ML24043A073

2024-01 Post Examination Comments

ML24043A073
Person / Time
Site:	Grand Gulf
Issue date:	01/29/2024
From:	Hargrove G, Kryska J Entergy Operations
To:	John Kirkland NRC Region 4
References
50-416/24-01, GNRO 2024-00007 50-416/OL-24
Download: ML24043A073 (1)

Text

Entergy Operations Inc.

7003 Ba ld Hill Road

• ~ Ent ergx Po rt Gibs on. MS 391 50

February 8, 2024

John Kirkland USNRC Chief Examiner U.S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd Arlington, TX 76011-4511

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

SUBJECT : NRC POST EXAMINATION SUBMITTIAL

GNRO 2024-00007

Dear Mr. Kirkland,

Post examination materials are being submitted for the NRC Initial License Written Examination administered on January 29, 2024, at Grand Gulf Nuclear Station. The examination was administered to 1 RO, 2 Instant SROs, and 2 Upgrade SRO applicants.

As Grand Gulf NRC Exam Management Sponsor and Facility Reviewer, we have confirmed the quality of the exam grading and concur with the individual and collective examination results.

There are no proposed changes to the examination.

This submittal includes all req uired documentation for the written examina tion in accordance with NURE G 1021 Revision 12, Section 4.4, "Grading and Doc um enting Written Examinations". The documents of the submittal are contained in an Entergy sponsored ShareFile. You have full admin rights to the ShareFile. The organization and content of the ShareFile folder is attached.

In accordance with NUREG 1021, Revision 12, Section ES-1.3, "Examination Security," please ensure that these materials a re withheld from public disclosure until after the examinations are complete. Additionally, Grand Gulf requests tha t the written examination outlines be w ithheld from public disclosure for two years after administration of the exams to allow reuse o f the examination mater ials in future initial licensing classes.

For questions concerning examination materials, please contact Rich Bolduc (601) 996-7361.

Sine~ / ()1

~ ska ~ Gabriel Harg ave Manager, Training & Development Facility Representative Grand Gulf Nuclear Station Grand Gulf Nuclear Station Entergy Operations Inc.

7003 Bald Hill Road

• ~ Entergy; Po rt Gibson MS 39150

February 8, 2024 Page 2

ShareFile: 2024 GG NRG EXAM Folder: POST EXAM SUBMITTAL

Folder: Graded Written Exam Documentation

RO and SRO Graded Exam Records

Folder: Documents for NRG Exam Grading

• Applicant Un-graded Answer Sheets

• Tabular Grading Answer Keys

• Machine Grading Answer Keys

Folder: Administered Written Exam

• GG 2024 NRG Exam Master Answer Key

• GG 2024 NRG Exam Applicant Copy

• 2024 NRG Written Exam SRO Provided References

• Exam Administration Log of Applicant Questions During Exam

Folder: Written Exam Analysis

• Analysis from Applicant Input for High Missed Questions

• RO and SRO Exam Analysis 1-75

• SRO Exam Analysis 1-100

• SRO Exam Analysis76-100

Folder: Additional Documents

• Signed-Off Examination Security Agreement Forms (Form 1.3-1)

• Examination Seating Chart

• Post Exam Submittal Cover Letter

• NRG Exam Related Condition Reports Analysis from Applicant Input for High Miss Questions

Q 16: (60% RO+2 SROs)

K/A 700000 AA2.06

Applicants selected the Over-hearting of the Main Generator. We have recently down powered several times due to stator bar temperatures.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant is operating at 100% power with the following:

• Grid instabilities are occurring.

• 05 02-I-8, Loss of BOP AC Power / Grid Instability ONEP, is entered.

• Grid frequency is 58 Hz and lowering slowly.

Which one of the following identifies:

• a concern with this frequency

and

• the need for a Reactor scram,

in accordance with 05-1-02-I-8?

Concern Reactor Scram

A. Trip of EPA breakers Required

B. Trip of EPA breakers NOT required

C. Over-heating of Main Generator Required

D. Over-heating of Main Generator NOT required

Answer: A

Q 16.A (2, 40.0%} B (0, 0.0%) C ( 2, 4 0.0 °/o) D ( 1., 2 0.0%)

2, 4 0.0% 60.0°/o

Page 1 of 9 Analysis from Applicant Input for High Miss Questions

Q 55: (60% 1 RO+2 SROs)

K/A 290001 A3.01

2 Applicants selected D because they knew that valve received a closed signal, 1 Applicant guessed. The applicants did not think they would have to know the normal positions for the valves at 100% reactor power.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant is operating at 100% power with the following:

• A loss of Feedwater occurs.

• The Reactor scrams.

• HPCS and RCIC automatically initiate.

• Reactor water level reaches a low of -45.

Which one of the following identifies an isolation valve whose position indication has changed status (from OPEN to CLOSED) on the Isolation Valve Status Board?

A. B21-F028A, MSL A CTMT OUTBOARD ISOL

B. P11-F 062, CST WATER SUPPLY HEADER TO AUX BLDG

C. B21-F019, INBOARD MSL DRAINS OUTBOARD DRAIN VALVE

D. P11-F047, REFUEL WATER TRANSFER PUMP SUCTION FROM RADWASTE

Answer: B

Q 55 A (0, 0.0%) B (2, 40.0%) C (1, 20.0%) D (2, 40.0%)

2, 40.0% 6 0. 0 °/o

Page 2 of 9 Analysis from Applicant Input for High Miss Questions

Q 65: (60% 1 RO+2 SROs)

K/A 2.1.4

Applicants could not remember watchstanding proficiency requirements.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

Which one of the following is the minimum number of twelve (12) hour shifts a licensed operator is required to complete in a calendar quarter to maintain an active license, in accordance with 02-S 39, Maintaining Watchstanding Proficiency?

A. 3

B. 5

C. 7

D. 9

Answer: B

Q 65.A (2, 40.0%) B (2, 40.0%} C (1, 20.0%) D (0, 0.0%)

2, 40.0% 60.0°/o

Page 3 of 9 Analysis from Applicant Input for High Miss Questions

Q78: (50% 2 SROs)

K/A 295016 AA2.03

Applicants remember the 20- minute limit listed in the PTLR and thought that rate was used at the Remote Shutdown Panel

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant is operating at 100% power with the following:

• A fire in the Control room requires an evacuation.

• 05 02-II-1, Shutdown from the Remote Shutdown Panel ONEP, is being performed.

• Control has been established at the Remote Shutdown Panel.

• Reactor pressure is 1000 psig and slowly rising.

Which one of the following describes the required control of Reactor pressure/temperature, in accordance with 05 02-II-1?

A. Stabilize Reactor pressure below 1060 psig, but do NOT commence a cooldown.

B. Commence a cooldown. The cooldown rate is limited to no more than 20°F/hr.

C. Commence a cooldown. The cooldown rate is limited to no more than 90°F/hr.

D. Rapidly depressurize the Reactor irrespective of cooldown rate.

Answer: C

Q 78.A (0, 0.0%) B (1, 25.0%) C (2, 50.0%) D ( 1, 25.0%)

2, 50.0% so. b%

Page 4 of 9 Analysis from Applicant Input for High Miss Questions

Q80: (50% 2 SROs)

K/A 295026 2.4.23

Applicants were confused because they thought the legs would be prioritized and said that means the specified order.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant has experienced a spurious opening of an SRV with the following:

• The Reactor has been manually scrammed.

• The SRV has been closed.

• EP-3, Primary Containment Control, has been entered due to high Suppression Pool temperature and level, only.

Which one of the following describes how to implement EP-3?

A. All legs are entered. There IS a specified order for which leg to execute first.

B. All legs are entered. There IS NOT a specified order for which leg to execute first.

C. Only the SP/T and SP/L legs are entered. There IS a specified order for which leg to execute first.

D. Only the SP/T and SP/L legs are entered. There IS NOT a specified order for which leg to execute first.

Answer: B

Q 80.A {O, 0.0%) lJ (2, 50.0%) C (1, 25.0%) D ( 1, 25.0%)

2, 50.0% 5 0. 0/o

Page 5 of 9 Analysis from Applicant Input for High Miss Questions Q81: (50% 2 SROs)

K/A 295006 AA2.05

Applicants thought that because we dont have a leak or challenge to feedwater injection, we are not allowed to lower pressure.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant has been scrammed with the following:

• APRMs indicate downscale.

• IRMs are fully inserted and indicate downscale on Range 1.

• SRMs are fully inserted and trending down with a negative period.

• A cluster of ten (10) adjacent control rods remain withdrawn at position 04.

• All other control rods are fully inserted.

• EP-2, RPV Control, has been entered due to low Reactor water level.

• NO steps have yet been performed in the Emergency Procedures (EPs).

• Reactor pressure is 940 psig and steady.

Which one of the following describes the required procedure execution and control of Reactor pressure, in accordance with the EPs?

Required Procedure Execution Control of Reactor Pressure

A. Remain in EP-2 Depressurization is allowed

B. Remain in EP-2 Depressurization is NOT allowed

C. Exit EP-2 and enter EP-2A, ATWS Depressurization is allowed RPV Control

D. Exit EP-2 and enter EP-2A, ATWS Depressurization is NOT allowed RPV Control

Answer: C

Q 8 1.A (0, 0.0%), B (0, 0.0%) C (2, 501.0 9/oJ D ( 2, 5 0.0%)

2, 5 0.0% 5 0.p%

Page 6 of 9 Analysis from Applicant Input for High Miss Questions

Q96: (75% 3 SROs)

K/A 2.4.40

Applicants did not remember what item could be delegated. They thought INFORM option C was delegated.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant has experienced an accident with the following:

• Conditions warrant emergency classification.

• You are assuming the role of the Emergency Director.

• The Emergency Response Organization has NOT yet been activated.

Which one of the following is a responsibility that you ARE allowed to delegate, in accordance with EN-EP-609, Emergency Operations Facility (EOF) Operation?

A. Ordering local area/building evacuation

B. Classifying and declaring the emergency

C. Emergency notifications of the accident to off-site agencies

D. Making Protective Action Recommendations (PARs) to off-site agencies

Answer: A

Q 96 A (1., 25.. 0%) B (0, 0.0%) C (3, 75.0%) D (0, 0.0%)

l, 2S.0% 75.0%

Page 7 of 9 Analysis from Applicant Input for High Miss Questions

Q97: (75% 3 SRO)

K/A 2.2.37

Applicants selected the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, they did not consider up to the limit of the specified frequency

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant is operating at 100% power with the following:

• It is discovered that a surveillance has NOT been completed on time for a Technical Specification required system.

• The surveillance frequency is quarterly (92 days).

• The surveillance was last performed 120 days ago.

• A risk evaluation has been performed and the associated impact is being managed.

• It is expected that the system will pass the surveillance when it is performed.

Which one of the following describes the requirement for this missed surveillance, in accordance with Technical Specifications?

A. The associated LCO must be declared NOT met at this time

B. Complete the surveillance within a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the time of discovery or then the associated LCO must be declared NOT met

C. Complete the surveillance within a maximum of 23 days from the time of discovery or then the associated LCO must be declared NOT met

D. Complete the surveillance within a maximum of 92 days from the time of discovery or then the associated LCO must be declared NOT met

Answer: D

Q 97.A (0, 0.0%) 1 13 (3, 75.. 0%) C (0, 0.. 0%)

1, 25.0% 7 5.0%

Page 8 of 9 Analysis from Applicant Input for High Miss Questions

Q99: (50% 2SRO)

K/A 2.1.15

Applicants remembered that Shift Managers post/discuss these in the control room but did not know OPS Director approves.

Question reviewed and applicants understand the correct answer.

No changes to the question are being proposed.

The plant is operating at 100% power with the following:

• A degraded plant condition requires issuing temporary written guidance to Operations personnel, in accordance with EN -OP-112, Night and Standby Orders.

• It is desired for the guidance to remain in effect for approximately one month and until formally cancelled.

Which one of the following identifies:

• the type of order to be used

and

• who is required to approved this order,

in accordance with EN-OP-112?

Type of Order Required Approval

A. Night Order Shift Manager

B. Night Order Director, Operations

C. Standing Order Shift Manager

D. Standing Order Director, Operations

Answer: D

Q 99.A (0, 0.0%), C ( 2, 5 0.0%} D (2, 50.0%,) '

2, 5 0.0% 50. 0%

Page 9 of 9