ML25014A182
| ML25014A182 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 01/29/2025 |
| From: | Tony Brown NRC/NRR/DANU/UNPO |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| IR 2024201 | |
| Download: ML25014A182 (1) | |
See also: IR 05000128/2024201
Text
Mr. Jere Jenkins, Director
Texas Engineering Experiment Station
Texas A&M University System
Nuclear Science Center
1095 Nuclear Science Road, MS 3575
College Station, TX 77843
SUBJECT:
TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY
SYSTEM - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION
REPORT NO. 05000128/2024201 AND NOTICE OF VIOLATION
Dear Mr. Jenkins:
From December 16-20, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted
an inspection at the Texas Engineering Experiment Station/Texas A&M University System
Nuclear Science Center. The results of this inspection are documented in the enclosed report.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed various activities, and
interviewed personnel.
Based on the results of this inspection, the NRC has determined that one Severity Level IV
violation of NRC requirements has occurred. The violation was evaluated in accordance with the
NRC Enforcement Policy. The current Enforcement Policy is included on the NRCs website at
https://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. The violation is cited in
the enclosed Notice of Violation (Notice) and the circumstances surrounding it are described in
detail in the enclosed inspection report. The violation is cited in the Notice because it
constitutes a failure to meet regulatory requirements that has more than minor safety
significance and the licensee failed to identify the violation.
You are required to respond to this letter and should follow the instructions specified in the
enclosed Notice when preparing your response. If you have additional information that you
believe the NRC should consider, you may provide it in your response to the Notice. The NRC
review of your response to the Notice will also determine whether further enforcement action is
necessary to ensure compliance with regulatory requirements.
January 29, 2025
J. Jenkins
- 2 -
During this inspection, the NRC has determined that another Severity Level IV violation of NRC
requirements occurred. This violation is being treated as a non-cited violation (NCV), consistent
with section 2.3.2.a of the Enforcement Policy. The NCV is described in the subject inspection
report. If you contest the violation or significance of the NCV, you should provide a response
within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear
Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with
copies to the Director, Office of Enforcement, United States Nuclear Regulatory Commission,
Washington, DC 20555-0001.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public
inspections, exemptions, requests for withholding, a copy of this letter, its enclosures, and your
response (if any) will be available electronically for public inspection in the NRC Public
Document Room or from the NRCs document system (Agencywide Documents Access and
Management System (ADAMS)). ADAMS is accessible from the NRC website at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). To the extent
possible, your response should not include any personal privacy or proprietary information, so
that it can be made available to the Public without redaction.
If you have any questions concerning this inspection, please contact Juan Arellano at
301-415-0477, or by email at Juan.Arellano@nrc.gov.
Sincerely,
Tony Brown, Chief
Non-Power Production and Utilization Facility
Oversight Branch
Division of Advanced Reactors and Non-Power
Production and Utilization Facilities
Office of Nuclear Reactor Regulation
Docket No. 50-128
License No. R-83
Enclosures:
As stated
cc w/enclosures: GovDelivery Subscribers
Signed by Brown, Tony
on 01/29/25
OFFICE
NRR/DANU/UNPO
NRR/DANU/UNPO/LA
NRR/DANU/UNPO/BC
NAME
JArellano
NParker
TBrown
DATE
01/15/2025
01/15/2025
01/20/2025
Enclosure 1
Texas Engineering Experiment Station
Docket No. 50-128
Texas A&M University System
License No. R-83
During a U.S. Nuclear Regulatory Commission (NRC) inspection conducted
December 16-20, 2024, a violation of NRC requirements was identified. In accordance with the
NRC Enforcement Policy, the violation is listed below:
Texas Engineering Experiment Station (TEES) Texas A&M University System (TAMU) Facility
Operating License No. R-83, Amendment No. 19, dated July 22, 2021, section 2.C.2.,
Technical Specifications, states that, The Technical Specifications contained in Appendix A,
as revised by license Amendment No. 19, are hereby incorporated in their entirety in the
license. The licensee shall operate the facility in accordance with the Technical Specifications.
Technical specification (TS) 6.2.4, RSB Audit Function, states, in part, The audit function shall
include selective (but comprehensive) examination of operating records, logs, and other
documents. Audits shall include but are not limited to the following:.
TS 6.2.4(1.) states, Facility operations, including radiation protection, for conformance to the
Technical Specifications, applicable license conditions, and standard operating procedures: at
least once per calendar year (interval between audits not to exceed 15 months). TS 6.2.4(2.)
states, The results of action taken to correct those deficiencies that may occur in the reactor
facility equipment systems, structures, or methods of operations that affect reactor safety: at
least once per calendar year (interval between audits not to exceed 15 months). TS 6.2.4(5.)
states, The reactor facility security plan and implementing procedures: at least once every
other calendar year (interval between audits not to exceed 30 months).
Contrary to TS 6.2.4(1.) and TS 6.2.4(2.), the inspectors identified that the licensee failed to
perform an audit to include facility operations and an audit to include the results of action taken
to correct those deficiencies that may occur in the reactor facility equipment systems, structures,
or methods of operations that affect reactor safety at least once per calendar year. Specifically,
the licensee performed an audit, that included TS 6.2.4(1.) and TS 6.2.4(2.), on August 28,
2022, and performed the subsequent audit on April 2, 2024, which exceeded the allowable 15-
month frequency.
Contrary to TS 6.2.4(5.), the inspectors identified that the licensee failed to perform an audit to
include the reactor facility security plan and implementing procedures at least once every other
calendar year. Specifically, the licensee performed an audit, that included TS 6.2.4(5.), on June
28, 2022, and had not performed a subsequent audit, which exceeded the 30-month
requirement.
TS 6.2.5, Audit of ALARA Program, states, in part, The Chair of the RSB or designated
alternate (excluding anyone whose normal job function is within the NSC) shall conduct an audit
of the reactor facility ALARA program annually.
Contrary to TS 6.2.5, the inspectors identified that the licensee failed to conduct an audit of the
reactor facility as low as is reasonably achievable (ALARA) program annually. Specifically, the
licensee performed an audit, that included TS 6.2.5, on June 28, 2022, and performed the
subsequent audit on April 3, 2024, which exceeded the annual requirement.
- 2 -
In accordance with the NRC Enforcement Manual, multiple examples of the same violation
during the period covered by an inspection should be included as one citation. This issue
involves four examples of the same non-compliance and has been determined to be a Severity
Level IV violation (NRC Enforcement Policy section 6.4).
Pursuant to the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 2.201,
Notice of violation, TEES/TAMU System is hereby required to submit a written statement or
explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,
Washington, DC 20555-0001, within 30 days of the date of the letter transmitting this Notice of
Violation (Notice). This reply should be clearly marked as a Reply to a Notice of Violation, and
should include: (1) the reason for the violation, or, if contested, the basis for disputing the
violation or severity level; (2) the corrective steps that have been taken and the results
achieved; (3) the corrective steps that will be taken; and (4) the date when full compliance will
be achieved. Your response may reference or include previous docketed correspondence, if the
correspondence adequately addresses the required response. If an adequate reply is not
received within the time specified in this Notice, an Order or a Demand for Information may be
issued as to why the license should not be modified, suspended, or revoked, or why such other
action as may be proper should not be taken. Where good cause is shown, consideration will be
given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the
basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory
Commission, Washington, DC 20555-0001.
Because your response will be made available electronically for public inspection in the NRC
Public Document Room or from the NRCs document system (Agencywide Documents Access
and Management System), accessible from the NRC website at https://www.nrc.gov/reading-
rm/adams.html, to the extent possible, it should not include any personal privacy, proprietary, or
safeguards information so that it can be made available to the public without redaction. If
personal privacy or proprietary information is necessary to provide an acceptable response,
then please provide a bracketed copy of your response that identifies the information that
should be protected and a redacted copy of your response that deletes such information.
If you request withholding of such material, you must specifically identify the portions of your
response that you seek to have withheld and provide in detail the bases for your claim of
withholding (e.g., explain why the disclosure of information will create an unwarranted invasion
of personal privacy or provide the information required by 10 CFR 2.390, Public inspections,
exemptions, requests for withholding, paragraph (b) to support a request for withholding
confidential commercial or financial information). If safeguards information is necessary to
provide an acceptable response, please provide the level of protection described in
10 CFR 73.21, Protection of Safeguards Information: Performance Requirements.
In accordance with 10 CFR 19.11, Posting of notices to workers, you may be required to post
this Notice within two working days of receipt.
Dated this 29th day of January 2025.
Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.:
50-128
License No.:
R-83
Report No.:
Licensee:
Texas Engineering Experiment Station/Texas A&M University System
Facility:
Texas Engineering Experiment Station/Texas A&M University System
Nuclear Science Center
Location:
College Station, Texas
Dates:
December 16 - 20, 2024
Inspectors:
Juan A. Arellano
Approved by:
Tony Brown, Chief
Non-Power Production and Utilization
Facility Oversight Branch
Division of Advanced Reactors and Non-Power
Production and Utilization Facilities
Office of Nuclear Reactor Regulation
- 2 -
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an inspection at the Texas Engineering Experiment (TEES) Texas
A&M University (TAMU) System, in accordance with the research and test reactor inspection
program. This is the NRCs program for overseeing the safe operation of licensed research and
test reactors. Refer to https://www.nrc.gov/reactors/non-power.html for more information.
List of Violations
Failure to conduct audits as required by the technical specifications (TSs)
Severity
Report Section
NOV 2024201-01
Open
69001.09
The inspectors identified a Severity Level IV notice of violation of TS 6.2.4(1.), TS 6.2.4(2.),
TS 6.2.4(5.), and TS 6.2.5 for the licensees failure to perform audits within the required
frequency.
Non-Cited Violation (NCV 05000128/2024201-02)
69001.07
The inspectors identified a Severity Level IV violation of TS 6.7.1 for the licensees failure to
submit an annual operating report within the required frequency. This violation of very low
safety significance was identified by the licensee and has been corrected and is treated as a
non-cited violation, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Additional Tracking Items
None.
- 3 -
REPORT DETAILS
Facility Status
The TEES/TAMU System Nuclear Science Center research reactor was operated in support of
training, experiments, and maintenance since the last routine inspection. During this inspection,
the reactor was operated for maintenance.
Inspection Scopes
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at
https://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Inspections were declared complete when the IP requirements most appropriate to the
inspection activity were met consistent with Inspection Manual Chapter 2545, Research and
Test Reactor Inspection Program. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
69001 - Class II Non-Power Reactors
This inspection included a review of selected aspects of the research and test reactor since the
last inspection, to verify activities were conducted safely and in accordance with regulatory
requirements and licensee commitments.
Organization and Staffing (IP Section 02.01)
This inspection included a review of the licensees organizational changes and shift staffing
records to verify compliance with TS requirements and licensee commitments. Specifically, the
inspection included a review of the following:
observation of daily control room briefings
current staff qualifications
staffing requirements for safe operation of the facility
reactor logbooks
organizational structure for the facility
reactor safety board (RSB) meeting minutes, dated 2022-present
Procedures (IP Section 02.03)
This inspection included a review of selected licensee procedures to verify: that the
administrative controls were in accordance with the TSs, license requirements, and licensee
commitments; the procedures in use were current and reviewed and approved, as required by
the TSs; procedures could be implemented as intended; and reactor personnel were observing
administrative controls and TS requirements relative to procedural adherence. Specifically, the
inspection included a review of the following:
select facility procedures
observation of a prestart up checklist
- 4 -
observation of a reactor startup
observation of a reactor shutdown
observation of a calibration on the facility air monitors
observation of an irradiated experiment removed from the core
RSB meeting minutes, dated 2022-present
Health Physics (IP Section 02.07)
This inspection included a review of the licensees health physics program to verify that the
provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 19, Notices,
Instructions and Reports to Workers: Inspection and Investigations, and Part 20, Standards for
Protection against Radiation, the TSs, and the licensees procedural requirements were met.
The inspection reviewed: licensees dose limits; required radiation surveys, sampling, and
monitoring; calibration of radiological instruments; the personnel dosimetry program; effluent
releases; posting requirements; training requirements; the implementation of as low as is
reasonably achievable (ALARA) principles; and the radiation protection programs review and
approval requirements. Specifically, the inspection included a review of the following:
observation of radiation surveys
observation of an emergency drill performed
inspectors performed radiation surveys
observation of selected postings and verified with surveys that they were posted
correctly
select personnel and environmental dosimetry records, dated 2022-present
select ALARA reviews, dated 2022-present
select pool water samples, dated 2022-present
select liquid and gaseous effluent data, dated 2022-present
select calibration records for radiation instrumentation, dated 2022-present
select radiation work permits, dated 2024-present
select radiation training records, dated 2023-present
Design Changes (IP Section 02.08)
This inspection included a review of design changes to determine whether they were reviewed,
approved, and implemented in accordance with 10 CFR 50.59, Changes, tests and
experiments, the TSs, and the licensees administrative procedures. The inspection also
verified that modified equipment would continue to meet regulatory and procedural requirements
and licensee commitments. Specifically, the inspection included a review of the following:
10 CFR 50.59 evaluations, dated 2023-present
10 CFR 50.59 screenings, dated 2023-present
RSB meeting minutes, dated 2022-present
2023 annual operating report
Committees, Audits and Reviews (IP Section 02.09)
This inspection included a review of the licensees committees, audits, and reviews to verify the
RSB and independent audits were conducted in accordance with the TSs. The inspection
verified issues identified from reviews were resolved in accordance with the TSs requirements
and the licensees procedures. Specifically, the inspection included a review of the following:
- 5 -
RSB meeting minutes, dated 2022-present
audits required to be performed by TS 6.2.4
event notification 57174 follow up
86740 - Inspection of Transportation Activities
This inspection included a review of the licensees transportation activities to verify they have
established and are maintaining an effective management-controlled program, to ensure
radiological and nuclear safety in the receipt, packaging, and delivery of licensed radioactive
materials. Specifically, the inspection included a review of the following:
select transportation procedures
select bill of lading documents dated from 2023-present
select radioactive shipping label checklist performed from 2023-present
select NESC repackaging shipment information performed from 2023-present
Inspection Results
Minor Violation (VIO 05000128/2024201-03)
69001.01
Minor Violation: On June 14, 2024, the licensee reported event notification57174 to the
Headquarters Operation Center for a fuel pin that did not pass the test criteria specified in
TS 3.1.5, Reactor Fuel Parameters, during fuel inspection. The licensee responded as
required by the TSs to identify a degraded fuel pin and inspected the entire core. While
reviewing EN 57174, the inspectors identified a violation of TS 6.7.2, Special Reports. TS 6.7.2 states, in part, There shall be a report not later than the following working day by
telephone and confirmed in writing by fax or similar conveyance to the NRC Headquarters
Operations Center, and followed by a written report that describes the circumstances of the
event and sent within 14 days to the U.S. Nuclear Regulatory Commission.
Contrary to TS 6.7.2, the licensee failed to send a written report that describes the
circumstances of the event to the NRC within 14 days after the licensee determined that a
reportable event occurred.
Screening: The event report was sent on December 15, 2024. The information in the report
would not have changed the NRCs oversight posture and because the licensee performed all
required corrective actions after identifying the failed fuel element, the inspectors determined
that the failure to meet the requirements of TS 6.7.2 constitutes a violation of minor
significance in accordance with section 2.0 of the NRC Enforcement Policy. This minor
violation (VIO 05000128-2024201-03) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 6.7.2 constitutes a minor violation that is not
subject to enforcement action in accordance with the NRC Enforcement Policy.
- 6 -
Non-Cited Violation (NCV 05000128/2024201-02)
69001.07
The inspectors identified a Severity Level IV violation of TS 6.7.1 for the licensee failing to
submit an annual operating report within the required frequency. This violation of very low
safety significance was identified by the licensee and has been corrected and is treated as a
non-cited violation, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Violation: TS 6.7.1, Annual Operating Report, states, in part, An annual report covering the
operation of the reactor facility during the previous calendar year shall be submitted to the
NRC before March 31 of each year providing the following information:.
Contrary to TS 6.7.1, the annual report covering the operation of the reactor facility for
calendar year 2023 was not submitted to the NRC before March 31, 2024. Specifically, the
annual operating report was not submitted until December 19, 2024, 8 months and 19 days
after the required time frame.
The inspectors determined that the problem was identified by the licensee and reported to the
inspectors. Corrective actions were identified and completed. As a result, this non-willful,
non-repetitive, licensee-identified and licensee-corrected violation will be treated as a
non-cited violation consistent with section 2.3.2.a of the NRC Enforcement Policy
Minor Violation (VIO 05000128/2024201-04)
69001.07
Minor Violation: TS 4.5, Radiation Monitoring Systems and Effluents, specification 1 states,
The area radiation monitoring system (ARM) and the FAM system shall be calibrated
annually, shall be channel tested weekly, and shall be channel checked prior to reactor
operation.
Contrary to TS 4.5(1.), the licensee identified that the Facility Air Monitoring (FAM) system
was not calibrated annually. Specifically, the licensee identified that the calibrations were
revised in 2018 to not require a full calibration of the entire FAM system. The last correct
calibration was performed on November 19, 2018.
Screening: The licensee performed a complete FAM system calibration in January 2024, prior
to reactor operations, and determined that the FAM system was never out of calibration since
the last calibration on November 19, 2018. As a result, the inspectors determined that failure
to meet the requirements of TS 4.5(1.) constitutes a violation of minor significance in
accordance with section 2.0 of the NRC Enforcement Policy. This minor violation (VIO 05000128/2024201-04) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 4.5(1.) constitutes a minor violation that is not
subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes Unresolved Item 05000128/2023201-04.
- 7 -
Failure to conduct audits as required by the TSs
Severity
Report Section
NOV 2024201-01
Open
69001.09
The inspectors identified a Severity Level IV notice of violation of TS 6.2.4(1.), TS 6.2.4(2.),
TS 6.2.4(5.), and TS 6.2.5 for the licensees failure to perform audits within the required
frequency.
Description: TS 6.2.4 and TS 6.2.5 requires the licensee to perform audits. While the licensee
failed to perform the audits required by TS 6.2.4(1.), TS 6.2.4(2.), and TS 6.2.5 within the
required time frame, the audits were eventually performed. However, during an NRC security
inspection performed December 11-14, 2023, the inspector noted TS 6.2.4(5.) was not
performed since June 2021 and was due December 2023. The inspector noted that the audit
was scheduled for the month of December, but the auditor changed plans to conduct the audit
in January 2024. During this inspection, the inspectors confirmed no audit was conducted in
January 2024. The licensee has currently not performed an audit required by TS 6.2.4(5.)
since June 2021.
Corrective Actions: The inspectors confirmed that the licensee placed the issue in their
spreadsheet tracking all issues that need to be completed. The licensee informed the
inspectors that an individual that works for the Nuclear Science Center and is not immediately
responsible for the area would perform the audit this calendar year.
Analysis: The violation was evaluated in accordance with the NRC Enforcement Policy. The
violation is cited as a Notice of Violation because it constitutes a failure to meet regulatory
requirements that has a more than minor safety significance and the licensee failed to identify
the violation.
Enforcement:
Severity: The violation is categorized at Severity Level IV in accordance with section 6.9.d of
Violation: TS 6.2.4, RSB Audit Function, states, in part, The audit function shall include
selective (but comprehensive) examination of operating records, logs, and other documents.
Audits shall include but are not limited to the following:.
TS 6.2.4(1.) states, Facility operations, including radiation protection, for conformance to the
Technical Specifications, applicable license conditions, and standard operating procedures:
at least once per calendar year (interval between audits not to exceed 15 months).
TS 6.2.4(2.) states, The results of action taken to correct those deficiencies that may occur in
the reactor facility equipment systems, structures, or methods of operations that affect reactor
safety: at least once per calendar year (interval between audits not to exceed 15 months).
TS 6.2.4(5.) states, The reactor facility security plan and implementing procedures: at least
once every other calendar year (interval between audits not to exceed 30 months).
Contrary to TS 6.2.4(1.) and TS 6.2.4(2.), the inspectors identified that the licensee failed to
perform an audit to include facility operations and an audit to include the results of action
taken to correct those deficiencies that may occur in the reactor facility equipment systems,
structures, or methods of operations that affect reactor safety at least once per calendar year.
Specifically, the licensee performed an audit, that included TS 6.2.4(1.) and TS 6.2.4(2.), on
- 8 -
August 28, 2022, and performed the subsequent audit on April 2, 2024, which exceeded the
allowable 15-month frequency.
Contrary to TS 6.2.4(5.), the inspectors identified that the licensee failed to perform an audit
to include the reactor facility security plan and implementing procedures at least once every
other calendar year. Specifically, the licensee performed an audit, that included TS 6.2.4(5.),
on June 28, 2022, and had not performed a subsequent audit, which exceeded the 30-month
requirement.
TS 6.2.5, Audit of ALARA Program, states, in part, The Chair of the RSB or designated
alternate (excluding anyone whose normal job function is within the NSC) shall conduct an
audit of the reactor facility ALARA program annually.
Contrary to TS 6.2.5, the inspectors identified that the licensee failed to conduct an audit of
the reactor facility as low as is reasonably achievable (ALARA) program annually.
Specifically, the licensee performed an audit, that included TS 6.2.5, on June 28, 2022, and
performed the subsequent audit on April 3, 2024, which exceeded the annual requirement.
Enforcement Action: This violation is being cited as a Notice of Violation, consistent with
sections 2.3.2 and 2.3.3 of the NRC Enforcement Policy.
This closes Inspector Follow Up Item 05000128/2023202-01.
Exit Meeting and Debriefs
The inspectors verified no proprietary information was retained or documented in this report.
On December 20, 2024, the inspectors presented the NRC inspection results to
members of licensee management and staff.
- 9 -
Documents Reviewed
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Logbook
272
Reactor Operations Logbook
N/A
N/A
License Management Change for the
Referenced Reactors
May 8, 2024
69001.01
Miscellaneous
N/A
NSCR Reactor Facilities Org Chart
December 1,
2024
AP-03
Procedures
Revision 1
CCP-01
Weekly FAM Channel Test
November 7,
2023
SOP Section
VII
Procedure A
Primary Coolant Radiological Analysis
January 31,
2020
SOP Section
VII
Procedure B
Radiation Monitoring Channels Check
January 31,
2020
SOP Section
II Procedure
E
Reactor Shutdown and Secure
February 17,
2016
69001.03
Procedure
SOP Section
II Procedure
B
Reactor Startup
February 17,
2016
SOP Section
VII
Procedure I
Stack Gas Monitor Calibration
Adjustment
January 31,
2020
CCP-04
Stack Gas (Ar-41) Monitor Calibration
June 5, 2024
RSP-01
ALARA Procedure
March 14,
2023
69001.07
Procedure
E-1
Personnel Dosimetry
February 13,
1995
- 10 -
RSP-06
Radiation Work Permit Procedure
December
12, 2023
C-12
Facility Radiation Survey
December
14, 2004
Power Point
N/A
Radiation Worker 1 Training
N/A
Logbook
270
Reactor Operations Logbook
N/A
845
Radiation Work Permit Sign in/Out Sheet
October 30,
2023
825
Channel No.1, Maintenance and
Calibration
January 4,
2024
826
Channel No. 2 Maintenance and
Calibration
January 4,
2024
827
Channel No. 3 and 5 Maintenance and
Calibration
January 11,
2024
828
Channel No. 4, Maintenance and
Calibration
January 5,
2024
Procedural
Form
829
Channel No. 6, Maintenance and
Calibration
January 23,
2024
Miscellaneous
PLN-NESC-
NESC Radiation Safety Program
November
11, 2021
AP-11
Change Management
July 16,
2023
Procedure
AP-12
Work Package
July 16,
2023
2023-02
TR Drawer Repair
April 5, 2023
2023-03
ARM Display Computer
April 26,
2023
2023-04
FAM 1, 2 Paper Drive Power Supply
May 3, 2023
2023-06
Bayonet Change Out
June 1, 2023
69001.08
Design
Change
2023-07
Safety Channel 1, 2 Repair
June 8, 2023
- 11 -
2023-09
August Fuel Element Swap
August 9,
2023
2023-10
July 2023 Transient Rod Damage
August 9,
2023
2023-11
July 2023 Transient Drive Component
Wear
August 15,
2023
2023-13
Pool Walkway Mount
November
28, 2023
2023-14
Log Channel Cable Repair
September
26, 2023
2023-15
HVAC Controls Reprogramming
September
23, 2023
2024-03
Reactor Bridge Jack Replacement
February 28,
2024
2024-05
June 2024 Fuel Elements Swap
July 15,
2024
2024-08
Log Power Channel Detector
Replacement
November
20, 2024
2024-09
Safety Channel 1 Inverter IC
Replacement
November
20, 2024
Miscellaneous
NSCR-RPT-
2302
2023 Transient Rod Malfunction Analysis
August 13,
2023
Drawing
252D205
Transient Rod Assembly-Air Follower
N/A
199
Meeting Minutes
July 28,
2022
200
Meeting Minutes
February 13,
2023
201
Meeting Minutes
March 13,
2023
69001.09
Reactor
Safety Board
202
Meeting Minutes
June 15,
2023
- 12 -
203
Meeting Minutes
July 19,
2023
204
Meeting Minutes
October 16,
2023
205
Meeting Minutes
December
14, 2023
206
Meeting Minutes
January 31,
2024
207
Meeting Minutes
May 23,
2024
PLN-RSB-
CHARTER
Charter for the Reactor Safety Board
February 21,
2022
N/A
Reactor Operations Audit
August 26,
2022
N/A
NSCR Reactor Staff Response to the
Program Audit Conducted in August 2022
February 9,
2023
N/A
Health Physics Records Review
June 28,
2022
N/A
Response to Health Physics Records
Review Conducted June 28, 2022
N/A
N/A
Reactor Operations Audit of the Texas
A&M Engineering Station Nuclear
Engineering & Science Center Research
Reactor
April 2, 2024
Audit/Review
N/A
Technical Specifications Audit
November
12, 2024
Event Report
57174
Submission of Technical Specifications
Required Report for Event Notification 57174, Identification of Degraded Fuel
Elements During 2024 Maintenance
December
15, 2024
86740
Procedure
SOP Section
VII
Procedure Q
Radioactive Materials Released
January 31,
2020
- 13 -
SOP Section
VII
Procedure R
Radioactive Materials Handling
December
19, 2024