ML25308A249
| ML25308A249 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/27/2025 |
| From: | Shea S South Texas |
| To: | Thomas Farina NRC/RGN-IV/DORS/OB |
| References | |
| Download: ML25308A249 (1) | |
Text
1 Thomas Farina From:
SHEA, SHANNON <SWSHEA@STPEGS.COM>
Sent:
Monday, October 27, 2025 8:55 AM To:
Thomas Farina Cc:
ext_William_Markham; ext_Derrick_Johnson; Wetteland Michael; LUSSIER, DEIDRE
Subject:
[External_Sender] South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Post-Examination Material This email provides Post-Examination Materials for the NRC License Examination that was administered on September 30 through October 15, 2025 at South Texas Project (STP), in accordance with NUREG-1021, Revision 12, Operator Licensing Examination Standards for Power Reactors.
STP Nuclear Operating Company requests the NRC consider the Post-Examination material listed below as Exempt from Public Disclosure. None of the examination materials are to go to the Public Document Room (ADAMS) for at least two years.
The following Post-Examination material is being sent via External Sharepoint:
LOT 29 NRC Written Examination cover sheet with the original graded answer sheet and one clean copy of the answer sheet for each examinee.
LOT 29 NRC JPMs LOT 29 NRC Simulator Scenarios LOT 29 NRC Written Exam LOT 29 NRC Written Exam Analysis LOT 29 NRC Written Exam Applicant Comments After Exam LOT 29 NRC Written Exam Questions and Clarifications During Exam LOT 29 NRC Written Exam Seating Arrangement The completed Form 1.3-1, Examination Security Agreement, will be forwarded as soon as possible.
Respectfully, Shannon Shea STP Operations Training Manager Desk - (361) 972-7405 Cell - (712) 310-4443
Question #
Answer A
B C
D Total Missed
% Missed 94 C
95 C
96 D
1 1
20%
97 B
98 B
99 D
100 B
1 1
20%
Condition Report 25-9607 was written the adequacy of training materials for questions with over a 50% miss rate.
Question 30 6 candidates missed this question for a 67% miss rate. 1 candidate selected A, 2 candidates selected B, 3 candidates selected D. The correct answer is C.
This question required knowledge of actions in 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.
Specifically, the candidates were required to know how CCW is placed in service to the RHR Heat Exchangers, and the at-power configuration of the RHR Heat Exchanger Outlet Temperature Control Valves.
The question is technically correct as written. No changes to the examination are necessary.
STP LOT-29 NRC RO Exam Question 30
A Large Break LOCA has occurred from 100% power
0POP05-EO-ES13 TRANSFER TO COLD LEG RECIRCULATION, is in progress
The crew is verifying CCW flow to the RHR Heat Exchangers CCW is ___(1)___ placed in service to the RHR Heat Exchangers for Cold Leg Recirculation.
The RHR Heat Exchanger OUTLET Temperature Control Valves ___(2)___.
A.
(1)
MANUALLY (2) are OPEN with POWER REMOVED B.
(1)
MANUALLY (2)
AUTOMATICALLY OPENED upon the SI signal C.
(1)
AUTOMATICALLY (2) are OPEN with POWER REMOVED D.
(1)
AUTOMATICALLY (2)
AUTOMATICALLY OPENED upon the SI signal
STP LOT-29 NRC RO Exam CORRECT ANSWER:
C DISTRACTOR ANALYSIS:
A.
Incorrect: Plausible because there are manual valve operations that need to be performed during the alignment for Cold Leg Recirculation (closing RWST to SI suction header valve). It is also plausible because prior to the transfer to Containment Sump, there is no need for cooling injection water due to it being supplied from the RWST. The second part is correct. The RHR Heat Exchanger Outlet Temperature Control Valves being power-disconnected open in Mode 1.
B.
Incorrect: Plausible because there are manual valve operations that need to be performed during the alignment for Cold Leg Recirculation (closing RWST to SI suction header valve). It is also plausible because prior to the transfer to Containment Sump, there is no need for cooling injection water due to it being supplied from the RWST. The second part is plausible because there are multiple valves that automatically actuate due to an SI signal.
C.
Correct: CCW is automatically placed in service to supply the RHR Heat Exchangers for Cold Leg Recirculation upon SI actuation. The RHR Heat Exchanger Outlet Temperature Control Valves are power-disconnected open in Mode 1.
D.
Incorrect: Plausible because the first part is correct. CCW is automatically placed in service to supply the RHR Heat Exchangers for Cold Leg Recirculation upon SI actuation. The second part is plausible because there are multiple valves that automatically actuate due to an SI signal.
STP LOT-29 NRC RO Exam Question Number:
30 Tier:
2 Group:
1 K/A:
(005) (SF4P RHR) Residual Heat Removal System (005K4.11) Knowledge of (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM design features and/or interlocks that provide for the following: Lineup for low head recirculation mode (external and internal)
Importance Rating: 4.0 10 CFR Part 55:
CFR: 41.7 K/A Match:
K/A is matched because the applicant is required to have knowledge of the RHR system design features and interlocks that provide for automatic alignment during low head recirculation mode.
Technical
Reference:
0POP05-EO-ES13 TRANSFER TO COLD LEG RECIRCULATION Design Basis Document, Component Cooling Water System Design Basis Document, Safety Injection System 5N129F05013#1, P&ID, Safety Injection System 5R 5-Z-42058 2, CCW Disch from RHR HX Valves Logic Diagram Proposed references to be provided:
None Learning Objective:
LOT201.10, EMERGENCY CORE COOLING SYSTEMS
- 7. GIVEN a plant condition, PREDICT the operation of the ECCS to include automatic actuations, interlocks and/or trips.
Cognitive Level:
Higher Lower X
Question Source:
New X
Modified Bank Bank Question History:
New Question Comments:
STP LOT-29 NRC RO Exam From 5N129F05013#1, P&ID, Safety Injection System:
STP LOT-29 NRC RO Exam From 5R 5-Z-42058 2, CCW Disch from RHR HX Valves Logic Diagram:
Question 49 7 candidates missed this question for a 78% miss rate. All 7 candidates selected C. The correct answer is D.
This question required knowledge of the Main Steam Line Radiation Monitors and the Control Room Radiation Monitoring displays. The Main Steam Line Radiation Monitors are specific to each Steam Generator and their values may be observed on the RM-11 and RM-23.
The question is technically correct as written. No changes to the examination are necessary.
STP LOT-29 NRC RO Exam Question 49 The Unit is at 100% power Subsequently, A Steam Generator TUBE LEAK occurs The ___(1)___ Radiation Monitor(s) can be used to IDENTIFY the AFFECTED SG.
These Radiation Monitors can be MONITORED using ___(2)___.
A.
(1)
CARS OR Main Steam Line (2)
RM-11 ONLY B.
(1)
CARS OR Main Steam Line (2)
RM-11 OR RM-23 C.
(1)
Main Steam Line ONLY (2)
RM-11 ONLY D.
(1)
Main Steam Line ONLY (2)
RM-11 OR RM-23
STP LOT-29 NRC RO Exam CORRECT ANSWER:
D DISTRACTOR ANALYSIS:
A.
Incorrect: Plausible because the CARS radiation monitor can be used to identify that a Steam Generator Tube Leak has occurred, but it cannot be used to identify the affected SG due to its location in the steam flow path. The second part is correct.
The Main Steam Line and CARS Radiation Monitors can be monitored using RM11 or RM23.
B.
Incorrect: Plausible because the CARS radiation monitor can be used to identify that a Steam Generator Tube Leak has occurred, but it cannot be used to identify the affected SG due to its location in the steam flow path. The second part is plausible because RM11 is the normal monitoring station for the identified radiation monitors. However, backup indication is also available on RM23.
C.
Incorrect: Plausible because the first part is correct. The Main Steam Line Radiation Monitors can be used to identify the affected SG because they monitor the individual Main Steam lines. The second part is plausible because RM11 is the normal monitoring station for the identified radiation monitors. However, backup indication is also available on RM23.
D.
Correct: The Main Steam Line Radiation Monitors can be used to identify the affected SG because they monitor the individual Main Steam lines. The Main Steam Line and CARS Radiation Monitors can be monitored using RM11 or RM23.
STP LOT-29 NRC RO Exam Question Number:
49 Tier:
2 Group:
1 K/A:
(073) (SF7 PRM) Process Radiation Monitoring System (073A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM, including:
Radiation levels Importance Rating: 3.5 10 CFR Part 55:
CFR: 41.7 K/A Match:
K/A is matched because the applicant is required to have the ability to predict and monitor changing radiation levels using the Process Radiation Monitoring System.
Technical
Reference:
0POP04-RC-0004, Steam Generator Tube Leakage 0POP04-RA-0001, Radiation Monitoring System Alarm Response 0POP04-RA-0003, Loss of RM-11 Proposed references to be provided:
None Learning Objective:
LOT202.41, RADIATION MONITORING SYSTEM
- 4. IDENTIFY the following components in the PERMS as to their and Function AND typical locations:
C. RM-11, Control Room Minicomputer Assembly D. RM-23 Monitor Panel (Control Room Cabinet)
Cognitive Level:
Higher Lower X
Question Source:
New X
Modified Bank Bank Question History:
New Question Comments:
Question 55 5 candidates missed this question for a 56% miss rate. 1 candidate selected A, 3 candidates selected B, and 1 candidate selected D. The correct answer is C.
This question required knowledge the power supply to the Control Rod LIFT coils. The Rod Control Power Cabinets are the power supply that was required.
The question is technically correct as written. No changes to the examination are necessary.
STP LOT-29 NRC RO Exam Question 55 Control Rod LIFT coils are energized DIRECTLY from the _______.
A.
Rod Drive MG Sets B.
Rod Control LOGIC Cabinets C.
Rod Control POWER Cabinets D.
Rod Control DC HOLD Cabinet
STP LOT-29 NRC RO Exam CORRECT ANSWER:
C DISTRACTOR ANALYSIS:
A.
Incorrect: Plausible because the Rod Drive MG Sets, but they do not supply power directly to the Control Rod lift coils. The Rod Drive MG Sets supply power to the Rod Control Power Cabinets, which then supply power to the lift coils.
B.
Incorrect: Plausible because the Rod Control Logic Cabinets control the power being supplied to the lift coils, but they do not directly supply power to them. The Logic Cabinets direct the Rod Control Power Cabinets when to supply power to the lift coils.
C.
Correct: Power is directly supplied to the Control Rod lift coils from the Rod Control power Cabinets.
D.
Incorrect: Plausible the Rod Control DC Hold Cabinet can be used to supply power to the Stationary Gripper Coils under certain conditions.
STP LOT-29 NRC RO Exam Question Number:
55 Tier:
2 Group:
2 K/A:
(001) (SF1 CRDS) Control Rod Drive System (001K2.04) Knowledge of electrical power supplies to the following: (SF1 CRDS) CONTROL ROD DRIVE SYSTEM: Control rod lift coil Importance Rating: 3.1 10 CFR Part 55:
CFR: 41.6 K/A Match:
K/A is matched because the applicant is required to have knowledge of the electrical power supply to the Control Rod Lift Coils.
Technical
Reference:
5Z529ZB0100, MODULE 1 - Rod Control & Position Indication Systems DBD Proposed references to be provided:
None Learning Objective:
LOT201.18, ROD CONTROL SYSTEM
- 12. LIST the power supplies for the major components of the Rod Control System.
Cognitive Level:
Higher Lower X
Question Source:
New X
Modified Bank Bank Question History:
New Question Comments:
Question 90 3 candidates missed this question for a 60% miss rate. 2 candidates selected A, 1 candidate selected D. The correct answer is C.
This question required knowledge of 0PGP03-ZF-0018, Fire Protection System Functionality Requirements. The first part of the question required the candidate to choose the type of fire watch (continuous or hourly) required for an outage of a Standby Diesel Generator sprinkler system. The second part of the question required the knowledge of whether an outage of the forementioned sprinkler system would affect the operability of the Standby Diesel Generator.
Although the question will be enhanced prior to its next use to eliminate the phrase backup suppression equipment in the stem, no changes to the examination are necessary.
STP LOT-29 NRC SRO Exam Question 90 REFERENCE PROVIDED The Unit is at 100% power The Fire Suppression System for Standby Diesel Generator 11 is required to be REMOVED FROM SERVICE for repairs Per 0PGP03-ZF-0018, Fire Protection System Functionality Requirements:
At a MINIMUM, compensatory measures require a(n) ___(1)___ Fire Watch with BACKUP SUPPRESSION EQUIPMENT.
With the Fire Suppression System out of service AND compensatory measures not YET in place, Standby Diesel Generator 11 ____(2)____.
A.
(1)
CONTINUOUS (2) will remain OPERABLE B.
(1)
CONTINUOUS (2) must be declared INOPERABLE C.
(1)
HOURLY (2) will remain OPERABLE D.
(1)
HOURLY (2) must be declared INOPERABLE REFERENCE PROVIDED
STP LOT-29 NRC SRO Exam CORRECT ANSWER:
C DISTRACTOR ANALYSIS:
A.
Incorrect: Plausible because a continuous Fire Watch is required if one or more of the required sprinkler or spray systems are impaired/nonfunctional for an area(s) in which redundant systems or components could be damaged in the event of a fire. The second part is correct. With compensatory measures in place, Standby Diesel Generator 1C will remain Operable until the Fire Suppression system is restored.
B.
Incorrect: Plausible because a continuous Fire Watch is required if one or more of the required sprinkler or spray systems are impaired/nonfunctional for an area(s) in which redundant systems or components could be damaged in the event of a fire. The second part is plausible because if compensatory actions are not in place, Standby Diesel Generator 1C is required to be declared Inoperable.
C.
Correct: At a minimum, compensatory measures require an hourly Fire Watch with backup suppression equipment. This is because the Standby Diesel Generator 1C room does not contain redundant systems or components could be damaged in the event of a fire. With compensatory measures in place, Standby Diesel Generator 1C will remain Operable until the Fire Suppression system is restored.
D.
Incorrect: Plausible because the first part is correct. At a minimum, compensatory measures require an hourly Fire Watch with backup suppression equipment.
This is because the Standby Diesel Generator 1C room does not contain redundant systems or components could be damaged in the event of a fire. The second part is plausible because if compensatory actions are not in place, Standby Diesel Generator 1C is required to be declared Inoperable.
STP LOT-29 NRC SRO Exam Question Number:
90 Tier:
2 Group:
1 K/A:
(064) (SF6 EDG) Emergency Diesel Generator System (064) (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (G2.4.26) EMERGENCY PROCEDURES/PLAN: Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage Importance Rating: 3.6 10 CFR Part 55:
CFR: 43.5 10CFR55.43.b:
(1) Conditions and limitations in the facility license.
K/A Match:
K/A is matched because the applicant is required to have knowledge of facility fire protection requirements for the nonfunctional fire suppression equipment for the Emergency Diesel Generator System.
SRO-Only Question is SRO-Only because the question requires the applicant to have knowledge of the administration of fire protection program requirements, such as compensatory actions associated with inoperable sprinkler systems and fire doors.
Technical
Reference:
0PGP03-ZF-0018, Fire Protection System Functionality Requirements Proposed references to be provided:
0PGP03-ZF-0018, Fire Protection System Functionality Requirements, Pages 1, 6-7, 16-17 ONLY Learning Objective:
LOT802.05, SRO Administrative Procedures, Set 2
- 1. DESCRIBE the requirements of the following procedures to include purpose, scope, definitions, responsibilities, applicable fire system evolutions and forms covered by the procedure:
D. 0PGP03-ZF-0018, Fire Protection System Functionality Requirements Cognitive Level:
Higher X
Lower Question Source:
New X
Modified Bank Bank Question History:
New Question Comments:
Question 93 3 candidates missed this question for a 60% miss rate. All 3 candidates selected C. The correct answer is D.
This question required knowledge of the Technical Specification requirement for Core Exit Thermocouples. Specifically, each core quadrant must contain a minimum of 2 and one quadrant must contain a minimum of 4.
The question is technically correct as written. No changes to the examination are necessary.
STP LOT-29 NRC SRO Exam Question 93 The unit is at 100% power.
Per 0PSP03-SP-0001, Remote Shutdown Monitoring and Accident Monitoring Instrumentation Channel Checks, EACH core quadrant must contain a MINIMUM of ____(1)____ Core Exit Thermocouples and ONE core quadrant must contain a MINIMUM of ____(2)____ Core Exit Thermocouples to satisfy acceptance criteria.
A.
(1) 1 (2) 3 B.
(1) 1 (2) 4 C.
(1) 2 (2) 3 D.
(1) 2 (2) 4
STP LOT-29 NRC SRO Exam CORRECT ANSWER:
D DISTRACTOR ANALYSIS:
A.
Incorrect: Plausible if there is confusion over the number of required channels and the number of CETs per quadrant and also in the TS table is 3 required Containment WR Water Level Transmitters.
B.
Incorrect: Plausible if there is confusion over the number of required channels and the number of CETs per quadrant and the 2nd part is correct.
C.
Incorrect: Plausible as the first part is correct and in the TS table is 3 required Containment WR Water Level Transmitters.
D.
Correct: ONE quadrant must have at least 4 CETs for operability. ALL quadrants must have at least 2 CETs for operability.
STP LOT-29 NRC SRO Exam Question Number:
93 Tier:
2 Group:
2 K/A:
(017) (SF7 ITM) In Core Temperature Monitor System (017) (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM (G2.2.12) EQUIPMENT CONTROL: Knowledge of surveillance procedures Importance Rating: 4.1 10 CFR Part 55:
CFR: 43.2 10CFR55.43.b:
(2) Facility operating limitations in the technical specifications and their bases.
K/A Match:
K/A is matched because the applicant is required to have knowledge of Surveillance procedures relating to the Operability of the In Core Temperature Monitor System.
SRO-Only Question is SRO-Only because the question requires the applicant to have knowledge of Surveillance procedures and action statements for Core Exit Thermocouple operability.
Technical
Reference:
Technical Specifications 0PSP03-SP-0001, Remote Shutdown System and Accident Monitoring Instrumentation Channel Checks Proposed references to be provided:
None Learning Objective:
LOT201.17, Incore Instrumentation System
- 12. Given the topic or title of a specification included in the Technical Specifications, or the Technical Requirements Manual (TRM), DESCRIBE the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillance in order to comply, and the bases for the specification.
Cognitive Level:
Higher Lower X
Question Source:
New X
Modified Bank Bank Question History:
New Question Comments:
STP LOT 29 NRC WRITTEN EXAM POST-EXAM APPLICANT COMMENTS Question: 30 Candidate:
Comment: For the second part, potentially put the valve name and number as it was easy to misconstrue that the second part was asking about RHR and not CCW.
STP Response: The second part of the question was as follows:
The RHR Heat Exchanger OUTLET Temperature Control Valves ____(2)____.
The RHR Heat Exchanger OUTLET Temperature Control Valve controls RCS flow through the RHR Heat Exchanger, not CCW flow. STP recommends no changes to this question.
Question: 73 Candidate:
Comment: The initially in the question made it confusing for me, I answered B because the temperature change of the Pzr water is a result of the pressure change. Therefore, even with the knowledge that a temperature change does happen, since its a secondary effect, I figured it would initially not change.
STP Response: Initially, as used in this question, means the first response. The first response of both pressure and temperature is to lower. It is true that the Pressurizer pressure change causes some of the saturated water to flash to steam which results in Pressurizer temperature lowering, but in each case this is the first response. STP recommends no changes to this question. For future use, the question will be enhanced to include valve numbers.
Question: 90 Candidate:
Comment: The stem for (1) includes misleading information that leads candidates to answering CONTINUOUS only because with BACKUP SUPPRESSION EQUIPMENT follows (1). Per the reference, HOURLY fire watches do not require with backup suppression equipment. Recommend adding with backup suppression equipment to answers A(1) and B(1) to prevent leading.
STP Response: The first part of the question included the requirement for backup suppression equipment, which only applies to continuous fire watches. In this question, the candidates were required to select between hourly and continuous. Since the fire watch requirement was still required to be selected, STP recommends no changes to this question. For future use, backup suppression equipment will be removed from the first part of the question.