ML24068A051

From kanterella
Jump to navigation Jump to search
8_1-CW-2023-09 Final Written Exam - Answer Key (Post-Admin Review Addendum)
ML24068A051
Person / Time
Site: Callaway 
Issue date: 03/08/2024
From: Heather Gepford
NRC/RGN-IV/DORS/OB
To:
Ameren Missouri
References
Download: ML24068A051 (1)


Text

March 8, 2024 From: Thomas Farina, Senior Operations Engineer, NRC Region IV To:

File Subj: MEMORANDUM An applicant requested an administrative review of the Callaway 2023 initial licensing exam, documented under ADAMS Accession Number ML23339A178. As a result of this administrative review performed by NRR/DRO/IOLB, RO Question #61 was deleted from the exam due to no correct answer, documented under ADAMS Accession Number ML24064A134.

Enclosed is a copy of Question #61 and the final grading key for this exam. The original exam can be found under ADAMS Accession Number ML23311A296.

T. Farina

oo C

o,w r

OOJ

-J CD ZO 0

0.0 no4 I

I fix U

J]

x D

LI x

nnn nfl uuu uu n

nnnn 0

0000 I]

UUUU

( finn n

UUU U

nn fin UU UU C\J U)

U)

CD F LI)

LI)

LI)

If)

U)

U)

I fin UUUU UU finn nnnnn 000 00000 UUU UUUUU nnnn nnnn UUUU UUUU n

nnnn U

UUUU a) a) 0 C\J U)

LI)

CD LI)

U)

CD CD CD CD CD CD CD I

n nn U

UU finn nn 000 00 UUU UU n

nnnn U

UUUU nnnn n

UUUU U

U)

CD F-a) a) o STUDENTS INSTRUCTORS USE 50.2 PENCIL osiJ_

  • EXAMPLE:

A rrB

  • MAKE DARK MARKS
  • ERASE COMPLETELY TO CHANGE
  • MAKE NO STRAY MARKS KEY MARKING INSTRUCTIONS KEY:

Must mark this box on Key sheet.

VERIFY:

Prints correct response next to incorrect answers.

If Verity is not marked, a dash will print next to incorrect answers.

RESCORE: Rescores a previously scored test.

Automatically prints correct responses.

2n23 (Last)

NAME

SUBJECT, DATE_

fAccuscan

...GUARANTEED IFirsIl (c.

PERIOD I

n0 U

-nfl u-

-nfl I<

U)

)J3.L.. )f;J SCORE nnnnnnnnnn C

C.J C in CD F-a) a)

UUUUUUUUUU nflfinnnnnnn Ce Cl D)

CD CD F-a) a)

UUUUUUUUUU nnn u)oOaLu WøU)<>

nnnnnnnnnn 0 Ci D)

CD CD F-a) a)

UUUUUUUUUU finfinfinfinfin 0 Cl C)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn Ce Cl C)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn 0.-Cl C)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn 0 i-Cl U)

CD CD F-a) a) nnnnnnnnnn 0.-Cl C)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn 0.- Cl C1)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn 0.-

C4 C)

CD CD F-a) a)

UUUUUUUUUU nnnnnnnnnn 0 Cl C)

CD CD F-a) a)

U U

U U

U UU U

U U

LLUiJ(I1thI-( nnnnnnnnnn nnnnnnnn nnnnn nnn fin UUUUUUUUUU UUUUUUUU UUUUU UUU UU fin nnnn fi nnnnnn nnnnnnnnnn n

n n

00 0000 0

000000 0000000000 0

0 0

UU UUUU U

UUUUUU UUUUUUUUUU U

U U

fi fi finfin nnn fin nn fin nnn nnnn U

LI UUUU UUU UU UU UU UUU UUUU nnnn finn nnnnnnnn finn nnnnnnnn 4<<<<<<<

UUUU UUU UUUUUUUU UUU UUUUUUUU CD CD CD F-F-

F-F-

F-F-

F-F-

F-F-

a) a)

a) a)

a) a)

a) a)

a) a)

a) a)

a) a)

C) a)

C) a)

a) a) 0 finn UUU Inn 00 UU

fi n

n U

U U

nnnnfl UUUUU n

finn 0

000 U

UUU finn n

UUU U

In fi U

U U)

CD F-a) n fin U

UU nnnn 0000 UUUU fin UU I

UUU a) 0 CU nnnn UUUU n

n 0

0 U

U I UUUU nnflnn UUUUU U)U)

CD F-nnnnn finn UUUUU UUU fin nnnn 00 0000 UU UUUU I

UUUU UU nnnnnnn UUUUUUU a) a) 0

CU U)

U)

CD CUCUCUCU RESCORE n

finn nnnnnnnnnnnn U

UUU UUUUUUUUUUUU nn finn nnnnn n

00 000 00000 0

UU UUU UUUUU U

( finn n

nnnn nnnnn UUU U

UUUU UUUUU nnnnnnnnnnnn nfl UUUUUUUUUUUU UU F-a) a) 0

CU U)

U)

CD F-a) a) 0 CU U)

CUU)U)U)U)U)U)U)U)U)U)

II 1111111111 IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII D

X C

X Markups reflect resolutions of post exam comments AND administrative review - TJF 3/8/2024 X

98

NRC Written Examination Callaway Plant Reactor Operator Examination Outline Cross-reference:

Level RO Rev 0 Tier #

2 STEAM GENERATOR SYSTEM Group #

2 K/A #

035 K3.01 Importance Rating 4.3 Knowledge of the effect that a loss or malfunction of the (SF4P SG) STEAM GENERATOR SYSTEM will have on the following systems or system parameters: RCS Question #61 Reactor power is 40% when 'A' MSIV, ABHV14, fails closed for unknown reasons.

Assume the following:

  • The reactor does NOT trip
  • 'A' RCP remains in service
  • 'A' Atmospheric Steam Dump, AB PIC-1A, is out of service (1) The RCS coolant temperature exiting the 'A' SG should stabilize at or around

____(1)____.

And (2) Per Technical Specification 3.7.2, MSIVs, MSIV Bypass Valves, and MSIV Low Point Drain Isolation Valves, MSIVs are required to be operable in

____(2)____.

A. (1) 557F (2) Mode 1, Mode 2 and 3 except when the MSIV is closed and deactivated B. (1) 557F (2) Mode 1, Mode 2 and 3 and 4 except when the MSIV is closed and deactivated C. (1) 567F (2) Mode 1, Mode 2 and 3 except when the MSIV is closed and deactivated D. (1) 567F (2) Mode 1, Mode 2 and 3 and 4 except when the MSIV is closed and deactivated Answer: C Explanation:

When the MSIV closes it removes that SG as a heat sink, and with forced loop flow still present, the RCS cross over piping (RCS at the exit of the SG) will be a function of the saturation temperature for whatever steam relief is active. Normal ASD operating parameters (lift range is Question 61 deleted from the exam following administrative review due to no correct answer to part 1.

NRC Written Examination Callaway Plant Reactor Operator 1125 psig to 1185 psig but with the 'A' ASD out of service, SG pressure will be controlled by the 1st safety valve. Per TS Table 3.7.1-2 MSSV Lift settings, the lift settings at as follows:

o 1185 psig o

1197 psig o

1210 psig o

1222 psig o

1234 psig The saturation temperature of 1185 psig (1200 psia is 567.26 or 567F). The distractor of saturation temperature for 1092 psig (1107 psia is 557F) is the normal setpoint for the condenser steam dumps. 557F is plausible if the applicant falsely remembers / confuses the setpoints and or the believes the condenser will mitigate the event.

Technical Specification 3.7.2 states: " APPLICABILITY: For the MSIV and its associated actuator trains in each main steam line: MODE 1, MODES 2 and 3 except when the MSIV is closed and de-activated. MODE 1, MODES 2 - 4 except when the MSIV is closed and de-activated is plausible as there is energy stored in the SG in Mode 4 and it can be believed MSIV are required to be operable such that they will close to prevent loss of control of the plant, etc. during heat and cooldowns. Furthermore, there are other plant system in TS Section 3.7 that are required in Mode 4 such as CCW, adding to this distractors plausibility.

A. Incorrect - See above explanation - part 1 is wrong B. Incorrect - See above explanation - both are wrong C. Correct D. Incorrect - See above explanation - part 2 is wrong Technical Reference(s):

1. ASME Steam Tables
2. Technical Specifications 3.7.2 References to be provided to applicants during examination:
1. ASME Steam Tables Learning Objective: T61.0110, Systems, LP#20, Objective B. DESCRIBE the purpose and operation of the following Main Steam System components:
6.

Steam Generator Question Source:

Vision System ID # _______

Modified Bank # ______

New ___X____

Question History: Last NRC Exam ______N/A______

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis

__X___

LOD ____3___

10 CFR Part 55 Content:

10 CFR 55.41(b)(4)

Comments: