IR 05000395/2025301

NRC Examination Report 05000395/2025301

ML26009A039
Person / Time
Site:	Summer
Issue date:	01/09/2026
From:	Matthew Endress NRC/RGN-II/DORS/OB
To:	Jenkins B South Carolina Electric & Gas Co
References
50-395/25-301 50-395/OL-25
Download: ML26009A039 (0)

Text

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION - NRC EXAMINATION REPORT 05000395/2025301

Dear Beth Jenkins:

During the period of November 3, 2025, to November 7, 2025, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who applied for licenses to operate the Virgil C Summer Nuclear Station. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests and the written examination submittal with members of your staff. The written examination was administered by your staff on November 13, 2025.

All applicants passed both the operating test and written examination. There were three post-administration comments submitted by your training staff. These comments, and NRC resolution of these comments, are summarized in Enclosure 2. A Simulator Fidelity Report is included in this report as Enclosure 3.

The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 12.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room).

January 9, 2026 If you have any questions concerning this letter, please contact me at (404) 997-4718.

Sincerely, Matthew Endress, Chief Operations Branch Division of Operating Reactor Safety Docket Nos: 50-395 License Nos: NPF-12

Enclosures:

1. Report Details 2. Post Exam Comments 3. Simulator Fidelity Report

REGION II==

Examination Report Docket No.:

05000395 License No.:

NPF-12 Report No.:

05000395/2025301 Enterprise Identifier:

L-2025-OLL-0035 Licensee:

South Carolina Electric & Gas Company Facility:

Virgil C Summer Nuclear Station Location:

Jenkinsville, SC 29065 Dates:

Operating Test - November 3, 2025 - November 7, 2025 Written Examination - November 13, 2025 Examiners:

K. Kirchbaum, (Chief Examiner) Senior Operations Engineer Michael Meeks, Senior Operations Engineer Mike Donithan, Senior Operations Engineer Shane Battenfield, Operations Engineer Approved by:

Matthew Endress, Chief Operating Branch Division of Operating Reactor Safety

SUMMARY

ER 05000395/2025301; Operating test November 3, 2025 - November 7, 2025 & written exam

November 13, 2025; Virgil C Summer Nuclear Station; Operator License Examinations.

Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 12, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.

Members of the Summer Nuclear Station staff developed both the operating tests and the written examination. The initial operating test, written RO examination, and written SRO examination submittals met the quality guidelines contained in NUREG-1021.

The NRC administered the operating tests during the period of November 3, 2025 - November 7, 2025. Members of the Summer Nuclear Station training staff administered the written examination on November 13, 2025. All Reactor Operator (RO) and Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. All applicants were issued licenses commensurate with the level of examination administered.

There were three post-examination comments.

No findings were identified.

REPORT DETAILS

4OA5 Operator Licensing Examinations

a. Inspection Scope

The NRC evaluated the submitted operating test by combining the scenario events and JPMs to determine the percentage of submitted test items that required replacement or significant modification. The NRC also evaluated the submitted written examination questions (RO and SRO questions considered separately) to determine the percentage of submitted questions that required replacement or significant modification, or that clearly did not conform with the intent of the approved knowledge and ability (K/A)statement. Any questions that were deleted during the grading process, or for which the answer key had to be changed, were also included in the count of unacceptable questions. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, Operator Licensing Standards for Power Reactors.

The NRC reviewed the licensees examination security measures while preparing and administering the examinations to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests.

The NRC performed an audit of license applications during the preparatory site visit to confirm that they accurately reflected the subject applicants qualifications in accordance with NUREG-1021.

The NRC administered the operating tests during the period of November 3, 2025, to November 7, 2025. The NRC examiners evaluated six Reactor Operator (RO) and nine Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. Members of the Summer Nuclear Station training staff administered the written examination on November 13, 2025. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Summer Nuclear Station, met the requirements specified in 10 CFR Part 55, Operators Licenses.

The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the operating tests.

b. Findings

No findings were identified.

The NRC developed the written examination sample plan outline. Members of the Summer Nuclear Plant training staff developed both the operating tests and the written examination. All examination material was developed in accordance with the guidelines contained in Revision 12, of NUREG-1021. The NRC examination team reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials.

The NRC determined, using NUREG-1021, that the licensees initial examination submittal was within the range of acceptability expected for a proposed examination.

All applicants passed both the operating test and written examination and were issued licenses.

Copies of all individual examination reports were sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.

The licensee submitted three post-examination comments. The resolution for those comments is contained on Enclosure 2. A copy of the final written examinations and answer key, with all changes incorporated, may be accessed not earlier than November 12, 2027, in the ADAMS system (ADAMS Accession Number(s) ML25350A064 and ML25350A136).

Exit Meeting

Summary On November 7, 2025, the NRC examination team discussed generic issues associated with the operating test with members of the Summer Nuclear Station staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.

On January 8, 2026, The NRC chief examiner conducted the final exit meeting with Mr.

Tim Kogelmann where exam results were shared with your training staff.

KEY POINTS OF CONTACT Licensee personnel Beth Jenkins Site Vice President Bob Williamson Training Manager Tim Kogelmann Initial Training Supervisor Michael Anderson Exam Author Darren Wokurka Exam Author

FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS

A complete text of the applicants and licensees post-examination comments can be found in

ADAMS under Accession Number ML25350A180.

25 NRC JPM A1-a SRO:

Comment from Applicant, in part:

This JPM was built and validated using the curve book to determine the volume that would raise

RWST level to 92% (462,683.75 gallons if calculated or 465,000 if reading the graph). This is

considered the Tech Spec minimum level based on Main Control Board indications. The

difference between the two volumes is to ensure that the percent level accounts for indication

inaccuracies.

In several examples, while performing the calculation to increase RWST level, the Tech Spec

minimum value of 453,800 gallons was used to calculate the volume that must be added to

reach the Tech Spec minimum value in the RWS

T. The Tech Spec minimum value of 453,800

gallons was used and current volume of 321,866.88 was subtracted. This resulted in a total of

131,933.12 gallons to be added to the RWS

T. This number (131,933.12 gallons) was then

divided by 80 gal/min as this is the total makeup flow and resulted in 1649.16 minutes. This

value was then divided by 60 min/hr., which gave them 27.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This led to the incorrect

number of hours being calculated for the addition as compared to the JPM Task Standard.

Because of the flow totalizers, the specific amount of water and acid being added to the RWST

can be precisely counted from the Main Control Board indications and therefore can accurately

determine a minimum of 453,800 gallons in the RWS

T. Therefore, it is recommended that the

Task Standard times from 29.16 -29.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> to 27.48 -29.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

Facility Licensee Recommendation, in part:

We ask that the task standard be changed in the following manner:

Calculates the time required to raise RWST level to a minimum of 453,800 gallons or

2% between 27.48 -29.35 hrs.

Determines the crew must shutdown to HOT STANDBY.

NRC Resolution:

The licensees recommendation was accepted.

The purpose of the JPM was to have the applicants determine time to raise RWST level and

ensure the plant complies with Technical Specifications while raising level. As alternate

methods are available to calculate the necessary volume needed to raise RWST, the answer

key was modified to accept this alternate approved method. The determination of the shorter fill

interval did not change the determination that the crew must shutdown the plant to HOT

STANDBY.

25 NRC JPM e:

Comment from Applicant, in part:

JPM e required candidates to manually initiate Reactor Building Spray and close several Phase-

B isolation valves. During the performance of this JPM, some candidates failed to close MVG-

9606. Upon further review, MVG-9605 and MVG-9606 are in series and only one of these two

valves are required to be closed to ensure the required Phase-B Containment Isolation has

occurred. MVG-9605 is inside the Reactor Building and MVG-9606 is outside the Reactor

Building. See picture from drawing 302-612, Component Cooling Water System.

Facility Licensee Recommendation, in part:

We would like to change the Task standard so that it reads the following:

Closes the following Phase-B Isolation valves from the MCB:

o

MVG-9600, TO THERM BARR ISOL.

o

MVG-9605, FROM RB LOAD ISOL (IRB) AND/OR MVG-9606, FROM RB LOAD

ISOL (ORB).

o

MVG-9568, TO RB LOAD.

Establishes at least one train of RB Spray with flow > 2500 gpm as indicated on Fl-7368

or Fl7378, SPR PP A(B) DISCH FLOW GPM.

Secures Reactor Coolant Pumps.

NRC Resolution:

The licensees recommendation was accepted.

The purpose of this Critical Step of the JPM was to have the applicants determine that a Phase

B had occurred and recognize that all the Reactor Building penetrations were properly isolated.

Closing either MVG-9605 or MVG-9606 provides adequate isolation of Penetration 330 to meet

Containment Isolation requirements

25 NRC JPM A3 SRO:

Comment from Applicant, in part:

This JPM required the applicants to determine that an ALERT was required to be declared

based on a given set of conditions. The applicants were also to determine which notification

was required in accordance with NL-122, REGULATORY NOTIFICATION AND REPORTING.

The applicants were then also required to determine the highest level of plant management at

VC Summer that must be notified by the Shift Manager. The applicant was expected to

determine that either the Operations Manager or the Operations Manager on Call (OMOC) must

be notified.

One applicant utilized OAP-100.4, COMMUNICATION, based on his experience of performing

certain actions during Emergency Response Organization (ERO) drills. NL-122, ID#/Reference

I-25, which covers Event Reporting Requirements. This item contains a NOTE to refer to OAP-

100.4. This procedure was not utilized during JPM validations nor was it considered when

creating this JPM. The applicant stated the Global Notification list was required to be sent out

which notified all senior level management positions. OAP-100.4, Attachment II, step 3.d.

states "the STA, SM, and OMOC shall determine, based on issue/event, if the Global Page List

or the Local Management Page List will be used to communicate that issue/event". Then on

Page 4 of Attachment II, there is a list of "notification criteria." Item 4 on that list is "Activation of

the Emergency Plan" and lists all senior site level management that must be notified including

the Site Vice President and Plant Manager.

Facility Licensee Recommendation, in part:

Request the task standard be changed in the following manner concerning the highest level of

management that must be notified as per the JPM Cue:

Determines that either the Operations Manager or the Operations Manager on Call

(OMOC) must be apprised.

OR

Determines the site personnel on the V.C. Summer Global Page List or the V.C.

Summer Local Management page list on Attachment II of OAP-100.4.

NRC Resolution:

The licensees recommendation was accepted.

The applicants were asked to determine the highest level of plant management at VC Summer

that must be apprised by the SM in accordance with NL-122 and based on the conditions

provided. Procedure NL-122 directed that the Operations Manager or the Operations Manager

on Call be informed. However, NL-122 also directs notifications, as necessary, per the Global

Page List, by referencing OAP-100.4, and is therefore an acceptable answer. Since the

notification necessary per NL-122 and the Global Page List is referenced by NL-122, the JPM

task standard was changed to accept both as acceptable answers.

SIMULATOR FIDELITY REPORT

Facility Licensee: Virgil C Summer Nuclear Station

Facility Docket No.: 05000395

Operating Test Administered: November 3, 2025 - November 7, 2025.

This form is to be used only to report observations. These observations do not constitute audit

or inspection findings and, without further verification and review in accordance with Inspection

Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee

action is required in response to these observations.

No simulator fidelity or configuration issues were identified.