Kansas State University; Exemption, 102167-102170 [2024-29695]
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[FR Doc. 2024–29932 Filed 12–13–24; 11:15 am]
BILLING CODE 7570–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–188; NRC–2024–0190]
Kansas State University; Exemption
Nuclear Regulatory
Commission.
ACTION: Notice; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing an
exemption in response to a request
dated March 7, 2024, as supplemented
by letters dated June 11, October 4, and
November 20, 2024, from Kansas State
University (KSU). The exemption
temporarily exempts three licensed
senior reactor operators at KSU from the
NRC’s requirements regarding
completing the facility’s requalification
program and actively performing the
functions of a senior operator in order
to allow them to resume maintenance
activities involving fuel movement, fuel
cleaning, and fuel inspection and to
return the facility to normal operations.
DATES: The exemption was issued on
December 5, 2024.
ADDRESSES: Please refer to Docket ID
NRC–2024–0190 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly available
information related to this document
using any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
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SUMMARY:
VerDate Sep<11>2014
19:45 Dec 16, 2024
Jkt 265001
for Docket ID NRC–2024–0190. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
Stacy.Schumann@nrc.gov. For technical
questions, contact the individuals listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publicly
available documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘Begin Web-based ADAMS Search.’’ For
problems with ADAMS, please contact
the NRC’s Public Document Room (PDR)
reference staff at 1–800–397–4209, at
301–415–4737, or by email to
PDR.Resource@nrc.gov. The exemption
request dated March 7, 2024, and the
supplemental letters dated June 11, and
October 4, and November 20, 2024, are
available in ADAMS under Accession
Nos. ML24085A808, ML24164A092,
ML24281A032, and ML24326A142,
respectively.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Andrew Miller, telephone: 301–415–
3398; email: Andrew.Miller@nrc.gov and
Duane Hardesty, telephone: 301–415–
3724; email: Duane.Hardesty@nrc.gov.
Both are staff of the Office of Nuclear
Reactor Regulation at the U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated: December 12, 2024.
Duane A. Hardesty,
Senior Project Manager, Non-Power
Production and Utilization Facility Licensing
Branch, Division of Advanced Reactors and
Non-Power Production and Utilization
Facilities, Office of Nuclear Reactor
Regulation.
Attachment—Exemption
NUCLEAR REGULATORY
COMMISSION
Docket No. 50–188
Kansas State University Nuclear
Reactor Facility; Exemption
I. Background
Kansas State University (KSU) holds
the U.S. Nuclear Regulatory
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102167
Commission (NRC, the Commission)
Renewed Facility Operating License No.
R–88 for the Kansas State University
Nuclear Reactor Facility (the facility),
which is a Training, Research, Isotopes,
General Atomics (TRIGA) research
reactor located on the KSU campus in
Manhattan, Kansas. Under this license,
KSU is authorized to operate the facility
at steady-state power levels up to a
maximum of 1,250 kilowatts (thermal)
and in the pulse mode with reactivity
insertions not to exceed specified limits.
The license is subject to the rules,
regulations, and orders of the NRC.
II. Request/Action
By letter dated March 7, 2024
(Agencywide Documents Access and
Management System (ADAMS)
Accession No. ML24085A808), as
supplemented by letters dated June 11
(ML24164A092), October 4
(ML24281A032), and November 20
(ML24326A142), 2024, KSU requested a
temporary exemption from Title 10 of
the Code of Federal Regulations (10
CFR) 55.53, ‘‘Conditions of licenses,’’
paragraphs (e), (f), and (h) and 10 CFR
55.59, ‘‘Requalification,’’ paragraph (a)
for three licensed senior reactor
operators (Docket Nos. 055–71404, 055–
70720, and 055–70722) at the facility in
order to allow them to resume
maintenance activities involving fuel
movement, fuel cleaning, and fuel
inspection and to return the facility to
normal operations.
The regulations at 10 CFR 55.53(e)
state:
If a licensee has not been actively
performing the functions of an operator or
senior operator, the licensee may not resume
activities authorized by a license issued
under [10 CFR part 55] except as permitted
by paragraph (f) of this section. To maintain
active status. . . [f]or test and research
reactors, the licensee shall actively perform
the functions of an operator or senior
operator for a minimum of four hours per
calendar quarter.
The regulations at 10 CFR 55.53(f)
state:
If paragraph (e) of this section is not met,
before resumption of functions authorized by
a license issued under [10 CFR part 55], an
authorized representative of the facility
licensee shall certify the following:
(1) That the qualifications and status of the
licensee are current and valid; and
(2) That the licensee has completed a
minimum of 40 hours of shift functions
under the direction of an operator or senior
operator as appropriate and in the position to
which the individual will be assigned. The
40 hours must have included a complete tour
of the plant and all required shift turnover
procedures. . . . For test and research
reactors, a minimum of six hours must have
been completed.
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The regulations at 10 CFR 55.53(h)
state:
The licensee shall complete a
requalification program as described by [10
CFR] 55.59.
And the regulations at 10 CFR
55.59(a) state:
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Each licensee shall—
(1) Successfully complete a requalification
program developed by the facility licensee
that has been approved by the Commission.
This program shall be conducted for a
continuous period not to exceed 24 months
in duration.
(2) Pass a comprehensive requalification
written examination and an annual operating
test.
(i) The written examination will sample
the items specified in [10 CFR] 55.41 and
55.43 . . ., to the extent applicable to the
facility, the licensee, and any limitation of
the license under [10 CFR] 55.53(c). . . .
(ii) The operating test will require the
operator or senior operator to demonstrate an
understanding of and the ability to perform
the actions necessary to accomplish a
comprehensive sample of items specified in
[10 CFR] 55.45(a) (2) through (13) inclusive
to the extent applicable to the facility.
(iii) In lieu of the Commission accepting a
certification by the facility licensee that the
licensee has passed written examinations and
operating tests administered by the facility
licensee within its Commission-approved
program developed by using a systems
approach to training under paragraph (c) of
this section, the Commission may administer
a comprehensive requalification written
examination and an annual operating test.
According to KSU, the facility has
been under an extended shutdown to
address a fuel issue identified during
routine fuel inspection. As a result of
the extended shutdown, three senior
operators at the facility are unable to
meet a portion of the facility’s operator
requalification program (the KSU
Requalification Plan) related to reactor
operations. Additionally, these senior
operators have not been actively
performing the functions of a senior
operator for a minimum of four hours
per calendar quarter. Therefore, KSU is
requesting to temporarily exempt these
senior operators from the NRC’s
requalification requirements at 10 CFR
55.53(h) and 10 CFR 55.59(a) and the
NRC’s active performance requirements
at 10 CFR 55.53(e) and (f) so that they
may resume fuel maintenance activities
and return the facility to normal
operations. The KSU staff will continue
to use the KSU Requalification Plan for
requalification requirements that can be
completed at the facility and those that
cannot be completed at the facility will
be accomplished through alternative
training or training at the University of
Texas at Austin Research Reactor
(UTARR). The October 4, 2024,
supplement to the exemption request
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19:45 Dec 16, 2024
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discusses this additional training,
including control manipulations at the
UTARR and simulations at the facility,
lectures, biweekly performance of
‘‘Procedure No. 12—Instrument
Checkout,’’ and monthly review of
operations daily checkout logbooks. The
requested duration of the exemption is
the sooner of 120 days after the issuance
of the exemption or 30 days following
the cancellation of the administrative
restriction on operations related to the
fuel issue. After this time, the senior
operators would again be subject to the
regulations related to the NRC’s
requalification and active performance
requirements.
As explained below, with the
proposed additional training, the
requested exemption is authorized by
law, will not endanger life or property,
and is otherwise in the public interest.
Therefore, the NRC grants the requested
exemption with respect to the three
senior operators named in the
exemption request and, pursuant to 10
CFR 55.59(b), requires those senior
operators to complete the additional
training discussed in the exemption
request and to submit evidence to the
NRC of the successful completion of
that training before returning the facility
to normal operations.
III. Discussion
Pursuant to 10 CFR 55.11, ‘‘Specific
exemptions,’’ the Commission may,
upon application by an interested
person, or upon its own initiative, grant
such exemptions from the requirements
of the regulations in 10 CFR part 55 as
it determines (1) are authorized by law,
(2) will not endanger life or property,
and (3) are otherwise in the public
interest.
A. The Exemption Is Authorized by Law
The exemption would allow three
senior operators at the facility who do
not satisfy the requalification
requirements of 10 CFR 55.53(h) and 10
CFR 55.59(a) and the active performance
requirements of 10 CFR 55.53(e) and (f)
to continue to perform the functions of
a senior operator to support the
resumption of fuel maintenance
activities and the return of the facility
to normal operations. As stated above,
10 CFR 55.11 allows the Commission to
grant exemptions from the requirements
of 10 CFR part 55, including 10 CFR
55.53(e), (f), and (h) and 10 CFR
55.59(a), when the exemptions are
authorized by law. Exemptions are
authorized by law where they are not
expressly prohibited by statute or
regulation. A proposed exemption is
implicitly authorized by law if it will
not endanger life or property and is
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otherwise in the public interest and no
other provisions in law prohibit, or
otherwise restrict, its application. The
NRC staff has determined, as explained
next, that no provisions in law expressly
prohibit or otherwise restrict the
requested exemption. The NRC staff has
also determined, as explained in
subsequent sections of this document,
that the requested exemption will not
endanger life or property and is
otherwise in the public interest.
The regulations in 10 CFR part 55
implement Section 107 of the Atomic
Energy Act of 1954, as amended (AEA),
which states, in part, that the
Commission shall (1) prescribe uniform
conditions for licensing individuals as
operators of any of the various classes
of utilization facilities licensed by the
NRC and (2) determine the
qualifications of such individuals.
These requirements in the AEA do not
expressly prohibit exemptions from 10
CFR 55.53(e), (f), and (h) and 10 CFR
55.59(a), which require licensed
operators to maintain proficiency by
actively performing the functions of an
operator for a minimum number of
hours and to complete a requalification
program. Further, as discussed below,
the requested exemption would have
little impact on the uniformity of
operator licensing conditions or on
operator qualification requirements.
In its exemption request, KSU stated
that the purpose of the exemption
request is to allow the resumption of
fuel maintenance activities, including
fuel cleaning and inspections, to
provide a pathway for returning the
facility to normal operations. This
cannot currently be accomplished
because three senior operators at the
facility do not satisfy the proficiency
and requalification requirements of the
NRC’s regulations due to the extended
shutdown of the facility. Under the
exemption, KSU would continue to use
the KSU Requalification Plan for
requalification requirements that can be
completed at the facility and those that
cannot be completed at the facility
would be satisfied by performing the
additional training described in the
request, including additional training at
the UTARR. Although fuel maintenance
activities could be resumed upon the
issuance of the exemption, pursuant to
10 CFR 55.59(b), the Commission would
require the senior operators to complete
the additional training and submit
evidence to the Commission of the
successful completion of this training
before returning the facility to normal
operations. After this, the senior
operators would again be subject to the
regulations related to the NRC’s
requalification and active performance
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requirements. Therefore, granting the
exemption request would have little
impact on the uniformity of operator
licensing conditions or on operator
qualification requirements.
Because no provisions in law
expressly prohibit the requested
exemption and because, as explained in
subsequent sections of this document,
the requested exemption will not
endanger life or property and is
otherwise in the public interest, the
NRC staff has determined that the
exemption is authorized by law.
B. The Exemption Will Not Endanger
Life or Property
The exemption would allow three
senior operators at the facility who do
not satisfy the requalification
requirements of 10 CFR 55.53(h) and 10
CFR 55.59(a) and the active performance
requirements of 10 CFR 55.53(e) and (f)
to continue to perform the functions of
a senior operator to support the
resumption of fuel maintenance
activities and the return of the facility
to normal operations. As stated above,
10 CFR 55.11 allows the Commission to
grant exemptions from the requirements
of 10 CFR part 55, including 10 CFR
55.53(e), (f), and (h) and 10 CFR
55.59(a), when they will not endanger
life or property.
The requested exemption will not
endanger life or property because it
would allow persons experienced with
licensed activities involving fuel
maintenance to resume inspections and
cleaning of the fuel with the reactor
shutdown. These activities would be
performed consistent with the facility’s
Commission-approved technical
specifications and would, therefore,
ensure that the necessary quality of
systems and components is maintained.
Further, the requested exemption will
not endanger life or property because
KSU has proposed additional training
for the three senior operators that would
provide reasonable assurance of their
competence as senior operators
regarding facility operations equivalent
to that required by the NRC’s
regulations and because that additional
training would be required by the NRC,
pursuant to 10 CFR 55.59(b), including
the submission of evidence to the
Commission of the successful
completion of the training, before the
facility is returned to normal operations.
As KSU stated in the October 4, 2024,
supplement to the exemption request,
the KSU Requalification Plan would
continue to be used, and supplemented,
for items that can be completed at the
facility, such as through training and
lectures, including biweekly
performance of ‘‘Procedure No. 12—
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19:45 Dec 16, 2024
Jkt 265001
Instrument Checkout,’’ and monthly
review of operations daily checkout
logbooks. The items in the plan that
cannot be completed at the facility, such
as control manipulations, would be
accomplished at the UTARR to satisfy
the operating test requalification
requirements of 10 CFR 55.45(a)(2), (5),
and (6). Both the UTARR and the KSU
facility have a similar licensed power.
Operations may be conducted at the
UTARR between shutdown and
designated power levels similar to the
KSU facility. Additionally, both
facilities utilize TRIGA fuel and
graphite reflection, hence operating
behavior characteristics during control
manipulations will have a similar
response.
Based on the above, the NRC staff
determined that the UTARR is
sufficiently similar to the KSU facility
such that the additional training
proposed to be conducted at the
UTARR, in combination with the
conduct of the KSU Requalification
Plan, as supplemented, at the facility,
provides reasonable assurance of the
competence of the three senior operators
to perform the functions of a senior
operator at the KSU facility. Although
fuel maintenance activities may be
resumed upon the issuance of this
exemption, pursuant to 10 CFR 55.59(b),
the senior operators must complete the
additional training discussed above and
submit evidence to the Commission of
the successful completion of this
training before returning the facility to
normal operations. Therefore, the NRC
staff has determined that the exemption
will not endanger life or property.
C. The Exemption Is Otherwise in the
Public Interest
The exemption would allow three
senior operators at the facility who do
not satisfy the requalification
requirements of 10 CFR 55.53(h) and 10
CFR 55.59(a) and the active performance
requirements of 10 CFR 55.53(e) and (f)
to continue to perform the functions of
a senior operator to support the
resumption of fuel maintenance
activities and the return of the facility
to normal operations. As stated above,
10 CFR 55.11 allows the Commission to
grant exemptions from the requirements
of 10 CFR part 55, including 10 CFR
55.53(e), (f), and (h) and 10 CFR
55.59(a), when they are otherwise in the
public interest.
The Commission’s values guide the
NRC in maintaining certain principles
of good regulation as it carries out
regulatory activities in furtherance of its
safety and security mission. These
principles focus the NRC on ensuring
safety and security while appropriately
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102169
considering the interests of the NRC’s
stakeholders, including the public and
licensees. The NRC’s principles of good
regulation can also provide guidance as
to whether the granting of a particular
exemption is otherwise in the public
interest.
On balance, the NRC’s principles of
good regulation demonstrate that the
granting of the requested exemption is
otherwise in the public interest. The
scope of the exemption is limited to
resuming fuel maintenance activities
and to returning the facility to normal
operations. The three senior operators
would be allowed to resume fuel
maintenance activities, including fuel
cleaning and inspections, upon the
issuance of the exemption; however,
pursuant to 10 CFR 55.59(b), the senior
operators would be required to complete
the additional training discussed above
and to submit evidence to the
Commission of the successful
completion of this training before
returning the facility to normal
operations. As discussed above, this
would ensure that the senior operators
have the competence required to
perform these duties. Moreover, the
exemption would expire the sooner of
120 days after the issuance of the
exemption or 30 days following the
cancellation of the administrative
restriction on operations related to the
fuel issue. After this time, the senior
operators would again be fully subject to
the regulations related to the NRC’s
requalification and active performance
requirements. Thus, the exemption is
narrowly tailored and does not make
any permanent changes to the senior
operator licenses, the facility license, or
KSU programs. This approach provides
for an efficient and clear resolution to a
situation that is outside of the
considerations of the applicable
regulations. Therefore, the NRC staff has
determined that the exemption is
otherwise in the public interest.
D. Environmental Considerations
The exemption would allow three
senior operators at the facility who do
not satisfy the requalification
requirements of 10 CFR 55.53(h) and 10
CFR 55.59(a) and the active performance
requirements of 10 CFR 55.53(e) and (f)
to continue to perform the functions of
a senior operator to support the
resumption of fuel maintenance
activities and the return of the facility
to normal operations. For the following
reasons, the NRC staff determined that
this exemption meets the eligibility
criteria for the categorical exclusion set
forth in 10 CFR 51.22(c)(25). There are
no special or extraordinary
circumstances present that would
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Federal Register / Vol. 89, No. 242 / Tuesday, December 17, 2024 / Notices
preclude reliance on this exclusion. The
NRC staff determined, in accordance
with 10 CFR 51.22(c)(25)(vi)(E), that the
requirements from which the exemption
is sought involve education, training,
experience, qualification,
requalification, or other employment
suitability requirements. The NRC staff
also determined that granting the
requested exemption involves no
significant hazards consideration
because it does not authorize any
physical changes to the facility or any
of its safety systems or change any of the
assumptions or limits used in the
facility licensee’s safety analyses or
introduce any new failure modes; there
is no significant change in the types or
significant increase in the amounts of
any effluents that may be released
offsite because the exemption does not
affect any effluent release limits as
provided in the facility licensee’s
technical specifications or by 10 CFR
part 20; there is no significant increase
in individual or cumulative public or
occupational radiation exposure
because the exemption does not affect
the limits on the release of any
radioactive material or the limits
provided in 10 CFR part 20 for radiation
exposure to workers or members of the
public; there is no significant
construction impact because the
exemption does not involve any changes
to a construction permit; and there is no
significant increase in the potential for
or consequences from radiological
accidents because the exemption does
not alter any of the assumptions or
limits in the facility licensee’s safety
analyses. In addition, the NRC staff
determined that there would be no
significant impacts to biota, water
resources, historic properties, cultural
resources, or socioeconomic conditions
in the region. Therefore, pursuant to 10
CFR 51.22(b), no environmental impact
statement or environmental assessment
need to be prepared in connection with
the granting of the exemption.
IV. Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
55.11, the exemption is authorized by
law, will not endanger life or property,
and is otherwise in the public interest.
Therefore, the Commission hereby
grants, with respect to the three senior
operators named in the exemption
request, an exemption from the NRC’s
requalification requirements at 10 CFR
55.53(h) and 10 CFR 55.59(a) and the
NRC’s active performance requirements
at 10 CFR 55.53(e) and (f) to continue
to perform the functions of a senior
operator to support the resumption of
fuel maintenance activities and the
return of the facility to normal
operations. Although fuel maintenance
activities may be resumed upon the
issuance of this exemption, pursuant to
10 CFR 55.59(b), the senior operators
must complete the additional training
discussed above and submit evidence to
the Commission of the successful
completion of this training before
returning the facility to normal
operations. This exemption expires the
sooner of (1) 120 days after issuance or
(2) 30 days following the cancellation of
the facility temporary administrative
limit/special condition for operation
stipulating in the entry on November 22,
2021, of Attachment 1, ‘‘Condition/
Limit Log,’’ in ‘‘SOM1 Operational
Limits and Special Administrative
Controls’’ that ‘‘No operation until fuel
element findings resolved.’’
This exemption is effective upon
issuance.
V. Availability of Documents
The documents identified in the
following table are related to the
requested exemption and available to
interested persons through the NRC’s
ADAMS at https://adams.nrc.gov/wba/.
Document
ADAMS accession No.
KSU letter, ‘‘License Requirements Exemption Request,’’ dated March 7, 2024. .............................................................
KSU letter, ‘‘License Requirements Exemption Request Supplemental Information,’’ dated June 11, 2024. ...................
KSU letter, ‘‘License Requirements Exemption Request Additional Supplemental Information,’’ dated October 4, 2024.
KSU letter, ‘‘License Requirements Exemption Request Further Supplemental Information,’’ dated November 20,
2024. ................................................................................................................................................................................
Dated: December 05, 2024.
/RA/
Jeremy Bowen, Director,
Division of Advanced Reactors and NonPower Production and Utilization Facilities,
Office of Nuclear Reactor Regulation.
[FR Doc. 2024–29695 Filed 12–16–24; 8:45 am]
NUCLEAR WASTE TECHNICAL
REVIEW BOARD
ddrumheller on DSK120RN23PROD with NOTICES1
Notice of Members of Senior Executive
Service Performance Review Board
This notice announces the
membership of the U.S. Nuclear Waste
Technical Review Board (NWTRB)
Senior Executive Service (SES)
Performance Review Board (PRB).
DATES: Effective immediately and until
December 10, 2025.
ADDRESSES: Send comments concerning
this notice to: U.S. Nuclear Waste
Technical Review Board, Clarendon
19:45 Dec 16, 2024
Jkt 265001
Section
4314(c)(1) through (5) of Title 5 of the
United States Code, requires each
agency to establish, in accordance with
regulations prescribed by the Office of
Personnel Management, one or more
SES Performance Review Boards.
Section 4314(c)(4) of Title 5 requires
that notice of appointment of board
members be published in the Federal
Register.
The following executives have been
designated as members of the
Performance Review Board for the U.S.
Nuclear Waste Technical Review Board:
R. Todd Davis, Associate Technical
Director, Nuclear Programs and
Analysis, Defense Nuclear Facilities
Safety Board
SUPPLEMENTARY INFORMATION:
BILLING CODE 7590–01–P
VerDate Sep<11>2014
Blvd., Suite 1300, Arlington, VA 22201–
3367.
FOR FURTHER INFORMATION CONTACT:
Kimberly Brown, Human Resources
Specialist, brown@nwtrb.gov, 703–235–
4473.
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ML24085A808
ML24164A092
ML24281A032
ML24326A142
Michael A. Mikolanis, Manager,
Savannah River Field Office, National
Nuclear Security Administration
Mark T. Sautman, Acting Deputy
Technical Director, Defense Nuclear
Facilities Safety Board
Gregory Sosson, Associate Principal
Deputy Assistant Secretary Field
Operations, Office of Environmental
Management, U.S. Department of
Energy
Christopher Roscetti, Deputy Director
for Environment, Health, and Safety,
U.S. Department of Energy
Dated: December 10, 2024.
Neysa M. Slater-Chandler,
Director of Administration, U.S. Nuclear
Waste Technical Review Board.
[FR Doc. 2024–29671 Filed 12–16–24; 8:45 am]
BILLING CODE 6820–AM–P
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Agencies
[Federal Register Volume 89, Number 242 (Tuesday, December 17, 2024)]
[Notices]
[Pages 102167-102170]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-29695]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-188; NRC-2024-0190]
Kansas State University; Exemption
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an
exemption in response to a request dated March 7, 2024, as supplemented
by letters dated June 11, October 4, and November 20, 2024, from Kansas
State University (KSU). The exemption temporarily exempts three
licensed senior reactor operators at KSU from the NRC's requirements
regarding completing the facility's requalification program and
actively performing the functions of a senior operator in order to
allow them to resume maintenance activities involving fuel movement,
fuel cleaning, and fuel inspection and to return the facility to normal
operations.
DATES: The exemption was issued on December 5, 2024.
ADDRESSES: Please refer to Docket ID NRC-2024-0190 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly available information related to this document
using any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0190. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; email: [email protected]. For technical
questions, contact the individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, please contact the NRC's Public
Document Room (PDR) reference staff at 1-800-397-4209, at 301-415-4737,
or by email to [email protected]. The exemption request dated March
7, 2024, and the supplemental letters dated June 11, and October 4, and
November 20, 2024, are available in ADAMS under Accession Nos.
ML24085A808, ML24164A092, ML24281A032, and ML24326A142, respectively.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except
Federal holidays.
FOR FURTHER INFORMATION CONTACT: Andrew Miller, telephone: 301-415-
3398; email: [email protected] and Duane Hardesty, telephone: 301-
415-3724; email: [email protected]. Both are staff of the Office
of Nuclear Reactor Regulation at the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Dated: December 12, 2024.
Duane A. Hardesty,
Senior Project Manager, Non-Power Production and Utilization Facility
Licensing Branch, Division of Advanced Reactors and Non-Power
Production and Utilization Facilities, Office of Nuclear Reactor
Regulation.
Attachment--Exemption
NUCLEAR REGULATORY COMMISSION
Docket No. 50-188
Kansas State University Nuclear Reactor Facility; Exemption
I. Background
Kansas State University (KSU) holds the U.S. Nuclear Regulatory
Commission (NRC, the Commission) Renewed Facility Operating License No.
R-88 for the Kansas State University Nuclear Reactor Facility (the
facility), which is a Training, Research, Isotopes, General Atomics
(TRIGA) research reactor located on the KSU campus in Manhattan,
Kansas. Under this license, KSU is authorized to operate the facility
at steady-state power levels up to a maximum of 1,250 kilowatts
(thermal) and in the pulse mode with reactivity insertions not to
exceed specified limits. The license is subject to the rules,
regulations, and orders of the NRC.
II. Request/Action
By letter dated March 7, 2024 (Agencywide Documents Access and
Management System (ADAMS) Accession No. ML24085A808), as supplemented
by letters dated June 11 (ML24164A092), October 4 (ML24281A032), and
November 20 (ML24326A142), 2024, KSU requested a temporary exemption
from Title 10 of the Code of Federal Regulations (10 CFR) 55.53,
``Conditions of licenses,'' paragraphs (e), (f), and (h) and 10 CFR
55.59, ``Requalification,'' paragraph (a) for three licensed senior
reactor operators (Docket Nos. 055-71404, 055-70720, and 055-70722) at
the facility in order to allow them to resume maintenance activities
involving fuel movement, fuel cleaning, and fuel inspection and to
return the facility to normal operations.
The regulations at 10 CFR 55.53(e) state:
If a licensee has not been actively performing the functions of
an operator or senior operator, the licensee may not resume
activities authorized by a license issued under [10 CFR part 55]
except as permitted by paragraph (f) of this section. To maintain
active status. . . [f]or test and research reactors, the licensee
shall actively perform the functions of an operator or senior
operator for a minimum of four hours per calendar quarter.
The regulations at 10 CFR 55.53(f) state:
If paragraph (e) of this section is not met, before resumption
of functions authorized by a license issued under [10 CFR part 55],
an authorized representative of the facility licensee shall certify
the following:
(1) That the qualifications and status of the licensee are
current and valid; and
(2) That the licensee has completed a minimum of 40 hours of
shift functions under the direction of an operator or senior
operator as appropriate and in the position to which the individual
will be assigned. The 40 hours must have included a complete tour of
the plant and all required shift turnover procedures. . . . For test
and research reactors, a minimum of six hours must have been
completed.
[[Page 102168]]
The regulations at 10 CFR 55.53(h) state:
The licensee shall complete a requalification program as
described by [10 CFR] 55.59.
And the regulations at 10 CFR 55.59(a) state:
Each licensee shall--
(1) Successfully complete a requalification program developed by
the facility licensee that has been approved by the Commission. This
program shall be conducted for a continuous period not to exceed 24
months in duration.
(2) Pass a comprehensive requalification written examination and
an annual operating test.
(i) The written examination will sample the items specified in
[10 CFR] 55.41 and 55.43 . . ., to the extent applicable to the
facility, the licensee, and any limitation of the license under [10
CFR] 55.53(c). . . .
(ii) The operating test will require the operator or senior
operator to demonstrate an understanding of and the ability to
perform the actions necessary to accomplish a comprehensive sample
of items specified in [10 CFR] 55.45(a) (2) through (13) inclusive
to the extent applicable to the facility.
(iii) In lieu of the Commission accepting a certification by the
facility licensee that the licensee has passed written examinations
and operating tests administered by the facility licensee within its
Commission-approved program developed by using a systems approach to
training under paragraph (c) of this section, the Commission may
administer a comprehensive requalification written examination and
an annual operating test.
According to KSU, the facility has been under an extended shutdown
to address a fuel issue identified during routine fuel inspection. As a
result of the extended shutdown, three senior operators at the facility
are unable to meet a portion of the facility's operator requalification
program (the KSU Requalification Plan) related to reactor operations.
Additionally, these senior operators have not been actively performing
the functions of a senior operator for a minimum of four hours per
calendar quarter. Therefore, KSU is requesting to temporarily exempt
these senior operators from the NRC's requalification requirements at
10 CFR 55.53(h) and 10 CFR 55.59(a) and the NRC's active performance
requirements at 10 CFR 55.53(e) and (f) so that they may resume fuel
maintenance activities and return the facility to normal operations.
The KSU staff will continue to use the KSU Requalification Plan for
requalification requirements that can be completed at the facility and
those that cannot be completed at the facility will be accomplished
through alternative training or training at the University of Texas at
Austin Research Reactor (UTARR). The October 4, 2024, supplement to the
exemption request discusses this additional training, including control
manipulations at the UTARR and simulations at the facility, lectures,
biweekly performance of ``Procedure No. 12--Instrument Checkout,'' and
monthly review of operations daily checkout logbooks. The requested
duration of the exemption is the sooner of 120 days after the issuance
of the exemption or 30 days following the cancellation of the
administrative restriction on operations related to the fuel issue.
After this time, the senior operators would again be subject to the
regulations related to the NRC's requalification and active performance
requirements.
As explained below, with the proposed additional training, the
requested exemption is authorized by law, will not endanger life or
property, and is otherwise in the public interest. Therefore, the NRC
grants the requested exemption with respect to the three senior
operators named in the exemption request and, pursuant to 10 CFR
55.59(b), requires those senior operators to complete the additional
training discussed in the exemption request and to submit evidence to
the NRC of the successful completion of that training before returning
the facility to normal operations.
III. Discussion
Pursuant to 10 CFR 55.11, ``Specific exemptions,'' the Commission
may, upon application by an interested person, or upon its own
initiative, grant such exemptions from the requirements of the
regulations in 10 CFR part 55 as it determines (1) are authorized by
law, (2) will not endanger life or property, and (3) are otherwise in
the public interest.
A. The Exemption Is Authorized by Law
The exemption would allow three senior operators at the facility
who do not satisfy the requalification requirements of 10 CFR 55.53(h)
and 10 CFR 55.59(a) and the active performance requirements of 10 CFR
55.53(e) and (f) to continue to perform the functions of a senior
operator to support the resumption of fuel maintenance activities and
the return of the facility to normal operations. As stated above, 10
CFR 55.11 allows the Commission to grant exemptions from the
requirements of 10 CFR part 55, including 10 CFR 55.53(e), (f), and (h)
and 10 CFR 55.59(a), when the exemptions are authorized by law.
Exemptions are authorized by law where they are not expressly
prohibited by statute or regulation. A proposed exemption is implicitly
authorized by law if it will not endanger life or property and is
otherwise in the public interest and no other provisions in law
prohibit, or otherwise restrict, its application. The NRC staff has
determined, as explained next, that no provisions in law expressly
prohibit or otherwise restrict the requested exemption. The NRC staff
has also determined, as explained in subsequent sections of this
document, that the requested exemption will not endanger life or
property and is otherwise in the public interest.
The regulations in 10 CFR part 55 implement Section 107 of the
Atomic Energy Act of 1954, as amended (AEA), which states, in part,
that the Commission shall (1) prescribe uniform conditions for
licensing individuals as operators of any of the various classes of
utilization facilities licensed by the NRC and (2) determine the
qualifications of such individuals. These requirements in the AEA do
not expressly prohibit exemptions from 10 CFR 55.53(e), (f), and (h)
and 10 CFR 55.59(a), which require licensed operators to maintain
proficiency by actively performing the functions of an operator for a
minimum number of hours and to complete a requalification program.
Further, as discussed below, the requested exemption would have little
impact on the uniformity of operator licensing conditions or on
operator qualification requirements.
In its exemption request, KSU stated that the purpose of the
exemption request is to allow the resumption of fuel maintenance
activities, including fuel cleaning and inspections, to provide a
pathway for returning the facility to normal operations. This cannot
currently be accomplished because three senior operators at the
facility do not satisfy the proficiency and requalification
requirements of the NRC's regulations due to the extended shutdown of
the facility. Under the exemption, KSU would continue to use the KSU
Requalification Plan for requalification requirements that can be
completed at the facility and those that cannot be completed at the
facility would be satisfied by performing the additional training
described in the request, including additional training at the UTARR.
Although fuel maintenance activities could be resumed upon the issuance
of the exemption, pursuant to 10 CFR 55.59(b), the Commission would
require the senior operators to complete the additional training and
submit evidence to the Commission of the successful completion of this
training before returning the facility to normal operations. After
this, the senior operators would again be subject to the regulations
related to the NRC's requalification and active performance
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requirements. Therefore, granting the exemption request would have
little impact on the uniformity of operator licensing conditions or on
operator qualification requirements.
Because no provisions in law expressly prohibit the requested
exemption and because, as explained in subsequent sections of this
document, the requested exemption will not endanger life or property
and is otherwise in the public interest, the NRC staff has determined
that the exemption is authorized by law.
B. The Exemption Will Not Endanger Life or Property
The exemption would allow three senior operators at the facility
who do not satisfy the requalification requirements of 10 CFR 55.53(h)
and 10 CFR 55.59(a) and the active performance requirements of 10 CFR
55.53(e) and (f) to continue to perform the functions of a senior
operator to support the resumption of fuel maintenance activities and
the return of the facility to normal operations. As stated above, 10
CFR 55.11 allows the Commission to grant exemptions from the
requirements of 10 CFR part 55, including 10 CFR 55.53(e), (f), and (h)
and 10 CFR 55.59(a), when they will not endanger life or property.
The requested exemption will not endanger life or property because
it would allow persons experienced with licensed activities involving
fuel maintenance to resume inspections and cleaning of the fuel with
the reactor shutdown. These activities would be performed consistent
with the facility's Commission-approved technical specifications and
would, therefore, ensure that the necessary quality of systems and
components is maintained.
Further, the requested exemption will not endanger life or property
because KSU has proposed additional training for the three senior
operators that would provide reasonable assurance of their competence
as senior operators regarding facility operations equivalent to that
required by the NRC's regulations and because that additional training
would be required by the NRC, pursuant to 10 CFR 55.59(b), including
the submission of evidence to the Commission of the successful
completion of the training, before the facility is returned to normal
operations. As KSU stated in the October 4, 2024, supplement to the
exemption request, the KSU Requalification Plan would continue to be
used, and supplemented, for items that can be completed at the
facility, such as through training and lectures, including biweekly
performance of ``Procedure No. 12--Instrument Checkout,'' and monthly
review of operations daily checkout logbooks. The items in the plan
that cannot be completed at the facility, such as control
manipulations, would be accomplished at the UTARR to satisfy the
operating test requalification requirements of 10 CFR 55.45(a)(2), (5),
and (6). Both the UTARR and the KSU facility have a similar licensed
power. Operations may be conducted at the UTARR between shutdown and
designated power levels similar to the KSU facility. Additionally, both
facilities utilize TRIGA fuel and graphite reflection, hence operating
behavior characteristics during control manipulations will have a
similar response.
Based on the above, the NRC staff determined that the UTARR is
sufficiently similar to the KSU facility such that the additional
training proposed to be conducted at the UTARR, in combination with the
conduct of the KSU Requalification Plan, as supplemented, at the
facility, provides reasonable assurance of the competence of the three
senior operators to perform the functions of a senior operator at the
KSU facility. Although fuel maintenance activities may be resumed upon
the issuance of this exemption, pursuant to 10 CFR 55.59(b), the senior
operators must complete the additional training discussed above and
submit evidence to the Commission of the successful completion of this
training before returning the facility to normal operations. Therefore,
the NRC staff has determined that the exemption will not endanger life
or property.
C. The Exemption Is Otherwise in the Public Interest
The exemption would allow three senior operators at the facility
who do not satisfy the requalification requirements of 10 CFR 55.53(h)
and 10 CFR 55.59(a) and the active performance requirements of 10 CFR
55.53(e) and (f) to continue to perform the functions of a senior
operator to support the resumption of fuel maintenance activities and
the return of the facility to normal operations. As stated above, 10
CFR 55.11 allows the Commission to grant exemptions from the
requirements of 10 CFR part 55, including 10 CFR 55.53(e), (f), and (h)
and 10 CFR 55.59(a), when they are otherwise in the public interest.
The Commission's values guide the NRC in maintaining certain
principles of good regulation as it carries out regulatory activities
in furtherance of its safety and security mission. These principles
focus the NRC on ensuring safety and security while appropriately
considering the interests of the NRC's stakeholders, including the
public and licensees. The NRC's principles of good regulation can also
provide guidance as to whether the granting of a particular exemption
is otherwise in the public interest.
On balance, the NRC's principles of good regulation demonstrate
that the granting of the requested exemption is otherwise in the public
interest. The scope of the exemption is limited to resuming fuel
maintenance activities and to returning the facility to normal
operations. The three senior operators would be allowed to resume fuel
maintenance activities, including fuel cleaning and inspections, upon
the issuance of the exemption; however, pursuant to 10 CFR 55.59(b),
the senior operators would be required to complete the additional
training discussed above and to submit evidence to the Commission of
the successful completion of this training before returning the
facility to normal operations. As discussed above, this would ensure
that the senior operators have the competence required to perform these
duties. Moreover, the exemption would expire the sooner of 120 days
after the issuance of the exemption or 30 days following the
cancellation of the administrative restriction on operations related to
the fuel issue. After this time, the senior operators would again be
fully subject to the regulations related to the NRC's requalification
and active performance requirements. Thus, the exemption is narrowly
tailored and does not make any permanent changes to the senior operator
licenses, the facility license, or KSU programs. This approach provides
for an efficient and clear resolution to a situation that is outside of
the considerations of the applicable regulations. Therefore, the NRC
staff has determined that the exemption is otherwise in the public
interest.
D. Environmental Considerations
The exemption would allow three senior operators at the facility
who do not satisfy the requalification requirements of 10 CFR 55.53(h)
and 10 CFR 55.59(a) and the active performance requirements of 10 CFR
55.53(e) and (f) to continue to perform the functions of a senior
operator to support the resumption of fuel maintenance activities and
the return of the facility to normal operations. For the following
reasons, the NRC staff determined that this exemption meets the
eligibility criteria for the categorical exclusion set forth in 10 CFR
51.22(c)(25). There are no special or extraordinary circumstances
present that would
[[Page 102170]]
preclude reliance on this exclusion. The NRC staff determined, in
accordance with 10 CFR 51.22(c)(25)(vi)(E), that the requirements from
which the exemption is sought involve education, training, experience,
qualification, requalification, or other employment suitability
requirements. The NRC staff also determined that granting the requested
exemption involves no significant hazards consideration because it does
not authorize any physical changes to the facility or any of its safety
systems or change any of the assumptions or limits used in the facility
licensee's safety analyses or introduce any new failure modes; there is
no significant change in the types or significant increase in the
amounts of any effluents that may be released offsite because the
exemption does not affect any effluent release limits as provided in
the facility licensee's technical specifications or by 10 CFR part 20;
there is no significant increase in individual or cumulative public or
occupational radiation exposure because the exemption does not affect
the limits on the release of any radioactive material or the limits
provided in 10 CFR part 20 for radiation exposure to workers or members
of the public; there is no significant construction impact because the
exemption does not involve any changes to a construction permit; and
there is no significant increase in the potential for or consequences
from radiological accidents because the exemption does not alter any of
the assumptions or limits in the facility licensee's safety analyses.
In addition, the NRC staff determined that there would be no
significant impacts to biota, water resources, historic properties,
cultural resources, or socioeconomic conditions in the region.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment need to be prepared in connection
with the granting of the exemption.
IV. Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
55.11, the exemption is authorized by law, will not endanger life or
property, and is otherwise in the public interest. Therefore, the
Commission hereby grants, with respect to the three senior operators
named in the exemption request, an exemption from the NRC's
requalification requirements at 10 CFR 55.53(h) and 10 CFR 55.59(a) and
the NRC's active performance requirements at 10 CFR 55.53(e) and (f) to
continue to perform the functions of a senior operator to support the
resumption of fuel maintenance activities and the return of the
facility to normal operations. Although fuel maintenance activities may
be resumed upon the issuance of this exemption, pursuant to 10 CFR
55.59(b), the senior operators must complete the additional training
discussed above and submit evidence to the Commission of the successful
completion of this training before returning the facility to normal
operations. This exemption expires the sooner of (1) 120 days after
issuance or (2) 30 days following the cancellation of the facility
temporary administrative limit/special condition for operation
stipulating in the entry on November 22, 2021, of Attachment 1,
``Condition/Limit Log,'' in ``SOM1 Operational Limits and Special
Administrative Controls'' that ``No operation until fuel element
findings resolved.''
This exemption is effective upon issuance.
V. Availability of Documents
The documents identified in the following table are related to the
requested exemption and available to interested persons through the
NRC's ADAMS at https://adams.nrc.gov/wba/.
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Document ADAMS accession No.
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KSU letter, ``License Requirements Exemption ML24085A808
Request,'' dated March 7, 2024................
KSU letter, ``License Requirements Exemption ML24164A092
Request Supplemental Information,'' dated June
11, 2024......................................
KSU letter, ``License Requirements Exemption ML24281A032
Request Additional Supplemental Information,''
dated October 4, 2024.........................
KSU letter, ``License Requirements Exemption ML24326A142
Request Further Supplemental Information,''
dated November 20, 2024.......................
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Dated: December 05, 2024.
/RA/
Jeremy Bowen, Director,
Division of Advanced Reactors and Non-Power Production and
Utilization Facilities, Office of Nuclear Reactor Regulation.
[FR Doc. 2024-29695 Filed 12-16-24; 8:45 am]
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