question # 63 Given the following conditions:

An SI has occurred due to a fault on SG 1-02 The operators have completed the actions of EOP-2.0A, Faulted Steam Generator Isolation, and transitioned to EOP-1.0A, Loss of Reactor or Secondary Coolant Containment pressure 7 psig slowly decreasing Total AFW flow to the intact SGs is 480 gpm All intact SG levels between 7% and 22%

PRZR pressure 1725 psig rapidly increasing All PRZR level channels indicate between 23% and 28%

CETs indicating 540ºF stable Which of the following would PROHIBIT terminating Safety Injection under these conditions?

A. Subcooling B. RCS pressure C. RCS inventory D. Secondary heat sink Answer: C Page 11 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the parameters used to determine if SI Termination can be implemented.

Explanation:

A. Incorrect. Plausible since this is one of the parameters required to be met to terminate SI

(> 55°F), but it is met as subcooling is approximately 76°F.

B. Incorrect. Plausible since this is one of the parameters required to be met to terminate SI (stable or increasing), but it is met as pressure is increasing.

C. Correct. RCS inventory is not adequate since 34% level is required with adverse containment conditions. The crew would be directed to stabilize pressure and transition to EOS-1.1A when SI flow restores adequate pressurizer level.

D. Incorrect. Plausible since this is one of the items required to be met to terminate SI (> 460 gpm or at least one intact SG level > 26%), but it is met as AFW is 480 gpm.

Technical Reference(s) EOP-1.0A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination: Steam Tables Learning Objective: IDENTIFY the proper transitions out of EOP-1.0 in accordance with EOP-1.0, Loss of Reactor or Secondary Coolant. (ERG.E1A.OB05)

Question Source: Bank # 62538 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 12 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOP-1.0A Revision: 9 Page 13 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A WE13.EK3.02 Level of Difficulty: 4 Importance Rating 2.9 Steam Generator Overpressure: Knowledge of the reasons for the following responses as they apply to the Steam Generator Overpressure: Normal, abnormal and emergency operating procedures associated with Steam Generator Overpressure.

Question # 64 Given the following conditions:

Unit 1 entered FRH-0.2A, Response to Steam Generator Overpressure, due to high pressure in SG 1-01 Attempts to lower SG 1-01 pressure are unsuccessful The crew is directed to cool down the RCS using the remaining three SGs Which of the following describes the reason for cooling the RCS hot leg temperature to less than 535ºF?

Ensure A. SG pressure is below the highest SG safety valve setpoint.

B. adequate subcooling in the RCS exists to continue RCP operation.

C. steam pressure supplied to the TDAFW pump is within design limits.

D. excessive heat transfer from the RCS is not the cause of the overpressure.

Answer: D Page 14 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the reasons for performing actions in response to a SG overpressure condition.

Explanation:

A. Incorrect. Plausible since it is preferred to not lift a safety valve, but maintaining the SG at normal temperature would keep the pressure below the safety setting.

B. Incorrect. Plausible since it is desirable to operate RCPs, but higher pressure would assure adequate subcooling.

C. Incorrect. Plausible since the TDAFWP may be the supply of AFW to the SGs, but higher pressure will not affect the TDAFWP capability.

D. Correct. Cooling down the RCS to less than 535oF ensures excessive heat transfer from the RCS is eliminated thereby reducing temperature and pressure of the affected SG.

Technical Reference(s) FRH-0.2A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.2 in accordance with FRH-0.2, Response to Steam Generator Overpressure. (ERG.FH2.OB04)

Question Source: Bank # 32622 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 15 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.2A Revision: 9 Page 16 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.2A Revision: 9 Page 17 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A WE09.EA2.02 Level of Difficulty: 2 Importance Rating 3.4 Natural Circulation Operations: Ability to determine and interpret the following as they apply to the Natural Circulation Operations:

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Question # 65 During EOS-0.2A, Natural Circulation Cooldown, following a reactor trip, which of the following criteria determines if the amount of RCS subcooling required is 75oF or 125oF?

A. Pressurizer level B. RCS cooldown rate C. Number of CCPs running D. Number of CRDM fans running Answer: D Page 18 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the subcooling limit based on plant conditions during a natural circulation cooldown.

Explanation:

A. Incorrect. Plausible since ERG decisions are based upon pressurizer level, but the subcooling required in EOS-0.2A is based upon the amount of vessel head cooling available from the CRDM fans.

B. Incorrect. Plausible since ERG decisions are based upon RCS pressure, but the subcooling required in EOS-0.2A is based upon the amount of vessel head cooling available from the CRDM fans.

C. Incorrect. Plausible since ERG decisions are based upon the number of CCPs operating, but the subcooling required in EOS-0.2A is based upon the amount of vessel head cooling available from the CRDM fans.

D. Correct. The amount of subcooling required in EOS-0.2A is based upon the amount of vessel head cooling available, which is dependent on the number of CRDM fans running.

Technical Reference(s) EOS-0.2A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the recovery technique used and the procedure steps of EOS-0.2, Natural Circulation Cooldown. (ERG.E02.OB02)

Question Source: Bank # 62529 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 19 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2A Revision: 9 Page 20 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2A Revision: 9 Page 21 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EOS-0.2A Revision: 9 Page 22 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.1.23 Level of Difficulty: 2 Importance Rating 4.3 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Question # 66 Procedures or work instructions with complex or infrequent work activities for which consequences of an improper action could have immediate, possibly irreversible impact on safety, production or reliability are classified as __(1)__ procedures.

__(2)__ are generally classified as these type of procedures.

A. (1) Information Use (2) Operations Department Work Instructions B. (1) Information Use (2) System Operating Procedures C. (1) Continuous Use (2) Operations Department Work Instructions D. (1) Continuous Use (2) System Operating Procedures Answer: D Page 23 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how procedures are be implemented in accordance with administrative requirements.

Explanation:

A. Incorrect. First part is incorrect, but plausible since these are procedures or work instructions with work activities, but are performed frequently and have no immediate consequences if performed improperly. Second part is incorrect, but plausible since OWIs are considered Information Use procedures.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see B).

D. Correct. First part is correct. Continuous Use procedures are procedures or work instructions with complex or infrequent work activities for which consequences of an improper action could have immediate, possibly irreversible impact on safety, production or reliability.

Second part is correct. SOPs are considered to be Continuous Use.

Technical Reference(s) STA-201 Attached w/ Revision # See ODA-407 Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE requirements for Procedure Use and Adherence in accordance with ODA-102, ODA-407, STA-201 and Operations Guideline 3. (ADM.XA3.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 24 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-201 Revision: 18 Page 25 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 26 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.1.29 Level of Difficulty: 2 Importance Rating 4.1 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Question # 67 As part of a clearance, several normally locked closed valves were tagged.

During restoration, a _______ locking tab should be reapplied to these valves.

A. Red B. Green C. Blue D. Yellow Answer: B Page 27 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of how to identify locked closed valves during clearance restorations.

Explanation:

A. Incorrect. Plausible as this is the color used to identify normally locked open or off positions.

B. Correct. This is the color used to identify normally locked closed positions.

C. Incorrect. Plausible as this is the color used to identify normally locked throttled positions.

D. Incorrect. Plausible as this is the color used for personal safety.

Technical Reference(s) ODA-403 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the administrative controls of valves, breakers and other equipment required to be secured-in-position in accordance with ODA-403 and OWI-103.

(ADM.XA1.OB10)

Question Source: Bank #

Modified Bank # 75848 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 28 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75848 Revision:

Page 29 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75848 Revision:

Page 30 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-403 Revision: 8 Page 31 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.1.43 Level of Difficulty: 2 Importance Rating 4.1 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Question # 68 In accordance with ODA-102, Conduct of Operations, Attachment 8, Operations Reactivity Management, complete the following statements.

When performing a reactor startup with a designated Reactivity SRO providing oversight, the RO is required to inform the designated Reactivity SRO __(1)__ the Unit Supervisor PRIOR TO each 50 step rod pull.

Informing the designated Reactivity SRO and/or the Unit Supervisor when each control rod movement is COMPLETE __(2)__ required.

A. (1) AND (2) is B. (1) AND (2) is NOT C. (1) OR (2) is D. (1) OR (2) is NOT Answer: C Page 32 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the administrative procedures governing reactivity manipulations of the plant.

Explanation:

A. Incorrect. First part is incorrect, but plausible because the Unit Supervisor is in charge of the startup so it would make sense that they are informed prior to the first rod pull. Second part is correct. Notification after each rod pull is required.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible because if performing multiple rod pulls (example given in ODA-102 is for restoring CBD after an instrument failure), notification of completion of the last movement is required.

C. Correct. ODA-102 states the Reactor Operator informs the Unit Supervisor or the designated SRO providing reactivity oversight prior to moving control rods and at the completion of rod movement.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ODA-102 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the requirements for manipulating reactor controls in accordance with ODA-102, STA-102 and STA-601. (ADM.XA1.OB06)

Question Source: Bank # 72316 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 33 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-102 Revision: 34 Page 34 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-102 Revision: 34 Page 35 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-102 Revision: 34 Page 36 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.2.4 Level of Difficulty: 2 Importance Rating 3.6 Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Question # 69 Unit 1 plant equipment labels are __(1)__.

Common equipment/alarms are normally controlled by __(1)__.

A. (1) blue (2) Unit 1 B. (1) yellow (2) Unit 2 C. (1) blue (2) Unit 2 D. (1) yellow (2) Unit 1 Answer: A Page 37 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of differences between units.

Explanation:

A. Correct. First part is correct. Unit 1 uses blue labeling and Unit 2 uses yellow labeling. Second part is correct. Common systems are normally controlled by Unit 1.

B. Incorrect. First part is incorrect, but plausible since yellow is used for labeling for one of the units, but it is Unit 2. Second part is incorrect, but plausible since only one of the units normally controls common equipment, but it is Unit 1, not Unit 2.

C. Incorrect. First part is correct (see A). Second part is incorrect, but plausible (see B).

D. Incorrect. First part is incorrect, but plausible (see B). Second part is correct (see A).

Technical Reference(s) OWI-402 Attached w/ Revision # See ODA-102 Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the administrative requirements for operating plant equipment; performing routine watchstanding evolutions and maintaining system status and plant configuration control in accordance with ODA-106, STI-604.03, OWI-207, ODA-102, ODA-410, ODA-407, OWI-107, STA-694, STA-601 and OWI-409.

(ADM.XA1.OB09)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam 2017 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Page 38 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2017 NRC Exam Q69 Revision:

Page 39 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2017 NRC Exam Q69 Revision:

Page 40 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

OWI-402 Revision: 5 Page 41 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-102 Revision: 35 Page 42 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.2.14 Level of Difficulty: 2 Importance Rating 3.9 Knowledge of the process for controlling equipment configuration or status.

Question # 70 The Shift Manager has directed a Verification Lineup performed on a system.

While performing the Verification Lineup, independent verification of the lineup __(1)__

required to be completed.

If a valve is found out of position, the operator performing the lineup should __(2)__.

A. (1) is (2) obtain specific permission prior to repositioning the valve B. (1) is (2) position the valve to the required position and document the repositioning on the lineup attachment C. (1) is NOT (2) obtain specific permission prior to repositioning the valve D. (1) is NOT (2) position the valve to the required position and document the repositioning on the lineup attachment Answer: C Page 43 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of procedures associated with maintaining system configuration control.

Explanation:

A. Incorrect. First part is incorrect, but plausible since independent verification is required for Initial Lineups. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since this is how an Initial Lineup would be performed.

C. Correct. First part is correct. Independent verification is not required for Verification Lineups unless a component must be repositioned. Second part is correct. Component repositioning requires specific permission prior to being operated.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ODA-410 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the administrative requirements for operating plant equipment; performing routine watchstanding evolutions and maintaining system status and plant configuration control in accordance with ODA-106, STI-604.03, OWI-207, ODA-102, ODA-410, ODA-407, OWI-107, STA-694, STA-601 and OWI-409.

(ADM.XA1.OB09)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 44 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-410 Revision: 16 Page 45 of 45 CPNPP 2021-08 NRC Written Exam Worksheet 61-70 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.2.35 Level of Difficulty: 2 Importance Rating 3.6 Ability to determine Technical Specification Mode of Operation.

Question # 71 If a Unit is in the process of cooling down for refueling, complete the following statements regarding the Mode of operation:

If average coolant temperature = 195oF, the plant is considered to be in __(1)__.

Mode 6 is INITIALLY declared when the __(2)__ Reactor Vessel Head Closure Bolt is detensioned.

A. (1) MODE 4, Hot Shutdown (2) first B. (1) MODE 4, Hot Shutdown (2) last C. (1) MODE 5, Cold Shutdown (2) first D. (1) MODE 5, Cold Shutdown (2) last Answer: C Page 1 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the definitions of different modes of operation.

Explanation:

A. Incorrect. First part is incorrect, but plausible since if it were 5 degrees hotter, it would be correct.

Second part is correct. With one RPV head bolt not fully tensioned, the unit is considered to be in Mode 6.

B. Incorrect. First part is incorrect but plausible (see A). Second part is incorrect, but plausible because it could be thought that all RPV head closure bolts must be detensioned to enter Mode 6 as this is similar to exit when all bolts must be tensioned.

C. Correct. First part is correct. If RCS temperature is < 200oF, the unit is considered to be in Cold Shutdown (Mode 5). 2nd part is correct (see A).

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) TS 1.1-1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DISCUSS the terms defined in Technical Specifications. (RLS.SL1.OB01)

Question Source: Bank #

Modified Bank # 71459 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 2 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank Question 71459 Revision:

Page 3 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank Question 71459 Revision:

Page 4 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 1.1-1 Revision: 150 Page 5 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.3.4 Level of Difficulty: 2 Importance Rating 3.2 Knowledge of radiation exposure limits under normal or emergency conditions.

Question # 72 Per STA-655, Exposure Monitoring Program, the normal annual administrative exposure limit that can be received, without an administrative extension or Planned Special Exposure, by an operator is __(1)__ mRem Total Effective Dose Equivalent.

Per EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, the Emergency Exposure limit to save a life is __(2)__ Rem.

A. (1) 2000 (2) 10 B. (1) 2000 (2) 25 C. (1) 4000 (2) 10 D. (1) 4000 (2) 25 Answer: B Page 6 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of annual and emergency radiation exposure limits.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible because 10 REM is the emergency limit for protecting valuable property.

B. Correct. First part is correct. Per STA-655 ATT 8.A the administrative limit without an extension has been set at CPNPP for operators at 2000 mrem. Second part is correct. Per EPP-305, the emergency dose limit to save a life is 25 REM.

C. Incorrect. First part is incorrect, but plausible since 4000 mrem is the limit with an approved extension but no extension is allowed in the stem of the question. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) STA-655 Attached w/ Revision # See EPP-305 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a known total exposure, CALCULATE the remaining exposure permitted before exceeding an administrative exposure limit in accordance with STA-655, Exposure Monitoring Program, and an NRC exposure limit in accordance with 10CFR20, Standards for Protection Against Radiation. (ADM.RAD.OB05)

Question Source: Bank #

Modified Bank # 75850 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Page 7 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75850 Revision:

Page 8 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75850 Revision:

Page 9 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-655 Revision: 23 Page 10 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EPP-305 Revision: 14 Page 11 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 3 Group K/A 2.3.15 Level of Difficulty: 3 Importance Rating 2.9 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Question # 73 You are exiting an RCA and approach the portable frisker which is reading 275 cpm background radiation.

(1) Are you allowed to perform your whole body frisk in an area with background radiation at this level?

(2) You should be considered to have received contamination if the frisker rises to a MINIMUM value of __(2)__.

A. (1) NO (2) 100 cpm above background B. (1) NO (2) double the background C. (1) YES (2) 100 cpm above background D. (1) YES (2) double the background Answer: A Page 12 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of personnel monitoring equipment use.

Explanation:

A. Correct. First part is correct. Frisking may only be performed in areas with the background radiation < 200 cpm. Second part is correct. Contamination is identified by being 100 cpm above background.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect. It is plausible because this would be indication of contamination in this case, but minimum level to be considered contaminated is 100 cpm above background.

C. Incorrect. 1st part is incorrect because background count rates are > 200 cpm, therefore NO (not allowed). It is plausible because it is well over the preferred background level (100 cpm). 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect, but plausible (see C). 2nd part is incorrect, but plausible (see B).

Technical Reference(s) STA-653 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a set of contamination conditions, DETERMINE the posting requirements for the area in accordance with RPI-304, Radiological Posting and Labeling.

(ADM.RAD.OB02)

Question Source: Bank #

Modified Bank # 82575 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Page 13 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 82575 Revision:

Page 14 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 82575 Revision:

Page 15 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-653 Revision: 21 Page 16 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-653 Revision: 21 Page 17 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 3 Group K/A 2.4.6 Level of Difficulty: 2 Importance Rating 3.7 Knowledge of EOP mitigation strategies.

Question # 74 Which of the following actions should NOT be performed prior to direction from the US in an Emergency Response Guideline?

A. Isolating AFW flow to a single faulted SG.

B. Throttling AFW flow to control a ruptured SG level within the required band.

C. Adjusting RCP seal injection flow to maintain within the required range of flow.

D. Securing a CCP to prevent overfilling the Pressurizer following an inadvertent SI.

Answer: D Page 18 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to Explanation:

A. Incorrect. Plausible because this is a numbered step in EOP-2.0, but the ERG Rules of Usage addresses this as being acceptable.

B. Incorrect. Plausible because this is a numbered step in EOP-3.0, but the ERG Rules of Usage addresses this as being acceptable.

C. Incorrect. Plausible because this is a numbered step in EOS-0.1, but the ERG Rules of Usage addresses this as being acceptable.

D. Correct. Performing steps out of sequence is allowed, but must be done with caution to prevent masking symptoms or defeating the intent of the EOP being used. Although terminating SI early might be beneficial to prevent filling the Pressurizer if the only event is a spurious SI, this may result in further degradation of the plant if another undiagnosed event is in progress.

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the requirements associated with deviating from an ERG in accordance with ODA-407, Operations Department Procedure Use and Adherence. (ERG.XD2.OB25)

Question Source: Bank # 23501 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC20 Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Page 19 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23501 Revision:

Page 20 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23501 Revision:

Page 21 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 22 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.4.17 Level of Difficulty: 2 Importance Rating 3.9 Knowledge of EOP terms and definitions.

Question # 75 While performing an Emergency Operating Procedure, the Unit Supervisor observes an asterisk next to a step number.

The asterisk indicates the step...

A. is only applicable under Adverse Containment conditions.

B. is to be performed from memory and verbalized upon completion.

C. must be completed in its entirety before the subsequent step is started.

D. is a continuous action that applies until superseded or no longer applies.

Answer: D Page 23 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of symbols used in the ERG network.

Explanation:

A. Incorrect. Plausible as Adverse containment parameters are specified in ERG's by parentheses.

B. Incorrect. Plausible as Initial Action are designated by diamond symbol.

C. Incorrect. Plausible as steps in ABNs and ERGs do not have to be completed prior to proceeding to next step. They just have to be started and have assurance that it is progressing. Step where this does not apply have to be designated.

D. Correct. An asterisk designates a continuous action step, which applies from that point in the procedure until superseded or no longer applies.

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the expectations associated with performing immediate action, continuous action and radiation hazard steps and how each is identified in the Emergency Response Guidelines. (ERG.XD2.OB05)

Question Source: Bank # 41924 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Page 24 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 25 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 26 of 26 CPNPP 2021-08 NRC Written Exam Worksheet 71-75 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 2 Group 1 K/A 006.A2.13 Level of Difficulty: 2 Importance Rating 4.2 Emergency Core Cooling: Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent SIS actuation Question # 76 Given the following conditions:

Unit 1 in MODE 3 waiting to enter MODE 2 An Inadvertent Train A Safety Injection occurs The Unit Supervisor __(1)__ expected to exercise procedure expediency as described in Operations Guideline 3, Attachment 6, Strategies for Successful Transient Mitigation.

An Inadvertent Safety Injection places a challenge on the __(2)__.

A. (1) is NOT (2) PRZR safeties B. (1) is (2) PRZR safeties C. (1) is NOT (2) RCS cooldown rate D. (1) is (2) RCS cooldown rate Answer: B Page 1 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the procedural strategy in response to an inadvertent safety injection.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

Explanation:

A. Incorrect. First part is incorrect, but plausible as no accident has occurred and it may be thought that terminating SI is secondary to stabilizing the plant. Second part is correct (see B).

B. Correct. First part is correct. Procedure expediency is required to prevent overfilling the pressurizer. Second part is correct. Overfilling the pressurizer could result in water damage to the pressurizer safety valves.

C. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since adequate heat removal existed without SI and it could be thought that the additional heat removal would result in an excessive RCS cooldown condition.

D. Incorrect. First part is correct (see B). Second part is incorrect, but plausible (see C).

Technical Reference(s) Ops Guideline 6, Att 3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: LIST three beneficial functions and one possible problem caused by SI flow during accident conditions. (ERG.XD4.OB01)

Question Source: Bank #

Modified Bank # 75863 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 2 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 3 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75863 Revision:

Page 4 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 75863 Revision:

Page 5 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Ops Guideline 6, Att 3 Revision: 10-21-2019 Page 6 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 013.G.2.2.25 Level of Difficulty: 2 Importance Rating 4.2 Engineered Safety Features Actuation: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Question # 77 In accordance with TSB 3.3.2, ESFAS Instrumentation, the reason the following signals use a 2 of 4 logic to actuate, vice a 2 of 3 logic to actuate, is:

Low Pressurizer Pressure Safety Injection logic __(1)__.

High-3 Containment Pressure logic __(2)__.

A. (1) is used for both protection and control functions (2) requires additional redundancy because it energizes to trip B. (1) is used for both protection and control functions (2) is used for both protection and control functions C. (1) requires additional redundancy because it energizes to trip (2) requires additional redundancy because it energizes to trip D. (1) requires additional redundancy because it energizes to trip (2) is used for both protection and control functions Answer: A Page 7 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of TS bases for ESFAS instrumentation.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring knowledge of TS bases that is required to analyze TS-required actions and terminology.

Explanation:

A. Correct. First part is correct. Pressurizer pressure provides both control and protection functions and actuation logic must be able to withstand both an input failure to control system, and a single failure in the other channels providing the protection function actuation. Thus, four channels are required to satisfy the requirements with a two-out-of-four logic. Second part is correct. This is one of the only functions that requires the bistable output to energize to perform its required action. Four channels are used in a two-out-of-four logic configuration because this function is energize to trip.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible if thought that reason for pressurizer pressure logic also applied to high-3 logic.

C. Incorrect. First part is incorrect, but plausible if thought that pressurizer pressure was energized to actuate. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) TSB 3.3.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given ESFAS operability status or parameter indications, various plant conditions, and a copy of regulatory requirements (TS, TRM, etc.), ASSESS any LCO entries, applicable conditions, and required actions (including completion time) in accordance with the associated regulatory requirement(s) and their bases. (SYS.ES1.OB08)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2 Page 8 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 9 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.3.2 Revision: 77 Page 10 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.3.2 Revision: 77 Page 11 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.3.2 Revision: 77 Page 12 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.3.2 Revision: 77 Page 13 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 4 Tier 2 Group 1 K/A 022.G.2.4.18 Level of Difficulty: 3 Importance Rating 4.0 Containment Cooling: Knowledge of the specific bases for EOPs.

Question # 78 Given the following conditions:

A LOCA has occurred inside Unit 1 Containment Containment pressure rose to 21.8 psig, resulting in a Containment Spray actuation Containment pressure has subsequently lowered to 9.4 psig and is continuing to lower slowly Due to multiple RHR malfunctions, entry has been made to ECA-1.1A, Loss of Emergency Coolant Recirculation All Containment Fan Coolers were stopped by the SI signal Per ECA-1.1A, Containment Fan Coolers may _______, WITHOUT consulting Plant Staff.

A. be restarted, under the above conditions B. be restarted, once Containment pressure drops below 5 psig C. NOT be restarted, due to a lack of CCW flow to HVAC Chill Water D. NOT be restarted, due to potential water hammer damage to HVAC Chill Water Answer: D Page 14 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the bases when non-safety containment cooling equipment can be started in the event of an accident.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. Plausible since CS is to be secured and it is desirable to restore some form of containment cooling and a step in the procedure directs restarting the coolers, but only if pressure has remained below 5 psig (without consulting plant staff).

B. Incorrect. Plausible since CS is to be secured and pressure must be below 5 psig to operate the fan coolers and a step in the procedure directs restarting the coolers, but it must have remained below 5 psig for the duration of the event otherwise a Plant Staff evaluation is required prior to starting the coolers.

C. Incorrect. Plausible since CCW flow must be verified to the Chillers or they cannot be started, but there is no reason to think that CCW flow cannot be restored.

D. Correct. With containment pressure above 5 psig, the cooling water for the containment coolers may be saturated and water hammer may occur in the system if chill water is restored. Plant Staff must be consulted to evaluate the effects of water hammer prior to restarting.

Technical Reference(s) ECA-1.1 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural step, or sequence of steps from ECA-1.1, STATE the purpose/basis for the step(s). (ERG.C11.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 15 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 16 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.1A Revision: 9 Page 17 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.1A Revision: 9 Page 18 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 1 K/A 063.A2.02 Level of Difficulty: 2 Importance Rating 3.1 DC Electrical Distribution: Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of ventilation during battery charging Question # 79 Given the following conditions:

Unit 1 100% power Battery 1ED1 in EQUALIZE on 125 VDC BATTERY CHARGER BC1ED1-1 Battery Room Exhaust Fan 7 running with Battery Room Exhaust Fan 8 in standby RO reports Battery Room Exhaust Fan 7 tripped and Battery Room Exhaust Fan 8 did not AUTO start and will NOT manually start Battery Room temperature 81oF stable Which of the following completes the statement below?

To ensure ___(1)___ is maintained within limits, the battery should be placed in FLOAT per

___(2)___.

A. (1) room temperature (2) ALM-0112A, 2.4, BATT RM EXH FN 8 AUTO START FAIL B. (1) room temperature (2) ALM-0112A, 2.3, BATT RM TRN A TEMP HI/LO-LO C. (1) hydrogen concentration (2) ALM-0112A, 2.4, BATT RM EXH FN 8 AUTO START FAIL D. (1) hydrogen concentration (2) ALM-0112A, 2.3, BATT RM TRN A TEMP HI/LO-LO Answer: C Page 19 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the concern of a loss of ventilation while charging a battery and the procedure and actions required to address this.

SRO Only: SRO Only due to requiring an assessment of plant conditions and then the selection of a section of a procedure to mitigate or recover, or with which to proceed.

Explanation:

A. Incorrect. 1st part is incorrect, but plausible because there is a TRM limit for temperature and the exhaust fan draws air through the battery room, however, the reason for placing the battery on float is for hydrogen concentration. 2nd part is correct. The procedure that directs placing the battery on float is correct, ALM-0112A, 2.4.

B. Incorrect. 1st part is incorrect, but plausible (see A). 2nd part is plausible since room temperature would direct starting a second fan, but the correct procedure is ALM-0112A, 2.4.

C. Correct. The battery should be placed in FLOAT to minimize the buildup of hydrogen gas. This is directed by ALM-0112A, Window 2.4, BATT RM EXH FN 8 AUTO START FAIL.

A. Incorrect. 1st part is correct (see C). 2nd part is incorrect, but plausible (see B).

Technical Reference(s) ALM-0112A, 2.4 Attached w/ Revision # See SOP-805A Comments / Reference ALM-0112A, 2.3 Proposed references to be provided during examination:

Learning Objective: EXPLAIN the normal, abnormal and emergency operation of the DC Electrical Distribution system in accordance with procedures:

1) SOP 605A 125 VDC SWITCHGEAR AND DISTRIBUTION SYSTEMS, BATTERIES AND BATTERY CHARGERS

2) SOP 606A 24/48V & 125/250 VDC SWITCHGEAR AND DISTRIBUTION SYSTEMS, BATTERIES & BATTERY CHARGERS

3) Review loss of DC loads in accordance with DBD-EE-044 DC POWER SYSTEMS. (SYS.DC1.OB04)

Question Source: Bank # 50415 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2020 Retake (Previous)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 20 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 21 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0112A Revision: 6 Page 22 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0112A, 2.4 Revision: 6 Page 23 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ALM-0112A, 2.3 Revision: 6 Page 24 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

SOP-805A Revision: 11 Page 25 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 1 K/A 103.A2.05 Level of Difficulty: 3 Importance Rating 3.9 Containment: Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency containment entry Question # 80 Unit 1 is operating in Mode 1.

A confirmed report of sabotage has occurred rendering the PAL INNER door INOPERABLE due to damaged hinges inside containment The PAL OUTER door remains OPERABLE No further sabotage has occurred The Security threat has ended An Emergency Containment Entry has been approved to repair the PAL INNER door

1) Per STA-620, CONTAINMENT ENTRY, which of the following is required to be completed PRIOR to EMERGENCY Containment Entry?

2) Per Technical Specification Bases 3.6.2, Containment Air Locks, the PREFERRED method of Containment Entry to repair the INOPERABLE PAL INNER door is to enter A. (1) RWP issuance (2) the PAL from the OUTER door B. (1) RWP issuance (2) through the EAL and access the PAL from inside containment C. (1) Containment briefing by Shift Manager (2) the PAL from the OUTER door D. (1) Containment briefing by Shift Manager (2) through the EAL and access the PAL from inside containment Answer: D Page 26 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of procedures used for emergency containment entry requirements.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis, assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed, as well as requiring knowledge of Tech Spec bases.

Explanation:

A. Incorrect. First part is incorrect, but plausible since STA-620 allows for the RWP to be completed after entry has occurred in a timely manner consistent with related emergency response activities. Second part is incorrect, but plausible as TS allows entry and exit of affected Airlock doors to perform repairs, however, an SRO must understand that TSB 3.6.2 Bases states this is not the preferred method to access the affected component.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A)

D. Correct. First part is correct. STA-620 states that a Containment briefing should be held by the Shift Manager. Each RWO entering into Containment should ensure that all questions on the checklist have been reviewed and that all entry members understand their responsibilities.

Second part is correct. TSB 3.6.2 explicitly states that it is preferred the air lock be accessed from inside primary containment by entering through another operable airlock door.

Technical Reference(s) TS 3.6.2 Attached w/ Revision # See TSB 3.6.2 Comments / Reference STA-620 Proposed references to be provided during examination:

Learning Objective: APPLY the administrative requirements of the Containment system including Technical Specifications, TRM and ODCM: 3) Containment Air Locks 3.6.2 (SYS.CY1.OB05)

Question Source: Bank #

Modified Bank # 82582 (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC Exam Q89 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5/2 Page 27 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 28 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 29 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2017 NRC Q89 Revision:

Page 30 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2017 NRC Q89 Revision:

Page 31 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

2017 NRC Q89 Revision:

Page 32 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.6.2 Revision: 150 Page 33 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS Bases 3.6.2 Revision: 74 Page 34 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-620 Revision: 15 Page 35 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-620 Revision: 15 Page 36 of 36 CPNPP 2021-08 NRC Written Exam Worksheet 76-80 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 2 Group 2 K/A 034.K4.03 Level of Difficulty: 4 Importance Rating 3.3 Fuel-Handling Equipment: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Overload protection Question # 81 In accordance with TR LCO 13.9.33, Refueling Machine bases, the Refueling Machine Auxiliary Monorail Hoist is used for __(1)__ and has a load indicator used to prevent lifting of loads in excess of __(2)__.

A. (1) latching, unlatching and movement of control rod drive shafts (2) 2800 pounds B. (1) lifting a fuel assembly with a control rod inserted (2) 2800 pounds C. (1) latching, unlatching and movement of control rod drive shafts (2) 600 pounds D. (1) lifting a fuel assembly with a control rod inserted (2) 600 pounds Answer: C Page 1 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the overload protection associated with refueling cranes.

SRO Only: SRO Only due to being addressed by 10 CFR 55.43(b)(7), assessment of surveillance requirements for the refueling mode.

Explanation:

A. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

B. Incorrect. First part is incorrect, but plausible since the main hoist is used for lifting a fuel assembly with a control rod inserted. Second part is incorrect, but plausible since 2800 pounds is the overload limit for the main hoist.

C. Correct. First part is correct. The auxiliary hoist is typically used for latching, unlatching and movement of control rod drive shafts. Second part is correct. 600 pounds is the cutoff limit for the auxiliary hoist.

D. Incorrect. First part is incorrect, but plausible (see B). Second part is correct (see C).

Technical Reference(s) TR/TRB 13.9.33 Attached w/ Revision # See RFO-102 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given access to Technical Specifications and a refueling activity, APPLY the appropriate specification. (OPD1.G16.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 7 Page 2 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TR 13.9.33 Revision: 77 Page 3 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TRB 13.9.33 Revision: 77 Page 4 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

RFO-102 Revision: 13 Page 5 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 2 K/A 056.A2.04 Level of Difficulty: 3 Importance Rating 2.8 Condensate: Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps Question # 82 Given the following conditions:

Unit 1 80% power B Condensate Pump trips ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, entered During the runback:

o MFP suction pressure lowers to 210 psig for 35 seconds and recovers to 350 psig and stable o 1-ALB-6D, window 2.7 - ANY CONTROL ROD BANK AT LO-LO LIMIT, alarms Per ABN-302, the US should ensure __(1)__.

In accordance with TS 3.1.6, Control Bank Insertion Limits, rods must be restored above the rod insertion limit within __(2)__.

A. (1) Main Feedwater Pump A has tripped (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. (1) Main Feedwater Pump A has tripped (2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. (1) 1-PV-2286, LP FW HTR BYP VLV has opened (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. (1) 1-PV-2286, LP FW HTR BYP VLV has opened (2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Answer: C Page 6 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the effect of a loss of a Condensate Pump will have on the condensate system.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1) and 10 CFR 55.43(b)(5) .

Explanation:

A. Incorrect. First part is incorrect, but plausible because MFP A would have tripped if Feedwater pressure had lowered to 190 psig for 30 seconds. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A) . Second part is incorrect, but plausible since many more TS actions are 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months requirements than 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months requirements.

C. Correct. First part is correct. When Feedwater pressure falls below 250 psig, ABN-302, Section 3.0, Step 2.b RNO requires the US to ensure PV-2286 is open. Second part is correct. Rods are to be restored above RIL within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-302 Attached w/ Revision # See TS 3.1.6 Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Condensate Pump Trip in accordance with ABN-302, Feedwater, Condensate, Heater Drains System Malfunction.

(ABN.302.OB02)

Question Source: Bank #

Modified Bank # 41844 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2/5 Page 7 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 8 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 41844 Revision:

Page 9 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 41844 Revision:

Page 10 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-302 Revision: 14 Page 11 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-302 Revision: 14 Page 12 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

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Reference:

ABN-302 Revision: 14 Page 13 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.1.6 Revision: 156 Page 14 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 2 Group 2 K/A 086.G.2.1.20 Level of Difficulty: 2 Importance Rating 4.6 Fire Protection: Ability to interpret and execute procedure steps.

Question # 83 Given the following conditions:

Due to a fire, the Shift Manager has directed the Control Room evacuated A Unit 1 Natural Circulation cooldown is to be performed The cooldown should be performed using __(1)__ per the guidance contained in __(2)__.

A. (1) Steam Dumps (2) ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room B. (1) Steam Dumps (2) EOS-0.2A, Natural Circulation Cooldown C. (1) SG ARVs (2) ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room D. (1) SG ARVs (2) EOS-0.2A, Natural Circulation Cooldown Answer: C Page 15 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the content of procedures related to fires in the Control Room or cable spreading room.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) analysis involves both (1) assessing plant conditions (normal, abnormal, or emergency) and then (2) selecting a procedure or section of a procedure to mitigate or recover, or with which to proceed. One area of SRO-level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.

Explanation:

A. Incorrect. First part is incorrect, but plausible since a cooldown via the steam dumps is normally preferred over using the ARVs. Second part is correct. ABN-803A contains a note that once the decision to evacuate the control room is made, ERGs are no longer applicable.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible because if control room evacuation was not performed, the natural circulation cooldown would be performed per the guidance of EOS-0.2A.

C. Correct. First part is correct. Any plant cooldown performed from outside the control room is performed using the SG ARVs. Second part is correct (see A).

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-803A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to a Fire in the Electrical or Control Building in accordance with ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room . (ABN.803.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 16 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 17 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-803A Revision: 16 Page 18 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-803A Revision: 16 Page 19 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 000007.EA2.04 Level of Difficulty: 3 Importance Rating 4.6 Reactor Trip, Stabilization, Recovery: Ability to determine or interpret the following as they apply to a reactor trip: If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP Question # 84 Given the following conditions:

An ATWT event occurred on Unit 1 FRS-0.1A, Response to Nuclear Power Generation/ATWT, in progress and the Reactor still NOT tripped Boration CANNOT be initiated because of blockage in the Boration flowpaths All Power Range Channels indicate 6%

Startup rate is zero on BOTH Intermediate Range Channels Average CET temperature 580°F slowly lowering Which of the following describes the operator actions under these conditions and the reason for taking these actions?

A. Exit FRS-0.1A because the zero startup rate on the Intermediate Range channels indicate actions taken in FRS-0.1A have been successful.

B. Remain in FRS-0.1A, and allow the RCS to heat up, adding negative reactivity, while continuing efforts to establish Emergency Boration.

C. Exit FRS-0.1A because the lowering CET temperatures indicate actions taken in FRS-0.1A have been successful.

D. Remain in FRS-0.1A, and lower RCS temperature, establishing DNBR margin, while continuing efforts to establish Emergency Boration.

Answer: B Page 20 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the actions taken in response to an ATWT condition.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose and knowledge of diagnostic steps and decision points in the emergency operating procedures (EOPs) that involve transitions to event-specific sub-procedures or emergency contingency procedures.

Explanation:

A. Incorrect. Plausible since a zero startup rate would not meet the entry conditions for FRS-0.1A if power ranges were below 5% so it could be considered that exit conditions are met.

B. Correct. Exit conditions have not been met in FRS-0.1A, as power range is still above 5%. While attempting establish boration, the RCS is allowed to heat up to add negative reactivity.

C. Incorrect. Plausible since a there is a transition from FRS-0.1 based on CET temperatures, though it is to SAMGs on high temperature.

D. Incorrect. First part is incorrect, but plausible as conditions to exit FRS have not been met.

Second part is incorrect, but plausible since it is a true statement but has no bearing on the performance of FRS-0.1A.

Technical Reference(s) FRS-0.1A Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRS-0.1A/B, Response to Nuclear Generation/ATWT in accordance with FRS-0.1. (ERG.FS1.OB04)

Question Source: Bank #

Modified Bank # 33641 (Note changes or attach parent)

New Question History: Last NRC Exam LC20 (Original Modified)

Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 21 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 22 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 33641 Revision:

Page 23 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 33641 Revision:

Page 24 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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FRS-0.1A Revision: 9 Page 25 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRS-0.1A Revision: 9 Page 26 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 1 K/A 000008.G.2.4.21 Level of Difficulty: 2 Importance Rating 4.6 Pressurizer Vapor Space Accident: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Question # 85 Given the following on Unit 1:

A Reactor Trip and SI have occurred EOP-1.0A, Loss of Reactor or Secondary Coolant, in progress Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection complete All RCPs have been stopped RVLIS - All lights are DARK CNTMT PRESS (IR) indicating 6.5 psig stable PRZR LVL indicating > 100%

RCS HL PRESS (WR) indicating 1400 psig stable CORE EXIT TEMP indicating 765ºF rising RCS HL TEMP (WR) indicating 685 ºF rising A(an) __(1)__ break has occurred.

A transition to __(1)__ is required.

A. (1) RCS cold leg (2) FRC-0.2A, Response to Degraded Core Cooling B. (1) RCS cold leg (2) FRC-0.1A, Response to Inadequate Core Cooling C. (1) PRZR steam space (2) FRC-0.2A, Response to Degraded Core Cooling D. (1) PRZR steam space (2) FRC-0.1A, Response to Inadequate Core Cooling Answer: C Page 27 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the parameters used to determine the conditions of the RCS following a PRZR steam space break.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures.

Explanation:

A. Incorrect. First part is incorrect, but plausible since all indication other than PRZR level support indication of a cold leg break on the RCS. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since an ORANGE path condition exists and for all CSFSTs except FRC, a RED and an ORANGE path condition direct entry into the highest FRG associated with the function.

C. Correct. First part is correct, with RVLIS dark and PRZR level full, this indicates a steam space break. Second part is correct, with RCS less than 1200°F, superheated, No RVLIS indication, and temp >750°F, FRC-0.2 entry conditions have been met.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) FRC-0.1 Attached w/ Revision # See Loss of Coolant Accident Analysis LP Comments / Reference Proposed references to be provided during examination:

Learning Objective: EXPLAIN the operational implications associated with all cautions, notes and actions of the Response to Inadequate Core Cooling procedure in accordance with FRC-0.1 (ERG.FC1.OB03)

Question Source: Bank # 18479 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 28 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 29 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRC-0.1A Revision: 9 Page 30 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Loss of Coolant Accident Analysis (PRZR) Revision: 00-0000 Page 31 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A 000022.AA2.02 Level of Difficulty: 3 Importance Rating 3.7 Loss of Reactor Coolant Makeup: Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:

Charging pump problems Question # 86 Given the following conditions:

Unit 1 100% power CCP 1-01 in service VCT level 50%

1-FI-121A, CHRG FLO 130 gpm stable 1-FI-132, LTDN FLO 120 gpm stable 1/1-LCV-112B, VCT TO CHRG PMP SUCT VLV spuriously closes The following alarms are received; 1-ALB-6A, Window 1.4 - REGEN HX LTDN OUT TEMP HI 1-ALB-6A, Window 3.4 - CHRG FLO HI/LO What action must be taken and the procedure used?

A. Stop CCP 1-01 and then isolate letdown per SOP-103A, Chemical and Volume Control System.

B. Stop CCP 1-01 and then isolate letdown per ABN-105, Chemical and Volume Control System Malfunction.

C. Isolate letdown and then stop CCP 1-01 per SOP-103A, Chemical and Volume Control System.

D. Isolate letdown and then stop CCP 1-01 per ABN-105, Chemical and Volume Control System Malfunctions.

Answer: B Page 32 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring diagnostic of charging problems and required actions.

SRO Only: SRO Only due to assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed Explanation:

A. Incorrect. Plausible because the actions stated are correct, however, ABN-105 is the correct procedure to use.

B. Correct. This is a symptom of pump cavitation due to suction valve being closed. The RNO actions of ABN-105 direct the operator to stop the CCP and isolate Letdown.

C. Incorrect. Plausible because actions stated are correct, however, they must be performed in the opposite order in accordance with ABN-105.

D. Incorrect. Plausible because actions stated are correct, however, they must be performed in the opposite order.

Technical Reference(s) ABN-105 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: EVALUATE plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation while responding to a Chemical and Volume Control System malfunction.

Question Source: Bank # 2103 NRC Q77 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2013 NRC Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 33 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 34 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-105 Revision: 8 Page 35 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A 000057.G.2.2.42 Level of Difficulty: 2 Importance Rating 4.6 Loss of Vital AC Instrument Bus: Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

Question # 87 Given the following conditions:

Unit 2 at 800 MWe Loss of 118 VAC Instrument Distribution Inverter IV2EC1 occurs ABN-603, Loss of Protection or Instrument Bus, in progress Per ABN-603, the Unit Supervisor INITIALLY directs energizing 2EC1 by aligning __(1)__ to supply 2EC1.

Per TS 3.8.9, Distribution Systems - Operating, the above action is required to be completed within a MAXIMUM of __(2)__.

A. (1) 120 VAC Bypass Distribution Panel 2EC3 (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. (1) 120 VAC Bypass Distribution Panel 2EC3 (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. (1) TRN A 118 VAC RPS/SFGD BOP Installed Spare Inverter IV2EC1/3 (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. (1) TRN A 118 VAC RPS/SFGD BOP Installed Spare Inverter IV2EC1/3 (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Answer: A Page 36 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of abnormal condition procedures which contain the guidance for restoring power to a Vital AC Instrument Bus and the associated Technical Specification.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1).

Explanation:

A. Correct. First part is correct. In accordance with ABN-603, the US will direct an operator in the field to energize 2EC1 via its alternate power supply, 2EC3, by sliding the manual transfer switch to the alternate position at the bottom of the instrument panel. Second part is correct. In accordance with TS 3.8.9, Condition 'B', the AC Vital bus subsystem will be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Per TS 3.8.9 Bases re-energizing Instrument Panel 2EC1 via its alternate power supply will restore it to OPERABLE status.

B. Incorrect. First part is correct (see A). Second part is incorrect, but plausible as TS 3.8.9 Condition 'A' requires an AC electrical power distribution subsystem to be restored within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Condition 'A' applies to 6900V and 480V distribution subsystems and is commonly confused with Condition 'B'.

C. Incorrect. First part is incorrect, but plausible since the next step of ABN 603 is to initiate actions to place the swing inverter, IV2EC1/3, in service. However, this must be performed per SOP-607B and will take some time to perform. Per TS 3.8.9 Bases re-energizing Instrument Panel 2EC1 via the swing inverter will also restore it to OPERABLE status. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) ABN-603 Attached w/ Revision # See TS/TSB 3.8.9 Comments / Reference 208/120 VAC, 118 VAC., Inv. & Lighting LP Proposed references to be provided during examination:

Learning Objective: ANALYZE the response to Loss of a Protection Bus in accordance with ABN-603, Loss of Protection or Instrument Bus. (ABN.603.OB01)

Question Source: Bank # 75858 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC24 Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 Page 37 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 55.43 2 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 38 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 75858 Revision:

Page 39 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 75858 Revision:

Page 40 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ABN-603 Revision: 8 Page 41 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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208/120 VAC, 118 VAC., Inv. & Lighting Revision: 01-0001 Lesson Page 42 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.8.9 Revision: 156 Page 43 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.8.9 Revision: 82 Page 44 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 1 K/A WE04.EA2.01 Level of Difficulty: 3 Importance Rating 4.3 LOCA Outside Containment: Ability to determine and interpret the following as they apply to the LOCA Outside Containment: Facility conditions and selection of appropriate procedures during abnormal and emergency operations Question # 88 Given the following conditions:

Unit 1 Reactor has been tripped due to a lowering RCS pressure Indications are that an RCS leak has occurred outside containment ECA-1.2A, LOCA Outside Containment, has been entered In accordance with ECA-1.2A, cycle __(1)__ closed, then open.

If RCS pressure continues to lower, GO TO __(2)__.

A. (1) 1/1-8809A and B, RHR TO CL INJ ISOL VLVS (2) EOP-1.0A, Loss of Reactor or Secondary Coolant B. (1) 1/1-8809A and B, RHR TO CL INJ ISOL VLVS (2) ECA-1.1A, Loss of Emergency Coolant Recirculation C. (1) 1/1-8840, RHR TO HL 2 & 3 INJ ISOL VLV (2) EOP-1.0A, Loss of Reactor or Secondary Coolant D. (1) 1/1-8840, RHR TO HL 2 & 3 INJ ISOL VLV (2) ECA-1.1A, Loss of Emergency Coolant Recirculation Answer: B Page 45 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring the ability to determine the selection of appropriate procedures during a LOCA outside containment.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis involving both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed, including knowledge of the content of the procedure versus knowledge of the procedure's overall mitigative strategy or purpose.

Explanation:

A. Incorrect. First part is correct. These valves are normally open, so you are directed to close them and check RCS pressure to see if the leak has stopped. Second part is incorrect, but plausible since a loss of reactor coolant exists. If the leak has not been stopped, you are directed to GO TO ECA-1.1A.

B. Correct. First part is correct (see A). Second part is correct. If the leak still exists, you are directed to GO TO ECA-1.1A.

C. Incorrect. First part is incorrect, but plausible since these valves are verified closed. They are normally closed so it would not be prudent to open them to check for a leak. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) ECA-1.2 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: IDENTIFY the proper transitions out of ECA-1.2 (ERG.C12.OB06)

Question Source: Bank # 72564 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 46 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 47 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.2 Revision: 9 Page 48 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ECA-1.2 Revision: 9 Page 49 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 1 K/A WE05.G.2.2.40 Level of Difficulty: 3 Importance Rating 4.7 Loss of Secondary Heat Sink: Ability to apply Technical Specifications for a system.

Question # 89 Given the following conditions:

1/2-PCV-455A, PRZR PORV, is stuck in mid-position and will not cycle 1/2-8000A, PRZR PORV BLK VLV, is CLOSED and deenergized In accordance with TS 3.4.11, Pressurizer Power Operated Relief Valves (PORVs),

1/2-8000A __(1)__.

Approximately twenty-four hours later:

The Unit has experienced a Loss of Secondary Heat Sink following a reactor trip from 100% power FRH-0.1B, Response to Loss of Secondary Heat Sink, in progress When Bleed and Feed operations are established, 1/2-8000A should __(2)__.

A. (1) can remain in this condition indefinitely (2) be re-energized and opened to ensure adequate bleed path B. (1) can remain in this condition indefinitely (2) remain de-energized and closed to comply with Technical Specifications C. (1) must be restored to operable within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (2) be re-energized and opened to ensure adequate bleed path D. (1) must be restored to operable within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (2) remain de-energized and closed to comply with Technical Specifications Answer: C Page 50 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring application of TS conditions associated with components used for bleed and feed during a loss of secondary heat sink event.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1) and 10 CFR 55.43(b)(5) Analysis requiring assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed.

Explanation:

A. Incorrect. First part is incorrect, but plausible since PORV block valve does not have to be deenergized for seat leakage and indefinite operation is permitted for these conditions, per condition A of TS. Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since PORV is closed in accordance with Tech Specs and re-opening will violate Tech Specs.

C. Correct. First part is correct, with a PORV stuck and unable to be manually cycled, the PORV block valve is required to be closed and deenergized. The PORV must be restored to an operable condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . These are all part of condition B of TS. Second part is correct. FRH-0.1B requires re-energizing and opening a previously de-energized and closed PORV Block valve regardless of Tech Spec implications to ensure adequate Bleed path.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) TS/B 3.4.11 Attached w/ Revision # See FRH-0.1 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given a procedural Step, NOTE, or CAUTION, DISCUSS the reason or basis for the Step, NOTE, or CAUTION in FRH-0.1 in accordance with FRH-0.1, Loss of Heat Sink. (ERG.FH1.OB04)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2/5 Page 51 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 52 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 53 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.4.11 Revision: 156 Page 54 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.4.11 Revision: 80 Page 55 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.4.11 Revision: 80 Page 56 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.4.11 Revision: 80 Page 57 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1 Revision: 9 Page 58 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRH-0.1 Revision: 9 Page 59 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 1 Group 2 K/A 000032.AA2.09 Level of Difficulty: 3 Importance Rating 2.9 Loss of Source Range Nuclear Instrumentation: Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Effect of improper HV setting Question # 90 Given the following conditions:

Reactor Startup in progress on Unit 1 Control Rods at 150 steps on Bank A SR counts on channels N-31 and N-32 differ by approximately 60 cpm Core Performance determined High Voltage adjustment is required on SR channel N-31 While adjusting SR channel N-31, 1-ALB-6D, Window 1.1 - SR HI VOLT FAIL alarms Reactor Startup is suspended in accordance with TS 3.3.1, RPS Instrumentation The SR HI VOLT FAIL alarm indicates SR Channel N-31 counts will be __(1)__ than actual counts.

If N-31 is NOT restored to OPERABLE within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , in accordance with TS 3.3.1, __(2)__

must be fully inserted.

A. (1) lower (2) Control Bank rods ONLY B. (1) lower (2) Control and Shutdown Bank rods C. (1) higher (2) Control Bank rods ONLY D. (1) higher (2) Control and Shutdown Bank rods Answer: B Page 60 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of actions to be taken in response to failed SR high voltage.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1).

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since actions taken during startup, if the startup is aborted, are to insert control bank rods to CBO and shutdown rods do not have a CBO position.

B. Correct. First part is correct, the improperly set SRHV power supply (110 volts below normal cause the alarm) causes less interactions between the core and the BF3 detector, causing counts to lower. Second part is correct. Per TS 3.3.1, if the inoperable SR is not returned to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , all rods, both control bank and shutdown bank rods, must be fully inserted.

C. Incorrect. First part is incorrect, but plausible if thought SRHV supplied compensating voltage, as is done in the IR channels, which would then cause counts to increase upon the loss. Second part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) Excore Nuclear Instrument Study Guide Attached w/ Revision # See ABN-701 Comments / Reference TS 3.3.1 Proposed references to be provided during examination:

Learning Objective: Given Excore Instrumentation system operability status or parameter indications, various plant conditions, and a copy of the Technical Specifications or Technical Requirements Manual, ASSESS any LCO entries, applicable conditions, and required actions (including Completion Time) in accordance with the associated regulatory requirements and their bases. (SYS.EC1.OB07)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2 Page 61 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 62 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Excore Nuclear Instrumentation Study Guide Revision: 5-1-2011 Page 63 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-701 Revision: 12 Page 64 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.3.1 Revision: 156 Page 65 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.3.1 Revision: 150 Page 66 of 66 CPNPP 2021-08 NRC Written Exam Worksheet 81-90 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 1 Group 2 K/A 000036.G.2.4.49 Level of Difficulty: 2 Importance Rating 4.4 Fuel-Handling Incidents: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Question # 91 Given the following conditions:

Unit 2 in MODE 6 reloading core Control Room notified an irradiated fuel assembly has been dropped into the core ABN-908, Fuel Handling Accident, in progress Per ABN-908, ...

the Fuel Handling Supervisor should ensure transfer cart is in the __(1)__ Building with Fuel Transfer Tube gate valve closed.

Containment Purge may have to be stopped to enable __(2)__.

A. (1) Fuel (2) closing the Fuel Transfer Tube gate valve B. (1) Fuel (2) installation of the equipment hatch C. (1) Containment (2) closing the Fuel Transfer Tube gate valve D. (1) Containment (2) installation of the equipment hatch Answer: B Page 1 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring the ability to take action to control the event in accordance with ABN-908.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of tasks performed by the Fuel Handling Supervisor which is an SRO position. It also requires knowledge of the content of the procedure and not just the overall mitigation strategy. Also due to 10 CFR 55.43(b)(7) Analysis requiring refueling floor SRO responsibilities.

Explanation:

A. Incorrect. First part is correct (see B). Second part is incorrect, but plausible since it may be thought that the DP between the Containment and Fuel buildings would prevent closing the fuel transfer tube gate valve.

B. Correct. First part is correct. Per ABN-908, Step 2.3.8, the Fuel Handling Supervisor has the specific responsibility to ensure the cart is in the Fuel Buildig. Second part is correct. A note in ABN-908 states it may be necessary to secure Containment Purge to enable installation of the equipment hatch.

C. Incorrect. First part is incorrect, but plausible since it may be thought that the transfer car should be left in Containment in preparation for putting the damaged assembly in the transfer car.

Second part is part is incorrect, but plausible (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is correct (see B).

Technical Reference(s) ABN-908 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given that a Fuel Handling accident is in progress, SUMMARIZE the expected control room response in accordance with ABN-908, Fuel Handling Accident.

(OPD1.G16.OB03)

Question Source: Bank # 75869 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC24 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5/7 Page 2 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 3 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 75869 Revision:

Page 4 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 75869 Revision:

Page 5 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ABN-908 Revision: 5 Page 6 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A WE14.EA2.01 Level of Difficulty: 3 Importance Rating 3.8 High Containment Pressure: Ability to determine and interpret the following as they apply to the High Containment Pressure: Facility conditions and selection of appropriate procedures during abnormal and emergency operations Question # 92 Given the following conditions:

Unit 1 LBLOCA EOS-1.3A, Transfer to Cold Leg Recirculation, entered at RWST LO-LO Level Subsequently:

An ECCS flowpath from the containment sump to the RCS could NOT be established Efforts to add makeup to the RWST in progress RWST level 18% lowering slowly Containment pressure 40 psig slowly rising CSP suction aligned to the RWST (1) The US should operate CSPs per __(1)__.

(2) How many Containment Spray Pumps should be run for the stated conditions above?

A. (1) FRZ-0.1A, Response to High Containment Pressure (2) Operate TWO CSPs until containment pressure less than 18 psig or RWST level is 9%

B. (1) ECA-1.1A, Loss of Emergency Coolant Recirculation (2) Operate TWO CSPs until containment pressure less than 18 psig or RWST level is 9%

C. (1) FRZ-0.1A, Response to High Containment Pressure (2) Operate NO CSPs to conserve RWST level D. (1) ECA-1.1A, Loss of Emergency Coolant Recirculation (2) Operate NO CSPs to conserve RWST level Answer: B Page 7 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of procedures to transition to, as well as implementation of the detailed steps of the procedure.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed. Also requires knowledge of diagnostic steps and decision points in the emergency operating procedures (EOPs) that involve transitions to event-specific sub-procedures or emergency contingency procedures.

Explanation:

A. Incorrect. First part is incorrect, but plausible since an orange path on Containment does exist and FRZ-0.1A implementation may be required (if not already implemented). Second part is correct (see B).

B. Correct. First part is correct, ECA-1.1A would be the procedure governing CSP operation regardless of procedure currently being implemented (FRZ-0.1A or ECA-1.1A). If examinee thought FRZ-0.1A was required due to the orange path, then step 4.d of FRZ-0.1A states to operate CSPs per ECA-1.1A. Second part is correct, with Containment pressure above 18 psig but less than 50 psig, two CSPs would be run until Containment pressure lowered to less than 18 psig or RWST level lowered to 9% (Empty)

C. Incorrect. First part is incorrect, but plausible (see A). Second part is incorrect, but plausible since ECA-1.1 would require no CSPs be run if RWST level were below 9% or if pressure were below 18 psig.

D. Incorrect. First part is correct (see B). Second part is incorrect, but plausible (see C)

Technical Reference(s) ECA-1.1 Attached w/ Revision # See FRZ-0.1 Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for the procedure steps, NOTEs and CAUTIONs contained in FRZ-0.1A/B. (ERG.FZ1.OB04)

Question Source: Bank #

Modified Bank # 52583 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 8 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 9 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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Bank 52583 Revision:

Page 10 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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Bank 52583 Revision:

Page 11 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ECA-1.1 Revision: 9 Page 12 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

FRZ-0.1 Revision: 9 Page 13 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 3 Tier 1 Group 2 K/A WE07.G.2.4.20 Level of Difficulty: 3 Importance Rating 4.3 Saturated Core Cooling: Knowledge of the operational implications of EOP warnings, cautions, and notes.

Question # 93 Given the following conditions:

SGTR occurred on Unit 1 Due to equipment failures, ECA-3.2A, SGTR with a Loss of Reactor Coolant-Saturated Recovery Desired, being performed The STA informs you the CSFSTs all GREEN with the exception of the following:

o CORE COOLING CSFST YELLOW based on Loss of Subcooling o INVENTORY CSFST YELLOW based on Reactor Vessel Level Which of the following describes the implementation of procedures for this event?

A. Address both CSFST YELLOW paths, as desired based on operator judgement.

B. Do NOT address either CSFST YELLOW path as implementation is NOT allowed in the ECA procedures.

C. Address CORE COOLING actions, as desired based on operator judgement, and do NOT perform the actions for INVENTORY due to conflict with ECA-3.2A actions.

D. Address INVENTORY actions, as desired based on operator judgement, and do NOT perform the actions for CORE COOLING due to conflict with ECA-3.2A actions.

Answer: D Page 14 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of cautions stated in procedure ECA-3.2.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed. Also requires knowledge of diagnostic steps and decision points in the emergency operating procedures (EOPs) that involve transitions to event-specific sub-procedures or emergency contingency procedures.

Explanation:

A. Incorrect. Plausible because normally YELLOW path procedures are addressed at the discretion of the US, but CORE COOLING actions conflict with ECA-3.2 actions and should not be performed.

B. Incorrect. Plausible because CORE COOLING actions conflict with ECA-3.2 actions and should not be performed, but INVENTORY actions could be taken.

C. Incorrect. Plausible since actions from one of these procedures is not to be performed due to conflicts with ECA-3.2 actions, but the conflicting procedure addresses CORE COOLING.

D. Correct. Per the guidance contained in FRC-0.3A, Response to Saturated Core Cooling. FRC-0.3A directs a reestablishment of RCS subcooling via Safety Injection Flow. This is inconsistent with the actions of ECA-3.2A which reduce RCS subcooling via ECCS flow reduction in order to minimize primary to secondary leakage during a SGTR.

Technical Reference(s) FRC-0.3 Attached w/ Revision # See OCA-407 Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE the bases for operator actions, notes and cautions from ECA-3.2.

(ERG.C31.OB12)

Question Source: Bank # 18539 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 15 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 16 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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ODA-407 Revision: 17 Page 17 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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FRC-0.3 Revision: 9 Page 18 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.1.35 Level of Difficulty: 3 Importance Rating 3.9 Knowledge of the fuel-handling responsibilities of SROs.

Question # 94 Which of the following is a direct responsibility of the Fuel Handling Supervisor during CORE ALTERATIONS in accordance with RFO-101, Refueling Organization.

A. Performing fuel assembly and insert component inspections.

B. Providing approved Fuel Shuffle Sequence Sheets to the Refueling Crew.

C. Ensuring new fuel assemblies to be loaded into the reactor have been properly processed and inspected and are available for loading.

D. Ensuring direct communications are maintained between the refueling area in Containment, the fuel building, and the Control Room.

Answer: D Page 19 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of direct responsibilities of the refueling SRO.

SRO Only: SRO Only due to 10 CFR 55.43(b)(7) Analysis requiring refueling floor SRO responsibilities.

Explanation:

A. Incorrect. Plausible because Performing fuel assembly and insert component inspections is a responsibility contained in RFO-101 but it is for the Core Performance Manager not the Fuel Handling Supervisor.

B. Incorrect. Plausible because providing approved Fuel Shuffle Sequence Sheets to the Refueling Crew is a responsibility contained in RFO-101 but it is for the Core Performance Manager not the Fuel Handling Supervisor.

C. Incorrect. Plausible because ensuring new fuel assemblies to be loaded into the reactor have been properly processed and inspected and are available for loading is a responsibility contained in RFO-101 but it is for the Core Performance Manager not the Fuel Handling Supervisor.

D. Correct. Maintaining direct communication between the refueling area in Containment, the fuel building, and the Control Room during core alterations is a direct responsibility of the Fuel Handling Supervisor per RFO-101.

Technical Reference(s) RFO-101 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given RFO-101, Refueling Organization, DISCUSS the Precautions, Limitations and major procedural actions IAW RFO-101. (OPD1.G16.OB01)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 7 Page 20 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

RFO-101 Revision: 9 Page 21 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.1.36 Level of Difficulty: 3 Importance Rating 4.1 Knowledge of procedures and limitations involved in core alterations.

Question # 95 Given the following conditions:

Unit 1 performing an off-load of the core during refueling outage ODA-308-3.9.0-S01, Refueling Special Condition Surveillances, Section 2, Surveillances Required for Core Alterations/Movement of Irradiated Fuel being implemented with the following information:

o One SR detector OPERABLE and the other inoperable o One Gamma-Metrics SR monitor OPERABLE and the other inoperable (1) Which of the following describes the operability status of the Nuclear Instrumentation?

(2) Refueling cavity water level OPERABLITY requires at least 23 feet above the __(2)__.

A. (1) Nuclear Instrumentation OPERABILITY is met (2) Reactor Vessel flange B. (1) Nuclear Instrumentation OPERABILITY is met (2) top of the irradiated fuel assemblies C. (1) Nuclear Instrumentation OPERABILITY is NOT met (2) Reactor Vessel flange D. (1) Nuclear Instrumentation OPERABILITY is NOT met (2) top of the irradiated fuel assemblies Answer: A Page 22 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring knowledge of TS bases that is required to analyze TS-required actions and terminology and 10 CFR 55.43(b)(6) Analysis requiring knowledge of TS bases for reactivity controls.

Explanation:

A. Correct. First part is correct (see B). Second part is correct. Cavity level must be 23 feet above the vessel flange.

B. Incorrect. First part is correct, any 2 of the 4 NIs, consisting of the SR NIs and the Gamma Metrics, are required to be operable. Second part is incorrect, but plausible as level would be required to be 23 feet above the fuel if the requirement was in the fuel building.

C. Incorrect. First part is incorrect, but plausible since until recently the operability of the nuclear instrumentation for refueling was based on either the SR NIs or the Gamma Metrics being operable in pairs, such that both of one set were required. Second part is correct (see A).

D. Incorrect. First part is incorrect, but plausible (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) TS/B 3.9.3 Attached w/ Revision # See TS/B 3.9.7 Comments / Reference Proposed references to be provided during examination:

Learning Objective: Given access to Technical Specifications and a refueling activity, APPLY the appropriate specification. (OPD1.G16.OB04)

Question Source: Bank #

Modified Bank # 52607 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2/6 Page 23 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 24 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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Bank 52607 Revision:

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Bank 52607 Revision:

Page 26 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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TS 3.9.3 Revision: 150 Page 27 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.9.3 Revision: 78 Page 28 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TS 3.9.7 Revision: 156 Page 29 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

TSB 3.9.7 Revision: 78 Page 30 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.2.11 Level of Difficulty: 2 Importance Rating 3.3 Knowledge of the process for controlling temporary design changes.

Question # 96 In accordance with STA-602, Temporary Modifications, (1) Who is responsible for performing walkdowns of active Temporary Modifications, and (2) How often is the walkdown required to be performed?

A. (1) Work Control Operations Supervisor (2) Monthly B. (1) Work Control Operations Supervisor (2) Quarterly C. (1) System Engineer (2) Monthly D. (1) System Engineer (2) Quarterly Answer: D Page 31 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of the procedures associated with Temporary Modifications.

SRO Only: SRO Only due to 10 CFR 55.43(b)(3) requiring knowledge of administrative processes for temporary modifications.

Explanation:

A. Incorrect. First part is incorrect, but plausible since this individual maintains and files copies of Temporary Modifications including clearances. Second part is incorrect, but plausible as monthly is a reasonable period of time compared to quarterly.

B. Incorrect. First part is incorrect, but plausible (see A). Second part is correct (see D).

C. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see A).

D. Correct. First part is correct, per STA-602, 5.7.2, the System Engineer is responsible for performance of a quarterly walkdown of TMs associated with their system to ensure proper installation. Second part is correct, the walkdown is required quarterly.

Technical Reference(s) STA-602 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DESCRIBE the administrative requirements for operating plant equipment; performing routine watchstanding evolutions and maintaining system status and plant configuration control in accordance with ODA-106, STI-604.03, OWI-207, ODA-102, ODA-410, ODA-407, OWI-107, STA-694, STA-601 and OWI-409.

(ADM.XA1.OB09)

Question Source: Bank #

Modified Bank # 35501 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Page 32 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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Bank 35501 Revision:

Page 33 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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Bank 35501 Revision:

Page 34 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

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STA-602 Revision: 20 Page 35 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 2 Tier 3 Group K/A 2.2.12 Level of Difficulty: 3 Importance Rating 4.1 Knowledge of surveillance procedures.

Question # 97 While operating at 100% power, it is discovered a 31 day Surveillance Requirement on a piece of Tech Spec equipment was overlooked and has NOT been performed for over 6 weeks.

What is the proper course of action?

A. Delay calling the equipment INOPERABLE for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow performance of the Surveillance.

B. Declare the equipment INOPERABLE at the time of discovery and delay complying with the LCO ACTION(s) for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. Declare the equipment INOPERABLE and enter LCO 3.0.3.

D. Delay calling the equipment INOPERABLE for up to 31 days to allow performance of the Surveillance.

Answer: D Page 36 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of surveillance procedure administrative requirements.

SRO Only: SRO Only due to 10 CFR 55.43(b)(2) Analysis requiring knowledge of generic LCO requirements (LCO 3.0.1 through 3.0.7 and SR 4.0.1 through 4.0.4).

Explanation:

A. Incorrect. Plausible since 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months would be the time frame if the surveillance period were less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but the greater interval is permitted.

B. Incorrect. Plausible since the surveillance is used to determine operability, but the LCO does not need to be implemented until the extended time granted by SR 3.0.3 expires.

C. Incorrect. Plausible since the surveillance is used to determine operability, but SR 3.0.3 permits delaying the surveillance.

D. Correct. If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is GREATER. This delay period is permitted to allow performance of the Surveillance.

Technical Reference(s) TS SR 3.0.3 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: DELINEATE the role of surveillances into Operability in accordance with the Technical Specifications. (ADM.XA5.OB04)

Question Source: Bank # 19387 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Page 37 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(2) Analysis Revision:

Page 38 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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Reference:

TS SR 3.0.3 Revision: 150 Page 39 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.3.13 Level of Difficulty: 2 Importance Rating 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Question # 98 A clearance is to be implemented with the following conditions:

Contact radiation on a piece of equipment is 5 R/hr Radiation level is 500 mrem/hr at 1 foot from the piece of equipment General area radiation for the room is 125 mrem/hr An operator must close and place a clearance tag on a valve which is located 8 feet away from the equipment It will take the operator 3 minutes to close the valve and place the clearance tag The proper classification for the room is __(1)__.

A waiver of the independent verification of the tag placement is __(2)__ by the Shift Manager.

A. (1) High Radiation Area (2) NOT allowed B. (1) Radiation Area (2) NOT allowed C. (1) Radiation Area (2) allowed D. (1) High Radiation Area (2) allowed Answer: D Page 40 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of radiological safe practices to minimize total exposure to personnel and authority of Shift Manager regarding waivers due to radiation levels.

SRO Only: SRO Only due to 10 CFR 55.43(b)(4) Analysis requiring analysis and interpretation of radiation and activity readings as they pertain to the selection of administrative, normal, abnormal, and emergency procedures.

Explanation:

A. Incorrect. First part is correct (see D). Second part is incorrect, but plausible (see B).

B. Incorrect. First part is incorrect, but plausible since a radiation area is defined as an area where an individual can receive a dose equivalent in excess of 5 mrem in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 30 cm (12 inches) from the radiation source, but being in excess of 100 mrem in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months upgrades the classification to a High Radiation Area. Second part is incorrect, but plausible since the total dose that the operator will receive is below threshold of 10 mrem to waive (dose received will be approximately 2.6 mrem total), however dose rate is sufficient to allow waiver.

C. Incorrect. First part is incorrect, but plausible (see B). Second part is correct (see D).

D. Correct. First part is correct. A high radiation area is defined as an area where an individual can receive a dose equivalent in excess of 100 mrem in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 30 cm (12 inches) from the radiation source. Second part is correct. The dose rate of >100 mrem/hr allows this verification be waived. .halving the distance from a point source causes the intensity to increase by a factor of four. , although total exposure for verification is 8 mrem (160 mrem/hr for 3 minutes, 1/20 th of hour), the dose rate of >100 mrem/hr allows this verification be waived.

Technical Reference(s) Radiation Protection Practices LP Attached w/ Revision # See STA-694 Comments / Reference STA-650 Proposed references to be provided during examination:

Learning Objective: DESCRIBE the administrative requirements for operating plant equipment; performing routine watchstanding evolutions and maintaining system status and plant configuration control in accordance with ODA-106, STI-604.03, OWI-207, ODA-102, ODA-410, ODA-407, OWI-107, STA-694, STA-601 and OWI-409.

(ADM.XA1.OB09)

Question Source: Bank #

Modified Bank # 33141 (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 4 Page 41 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Page 42 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 33141 Revision:

Page 43 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Page 44 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Radiation Protection Practices LP Revision: 00-0001 Page 45 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-650 Revision: 9 Page 46 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

STA-694 Revision: 8 Page 47 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.4.22 Level of Difficulty: 3 Importance Rating 4.4 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

Question # 99 Given the following conditions:

Unit 1 responding to a LBLOCA A CORE COOLING status tree ORANGE path causes a transition to FRC-0.2A, Response to Degraded Core Cooling During performance of FRC-0.2A, the CORE COOLING status tree changes from ORANGE to YELLOW An ORANGE path exists on the CONTAINMENT status tree FRZ-0.1A, Response to High Containment Pressure, is the procedure referenced by the CONTAINMENT status tree Which of the following is the required action?

A. Complete FRC-0.2A and then go to FRZ-0.1A since CONTAINMENT is a lower priority path than CORE COOLING.

B. Go to FRZ-0.1A since an ORANGE path has a higher priority than a YELLOW path.

Completion of FRC-0.2A is NOT needed.

C. Complete FRC-0.2A as entry into FRZ-0.1 is NOT needed since it would have been addressed by the performance of steps in EOP-1.0A.

D. Go to FRZ-0.1A since an ORANGE path has a higher priority than a YELLOW path.

Return to complete FRC-0.2A after FRZ-0.1A is addressed.

Answer: A Page 48 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring the ability to prioritize safety functions during an event.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

Explanation:

A. Correct. Upon entry to a RED or ORANGE path FRG, the procedure is performed to completion unless a higher RED or ORANGE path procedure is encountered, even if the path clears or becomes YELLOW before completion. Since CORE COOLING is a higher priority than CONTAINMENT, FRC-0.2 is completed before FRZ-0.1 is addressed.

B. Incorrect. Plausible since if these conditions had been identified prior to entering FRC-0.2, then FRZ-0.1 would be the higher priority, but incorrect since FRC-0.2 is to be completed even though it has turned YELLOW.

C. Incorrect. Plausible since entry into FRZ-0.1 would not be required if the steps were performed in EOP-1.0 and an ORANGE path did not exist. The crew would enter FRZ-0.1 and immediately transition out at Step 1 in this case.

D. Incorrect. Plausible since if these conditions had been identified prior to entering FRC-0.2, then FRZ-0.1 would be the higher priority, but incorrect since FRC-0.2 is to be completed even though it has turned YELLOW.

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: STATE when an operator is allowed/required to exit an FRG and the requirements for completion of an FRG exited before it is complete in accordance with ODA-407, Operations Department Procedure Use and Adherence. (ERG.XD2.OB18)

Question Source: Bank # 23165 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam LC26 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Page 49 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 50 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23165 Revision:

Page 51 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

Bank 23165 Revision:

Page 52 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 53 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

ODA-407 Revision: 17 Page 54 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Rev. Date: Rev. 1 Tier 3 Group K/A 2.4.44 Level of Difficulty: 2 Importance Rating 4.4 Knowledge of emergency plan protective action recommendations.

Question # 100 Per EPP-304, Protective Action Recommendations, initial PARs are issued at the __(1)__

Emergency Classification and are formulated in the Control Room by the Emergency Coordinator and the __(2)__.

A. (1) Site Area (2) STA B. (1) Site Area (2) US C. (1) General (2) STA D. (1) General (2) US Answer: C Page 55 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 K/A Match: K/A match due to requiring knowledge of when emergency plan protective action recommendations are implemented and the positions that formulate the PAR.

SRO Only: SRO Only due to 10 CFR 55.43(b)(5) Analysis requiring knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

Explanation:

A. Incorrect. First part is incorrect, but plausible (see B). Second part is correct (see C).

B. Incorrect. First part is incorrect, but plausible because a Site Area Emergency is the next lower classification below the General Emergency when PARs are required and it is plausible that PARs would be issued at this EAL Classification. Second part is incorrect, but plausible if it is assumed that the US on the affected unit would function as the second SRO concurrence on PARs as is the case for other activities such as ERG deviations, etc.

C. Correct. First part is correct. In accordance with EPP-304, PARs are issued upon declaration of a GE. Second part is correct. The STA aids the EC in developing PARs from the Control Room.

D. Incorrect. First part is correct (see C). Second part is incorrect, but plausible (see B).

Technical Reference(s) EPP-304 Attached w/ Revision # See Comments / Reference Proposed references to be provided during examination:

Learning Objective: IDENTIFY the ERO position holders responsible for PARs in each facility, in accordance with EPP-304. (PAR.OW5.OB01)

Question Source: Bank # 62572 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Page 56 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

10 CFR 55.43(b)(5) Analysis Revision:

Page 57 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EPP-304 Revision: 22 Page 58 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

ES-401 CPNPP 2021-08 NRC Written Exam Worksheet Form ES-401-5 Comments /

Reference:

EPP-304 Revision: 22 Page 59 of 59 CPNPP 2021-08 NRC Written Exam Worksheet 91-100 Rev. 5

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