Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2, 37965-37968 [2020-13651]
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Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices
Written comments may be submitted
during the draft EIS comment period as
described in the ADDRESSES section of
the document.
The NRC cautions you not to include
identifying or contact information that
you do not want to be publicly
disclosed in your comment submission.
The NRC posts all comment
submissions at https://
www.regulations.gov and enters all
comment submissions into ADAMS.
The NRC does not routinely edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information that
they do not want to be publicly
disclosed in their comment submission
because the NRC does not routinely edit
comment submissions before making
the comment submissions available to
the public or entering the comment
submissions into ADAMS.
On March 20, 2020 (85 FR 16150), the
NRC issued for public comment a draft
EIS for Holtec’s application to construct
and operate a CISF for SNF and GTCC
waste. The draft EIS for Holtec’s license
application includes the preliminary
analysis that evaluates the
environmental impacts of the proposed
action and alternatives to the proposed
action. After comparing the impacts of
the proposed action (Phase 1) to the NoAction alternative, the NRC staff, in
accordance with the requirements in
part 51 of title 10 of the Codes of
Federal Regulations, recommends the
proposed action (Phase 1), which is the
issuance of an NRC license for 40 years
to Holtec to construct and operate a
CISF for SNF at the proposed location.
In addition, the Bureau of Land
Management (BLM) staff recommends
the issuance of a permit to construct and
operate the rail spur. This
recommendation is based on (i) the
license application, which includes an
environmental report and supplemental
documents, and Holtec’s responses to
the NRC staff’s requests for additional
Date
Time
7/09/2020 ........
5:00 p.m. to 9:00 p.m. (EDT) or 3:00 p.m. to 7:00 p.m. (MDT)
Persons interested in attending this
meeting should monitor the NRC’s
Public Meeting Schedule website at
https://www.nrc.gov/pmns/mtg for
additional information, agenda for the
meeting, information on how to provide
verbal comments, and access
information for the meeting.
Participants should register in advance
of the meeting by visiting the website
(https://usnrc.webex.com) and using the
event number provided above. A
confirmation email will be generated
providing additional details and a link
to the meeting. Those wishing to make
verbal comments at the meeting should
follow instructions listed on the NRC’s
Public Meeting Schedule website.
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II. Discussion
Dated: June 18, 2020.
For the Nuclear Regulatory Commission.
Diana B. Diaz Toro,
Acting Chief, Environmental Review Materials
Branch, Division of Rulemaking,
Environmental, and Financial Support, Office
of Nuclear Material Safety, and Safeguards.
[FR Doc. 2020–13590 Filed 6–23–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–254 and 50–265; NRC–
2020–0143]
Exelon Generation Company, LLC and
MidAmerican Energy Company Quad
Cities Nuclear Power Station, Units 1
and 2
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
AGENCY:
Jkt 250001
PO 00000
III. Meeting Information
The NRC staff will hold a public
webinar on July 9, 2020 to receive
comments on the draft EIS for Holtec’s
application to construct and operate a
CISF. The webinar will be held online
and will offer a telephone line for
members of the public to submit
comments. A court reporter will be
recording all comments received during
the webinar. The dates and times for the
public webinar are as follow:
WEBINAR INFORMATION:
Webinar address:
https://usnrc.webex.com/.
Event Number: 199 943 8370.
Password: HOLTEC.
TELEPHONE ACCESS:
Telephone number: 800–475–0220.
Telephone passcode: 9575497.
The U.S. Nuclear Regulatory
Commission (NRC) has issued an
exemption in response to a July 22,
18:20 Jun 23, 2020
information; (ii) consultation with
Federal, State, Tribal, local agencies,
and input from other stakeholders; (iii)
independent NRC and BLM staff review;
and (iv) the assessments provided in the
EIS.
The public comment period was
originally scheduled to close on May 22,
2020. The NRC has decided to extend
the public comment until September 22,
2020 to allow more time for members of
the public to submit their comments.
Comments of Federal, State, and local
agencies, Indian Tribes or other
interested persons will be made
available for public inspection when
received.
Location
SUMMARY:
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2019, request from Exelon Generation
Company, LLC, from certain regulatory
requirements in order to permit
exclusion of main steam isolation valve
(MSIV) leakage from the overall
integrated leak rate Type A test
measurement and MSIV pathway
leakage contributions from the
combined leakage rate of all
penetrations and valves subject to Type
B and Type C tests.
DATES: The exemption was issued on
June 18, 2020.
ADDRESSES: Please refer to Docket ID
NRC–2020–0143 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–2020–0143. Address
questions about NRC docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
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Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices
Jennifer.Borges@nrc.gov. For technical
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable 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, 301–
415–4737, or by email to pdr.resource@
nrc.gov. The ADAMS accession number
for each document referenced (if it is
available in ADAMS) is provided the
first time that it is mentioned in this
document.
FOR FURTHER INFORMATION CONTACT:
Robert F. Kuntz, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
3733, email: Robert.Kuntz@nrc.gov.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated: June 19, 2020.
For the Nuclear Regulatory Commission.
Russell S. Haskell,
Project Manager, Plant Licensing Branch III,
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
Attachment—Exemption
NUCLEAR REGULATORY COMMISSION
Docket Nos. 50–254 and 50–265
Exelon Generation Company, LLC and
MidAmerican Energy Company Quad Cities
Nuclear Power Station, Units 1 and 2
Exemption
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I. Background
Exelon Generation Company, LLC (EGC,
the licensee) and MidAmerican Energy
Company are the holders of Facility
Operating License Nos. DPR–29 and DPR–30,
which authorize operation of the Quad Cities
Nuclear Power Station (QCNPS), Units 1 and
2. The licenses provide, among other things,
that the facilities are subject to the rules,
regulations, and orders of the U.S. Nuclear
Regulatory Commission (NRC, the
Commission) now or hereafter in effect. The
facilities each consist of a boiling, light-water
reactor located in Rock Island County,
Illinois.
II. Request/Action
In its letter dated March 5, 2019
(Agencywide Documents and Access
Management System (ADAMS) Accession
No. ML19064B369), as supplemented by
letters dated May 23, 2019 (ADAMS
Accession No. ML19143A347), July 22, 2019
(ADAMS Accession No. ML19203A176),
February 24, 2020 (ADAMS Accession No.
ML20055E826), and March 31, 2020
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(ADAMS Accession No., ML20091H576) EGC
requested a permanent exemption from the
Part 50 of Title 10 of the Code of Federal
Regulations (10 CFR), Appendix J, Option B,
Section III.A requirements in order to permit
exclusion of main steam isolation valve
(MSIV) leakage from the overall integrated
leak rate Type A test measurement, and from
Option B, Section III.B, requirements in order
to permit exclusion of the MSIV pathway
leakage contributions from the combined
leakage rate of all penetrations and valves
subject to Type B and Type C tests. The
letters also requested license amendments to
revise Technical Specification (TS) 3.6.1.3,
‘‘Primary Containment Isolation Valves
(PCIVs),’’ Surveillance Requirement (SR)
3.6.1.3.10 that would increase the single and
combined MSIV leakage rate limits; add a
new TS 3.6.2.6, ‘‘Residual Heat Removal
(RHR) Drywell Spray,’’ to reflect the crediting
of drywell spray for fission product removal;
and revise TS 3.6.4.1, ‘‘Secondary
Containment,’’ SR 3.6.4.1.1 to address shortduration conditions during which the
secondary containment pressure may not
meet the SR pressure requirement at QCNPS,
Units 1 and 2. The license amendment
requests are addressed separately.
Under Part 50 of 10 CFR, paragraph
50.54(o), primary reactor containments for
water-cooled power reactors are subject to
the requirements of Appendix J to 10 CFR
part 50. Appendix J specifies the leakage rate
test requirements, schedules, and acceptance
criteria for tests of the leak-tight integrity of
the reactor containment, and systems and
components that penetrate the containment.
Option B of 10 CFR 50, Appendix J,
‘‘Performance-Based Requirements,’’
paragraph III.A, ‘‘Type A Test,’’ requires,
among other things, that the overall
integrated leakage rate must not exceed the
allowable leakage rate (La) with margin, as
specified in the TSs. The overall integrated
leakage rate is defined in 10 CFR part 50,
Appendix J, as ‘‘the total leakage rate through
all tested leakage paths, including
containment welds, valves, fittings, and
components that penetrate the containment
system.’’ This includes the contribution
through the four main steam (MS) lines
where each line contains two MSIVs in
series. Paragraph III.B, ‘‘Type B and C Tests,’’
requires, among other things, that the sum of
the leakage rates of Type B and Type C local
leakage rate tests be less than the
performance criterion (La) with margin as
specified in the TSs. The allowable leakage
rates set in the TSs ensure that the required
dose limits, such as in 10 CFR 50.67,
‘‘Accident source term,’’ will not be
exceeded.
This requested exemption concerns the MS
system, which penetrates containment. The
licensee requested this exemption because
the MS pathway leakage is treated separately
from the remainder of the assumed leakage
from primary containment in the design basis
loss of coolant accident (LOCA) analysis. The
radiological consequences of MSIV leakage
are modeled as a separate primary
containment release path to the environment
that bypasses secondary containment, and
therefore, it is not filtered through the
standby gas treatment system like other
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containment leakage. The design basis LOCA
dose calculation assumes all MSIV leakage
migrates to the turbine building and then to
the environment. By currently including the
MS pathway leakage with the rest of the
primary containment leakage test results, it is
being accounted for twice—once as part of
the actual containment leakage and again as
part of the MSIV leakage used in the LOCA
dose calculations.
III. Discussion
Pursuant to 10 CFR 50.12, the Commission
may, upon application by any interested
person or upon its own initiative, grant
exemptions from the requirements of 10 CFR
part 50 when (1) the exemptions are
authorized by law, will not present an undue
risk to public health or safety, and are
consistent with the common defense and
security; and (2) when special circumstances
as described in 10 CFR 50.12(a)(2)(i)–(vi) are
present. The licensee asserted that special
circumstances are present under 10 CFR
50.12(a)(2)(ii) (stating that the application of
the regulation in the particular circumstances
would not serve the underlying purpose of
the rule or is not necessary to achieve the
underlying purpose of the rule).
The licensee’s exemption request was
submitted with license amendments request
to increase the allowable MSIV leakage rate.
The exemption and amendments together
will permit an increase in allowable MSIV
leakage rate that is excluded from the overall
integrated leak rate Type A test measurement
and excluded from the combined Type B and
Type C test total. The licensee described its
view on the special circumstances associated
with the MSIV leakage path testing in its
application dated July 22, 2019.
A. The Exemption Is Authorized by Law
This exemption permits exclusion of the
MSIV pathway leakage contribution from the
overall integrated leakage rate Type A test
measurement and from the combined leakage
rate of all penetrations and valves subject to
Type B and Type C tests. As stated above, 10
CFR 50.12 allows the NRC to grant
exemptions from the requirements of 10 CFR
part 50. The NRC staff has determined that
granting of the licensee’s proposed
exemption will not result in a violation of the
Atomic Energy Act of 1954, as amended, or
the Commission’s regulations. Therefore, the
exemption is authorized by law.
B. The Exemption Presents No Undue Risk to
Public Health and Safety
Type A tests to measure the containment
system overall integrated leakage rate must
be conducted under conditions representing
design basis LOCA containment peak
pressure. Type B pneumatic tests to detect
and measure local leakage rates across
pressure retaining, leakage-limiting
boundaries, and Type C pneumatic tests to
measure containment isolation valve leakage
rates, must be conducted to ensure the
integrity of the overall containment system as
a barrier to fission product release to reduce
the risk from reactor accidents.
In license Amendment Nos. 233 and
Amendment 229 (ADAMS Accession No.
ML062070290), the NRC approved the use of
the alternative source term (AST) (as
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prescribed in 10 CFR 50.67) in the
calculations of the radiological dose
consequences of design basis accidents
(DBAs), including the design basis LOCA, for
QCNPS, Units 1 and 2. The NRC staff safety
evaluation accompanying these amendments
acknowledged that once fission products are
dispersed in the primary containment, their
release to the environment is assumed to
occur through three pathways: (1) The
leakage of primary containment atmosphere;
(2) the leakage of primary containment
atmosphere through MSIVs; and (3) the
leakage from emergency core cooling systems
that recirculate suppression pool water
outside of the primary containment. As noted
above, however, leakage through the MSIVs
is considered a separate pathway and is
calculated as a separate contributor to the
dose consequence analysis. As such, the
inclusion of MSIV leakage as part of Type A
and as part of Type B and C test results is
not necessary to ensure the actual
radiological consequences of DBAs remain
below the regulatory limit.
The proposed exemption does not create
any new accident precursors. Therefore, the
probability of postulated accidents is not
increased. Also, the consequences of
postulated accidents are not significantly
changed from the previously evaluated
consequences associated with the design
basis LOCA as described in the AST
amendments. Therefore, there is no undue
risk to public health and safety.
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C. The Exemption Is Consistent With the
Common Defense and Security
The proposed exemption excludes the
MSIV pathway leakage contribution from the
overall integrated leakage rate Type A test
measurement and from the combined leakage
rate of all penetrations and valves subject to
Type B and Type C tests. This change to
accounting for leakage rate measurement has
no relation to security issues. Therefore, the
exemption is consistent with the common
defense and security.
D. Special Circumstances
Under 10 CFR 50.12(a)(2)(ii) special
circumstances include when, ‘‘[a]pplication
of the regulation in the particular
circumstances would not serve the
underlying purpose of the rule or is not
necessary to achieve the underlying purpose
of the rule.’’
The test requirements in Appendix J to 10
CFR part 50 ensure that leakage through
containments or systems and components
penetrating containments does not exceed
allowable leakage rates specified in the
technical specifications, and integrity of the
containment structure is maintained during
its service life. Option B of Appendix J
identifies the performance-based
requirements and criteria for preoperational
and subsequent periodic leakage-rate testing.
The licensee has analyzed the MS pathway
leakage separately from the overall
containment integrated leakage; the local
leakage across pressure-containing or
leakage-limiting boundaries; and the
containment isolation valve leakage in its
dose consequence analyses. The dose
consequences were found to be within the
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applicable acceptance criteria in 10 CFR
50.67, ‘‘Accident source term,’’ and the
guidance of NRC Regulatory Guide 1.183,
‘‘Alternative Radiological Source Terms for
Evaluating Design Basis Accidents [DBAs] at
Nuclear Power Reactors,’’ dated July 2000
(ADAMS Accession No. ML003716792). The
staff has reviewed the licensee’s analysis and
determined that the dose consequences of
implementing the proposed change are below
the applicable acceptance criteria and the
containment leaks will continue to be limited
by the QCNPS, Units 1 and 2, TSs.
Therefore, because the underlying
purposes of 10 CFR part 50, Appendix J, is
still achieved, the special circumstances
required by 10 CFR 50.12(a)(2)(ii) for the
granting of an exemption from 10 CFR part
50, Appendix J, Option B, Sections lII.A and
III.B, exist.
E. Environmental Considerations
The NRC staff determined that the issuance
of the requested exemption meets the
provisions of categorical exclusion 10 CFR
51.22(c)(25) because: (i) No significant
hazards consideration; (ii) no significant
change in the types or significant increase in
the amounts of any effluents that may be
released offsite; (iii) no significant increase in
individual or cumulative public or
occupational radiation exposure; (iv) there is
no significant construction impact; (v) there
is no significant increase in the potential for
or consequences from radiological accidents;
and (vi) the requirements from which an
exemption is sought involve e.g., inspection
or surveillance requirements. Therefore, in
accordance with 10 CFR 51.22(b), no
environmental impact statement or
environmental assessment need be prepared
in connection with the NRC’s issuance of this
exemption. The basis for the NRC staff’s
determination is provided in the following
evaluation of the requirements in 10 CFR
51.22(c)(25)(i)–(vi).
Requirements in 10 CFR 51.22(c)(25)(i)
To qualify for a categorical exclusion under
10 CFR 51.22(c)(25)(i), the exemption must
involve ‘‘no significant hazards
consideration.’’ The NRC staff evaluated
whether the exemption involves no
significant hazards consideration by using
the standards in 10 CFR 50.92(c), as
presented below:
1. Does the requested exemption involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The proposed exemption would permit
exclusion of the MSIV pathway leakage
contribution from the overall integrated
leakage rate Type A test measurement and
from the sum of the leakage rates from Type
B and Type C tests. The leakage of primary
containment atmosphere through MSIVs is
accounted for as a separate contributor to the
design basis LOCA dose consequence
analysis. This exemption will allow the
leakage testing to be performed in a manner
consistent with the way MSIV leakage is
modeled in the revised radiological
consequence analysis included as part of the
related license amendment requests (LARs)
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37967
submitted in the letter dated March 5, 2019
as supplemented by the letters dated March
23, 2019, February 24, 2020, and March 31,
2020. This change to the leakage rate
measurement does not increase the
probability or consequences of an accident
previously evaluated.
Therefore, the exemption does not involve
a significant increase in the probability or
consequences of an accident previously
evaluated.
2. Does the requested exemption create the
possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
The proposed exemption does not involve
a physical modification to the plant (i.e., no
new or different type of equipment will be
installed and there are no physical
modifications to existing equipment
associated with the proposed change).
Similarly, it does not physically change any
structures, systems, or components involved
in the mitigation of any accidents.
Therefore, the exemption does not create
the possibility of a new or different kind of
accident from any accident previously
evaluated.
3. Does the requested exemption involve a
significant reduction in a margin of safety?
Response: No.
The proposed exemption does not
alter a design basis or safety limit nor
cause a limit to be exceeded. The
proposed exemption allows the results
of the TS required MSIV leakage
pathway tests to no longer be accounted
for as part of the overall integrated
leakage rate Type A test measurement
and as part of the sum of the local
leakage rates from Type B and Type C
tests. This change only affects which
leakage rates are included in the Types
A, B, and C results. This exemption will
allow the leakage testing to be
performed in a manner consistent with
the way MSIV leakage is modeled in the
revised radiological consequence
analysis submitted as part of the related
LAR.
Therefore, the exemption does not
involve a significant reduction in a
margin of safety.
Based on the evaluation above, the
NRC staff has determined that the
proposed exemption involves no
significant hazards consideration.
Therefore, the requirements of 10 CFR
51.22(c)(25)(i) are met.
Requirements in 10 CFR 51.22(c)(9)(ii)
To qualify for a categorical exclusion
under 10 CFR 51.22(c)(25)(ii), the
exemption must result in ‘‘no significant
change in the types or significant
increase in the amounts of any effluents
that may be released offsite.’’ The
proposed exemption allows the results
of the TS-required MSIV leakage
pathway tests to be accounted for only
as part of the design basis LOCA
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consequence analysis. This change only
affects the total in which the leakage
rates are included and does not change
the frequency or pressure at which the
testing must be performed. The
underlying purpose of 10 CFR part 50,
Appendix J, is to demonstrate by
periodic testing and visual inspection
that the primary reactor containment
will be able to perform its function of
providing an essentially leak-tight
barrier against uncontrolled release of
radioactivity to the environment. The
inclusion of the MSIV leakage testing
results in the design basis LOCA serves
the same purpose as the inclusion in the
rate Type A test measurement and the
sum of the leakage rates from Type B
and Type C tests required by Appendix
J, Option B, paragraphs III.A and III.B.
Therefore, the proposed exemption will
not significantly change the types of
effluents that may be released offsite, or
significantly increase the amount of
effluents that may be released offsite.
Therefore, the requirements of 10 CFR
51.22(c)(25)(ii) are met.
Requirements in 10 CFR 51.22(c)(9)(iii)
To qualify for a categorical exclusion
under 10 CFR 51.22(c)(25)(iii), the
exemption must result in ‘‘no significant
increase in individual or cumulative
public or occupational radiation
exposure.’’ The proposed exemption
permits the exclusion of the MSIV
leakage pathway results from the Type
A test measurement and the sum of the
leakage rates from Type B and Type C
tests required by Appendix J, Option B,
paragraphs III.A and III.B, and has no
impact on, or change to, fuel or core
design. Additionally, the TSs still
require that the MSIV leakage rates be
tested and maintained below set limits.
As such, the calculated public and
occupational doses will remain
essentially the same. Therefore, the
proposed exemption will not
significantly increase individual or
cumulative public or occupational
radiation exposure. Therefore, the
requirements of 10 CFR 51.22(c)(25)(iii)
are met.
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Requirement in 10 CFR 51.22(c)(25)(iv)
To qualify for a categorical exclusion
under 10 CFR 51.22(c)(25)(iv), the
exemption must result in ‘‘no significant
construction impact.’’ The exemption
does not propose any changes to the
site, alter the site, or change the
operation of the site. Therefore, there is
no significant construction impact.
Therefore, the requirements of 10 CFR
51.22(c)(25)(iv) are met.
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Requirement in 10 CFR 51.22(c)(25)(v)
To qualify for a categorical exclusion
under 10 CFR 51.22(c)(25)(v), the
exemption must involve ‘‘no significant
increase in the potential for or
consequences from radiological
accidents.’’ The proposed exemption
does not remove the requirement to
perform leakage rate testing of the
MSIVs. This exemption will allow the
leakage testing to be performed in a
manner consistent with the way MSIV
leakage is modeled in the revised
radiological consequence analysis
submitted as part of the related LAR.
Therefore, this change to the leakage
rate measurement does not result in a
significant increase in the potential for
or consequences from radiological
accidents. Therefore, the requirements
of 10 CFR 51.22(c)(25)(v) are met.
Requirement in 10 CFR 51.22(c)(25)(vi)
To qualify for a categorical exclusion
under 10 CFR 51.22(c)(25)(vi)(C), the
exemption must involve inspection or
surveillance requirements. The
exemption seeks to permit exclusion of
the MSIV leakage from the overall
integrated leak rate Type A test
measurement and the combined leakage
rate of all penetrations and valves
subject to Type B and Type C tests
required by Appendix J to 10 CFR part
50. Appendix J specifies the leakage rate
test requirements, schedules, and
acceptance criteria for tests of the leaktight integrity of the reactor
containment, and systems and
components that penetrate the
containment. Therefore, the exemption
involves a surveillance requirement.
Therefore, the requirements of 10 CFR
51.22(c)(25)(vi) are met.
Conclusion
Based on the above, the NRC staff
concludes that the proposed exemption
meets the eligibility criteria for the
categorical exclusion set forth in 10 CFR
51.22(c)(25). Therefore, in accordance
with 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared in
connection with the NRC’s issuance of
this exemption.
IV. Conclusions
Accordingly, the NRC has determined
that, pursuant to 10 CFR 50.12, the
exemption is authorized by law, will not
present an undue risk to the public
health and safety, and is consistent with
the common defense and security. Also,
special circumstances are present.
Therefore, the NRC hereby grants EGC a
permanent exemption (1) from the
requirements of 10 CFR part 50,
Appendix J, Option B, Section III.A, to
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allow exclusion of the MSIV pathway
leakage from the overall integrated
leakage rate measured when performing
a Type A test; and (2) from the
requirements of 10 CFR part 50,
Appendix J, Option B, Section III.B, to
allow exclusion of the MSIV pathway
leakage from the combined leakage rate
of all penetrations and valves subject to
Types B and C tests for QCNPS, Units
1 and 2.
This exemption is effective upon
issuance.
Dated: 18th day of June 2020.
For the Nuclear Regulatory Commission
Craig G. Erlanger,
Director, Division of Operating Reactor
Licensing Office of Nuclear Reactor
Regulation.
[FR Doc. 2020–13651 Filed 6–23–20; 8:45 am]
BILLING CODE 7590–01–P
POSTAL REGULATORY COMMISSION
[Docket Nos. MC2020–179 and CP2020–203;
MC2020–180 and CP2020–204]
New Postal Products
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
The Commission is noticing a
recent Postal Service filing for the
Commission’s consideration concerning
negotiated service agreements. This
notice informs the public of the filing,
invites public comment, and takes other
administrative steps.
DATES: Comments are due: June 25,
2020.
SUMMARY:
Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Those who cannot submit
comments electronically should contact
the person identified in the FOR FURTHER
INFORMATION CONTACT section by
telephone for advice on filing
alternatives.
ADDRESSES:
FOR FURTHER INFORMATION CONTACT:
David A. Trissell, General Counsel, at
202–789–6820.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Introduction
II. Docketed Proceeding(s)
I. Introduction
The Commission gives notice that the
Postal Service filed request(s) for the
Commission to consider matters related
to negotiated service agreement(s). The
request(s) may propose the addition or
removal of a negotiated service
agreement from the market dominant or
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]]>Agencies
[Federal Register Volume 85, Number 122 (Wednesday, June 24, 2020)]
[Notices]
[Pages 37965-37968]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-13651]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-254 and 50-265; NRC-2020-0143]
Exelon Generation Company, LLC and MidAmerican Energy Company
Quad Cities Nuclear Power Station, Units 1 and 2
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an
exemption in response to a July 22, 2019, request from Exelon
Generation Company, LLC, from certain regulatory requirements in order
to permit exclusion of main steam isolation valve (MSIV) leakage from
the overall integrated leak rate Type A test measurement and MSIV
pathway leakage contributions from the combined leakage rate of all
penetrations and valves subject to Type B and Type C tests.
DATES: The exemption was issued on June 18, 2020.
ADDRESSES: Please refer to Docket ID NRC-2020-0143 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-2020-0143. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email:
[[Page 37966]]
[email protected]. For technical questions, contact the
individual 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, 301-415-4737, or
by email to [email protected]. The ADAMS accession number for each
document referenced (if it is available in ADAMS) is provided the first
time that it is mentioned in this document.
FOR FURTHER INFORMATION CONTACT: Robert F. Kuntz, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-3733, email: [email protected].
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Dated: June 19, 2020.
For the Nuclear Regulatory Commission.
Russell S. Haskell,
Project Manager, Plant Licensing Branch III, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
Attachment--Exemption
NUCLEAR REGULATORY COMMISSION
Docket Nos. 50-254 and 50-265
Exelon Generation Company, LLC and MidAmerican Energy Company Quad
Cities Nuclear Power Station, Units 1 and 2
Exemption
I. Background
Exelon Generation Company, LLC (EGC, the licensee) and
MidAmerican Energy Company are the holders of Facility Operating
License Nos. DPR-29 and DPR-30, which authorize operation of the
Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The
licenses provide, among other things, that the facilities are
subject to the rules, regulations, and orders of the U.S. Nuclear
Regulatory Commission (NRC, the Commission) now or hereafter in
effect. The facilities each consist of a boiling, light-water
reactor located in Rock Island County, Illinois.
II. Request/Action
In its letter dated March 5, 2019 (Agencywide Documents and
Access Management System (ADAMS) Accession No. ML19064B369), as
supplemented by letters dated May 23, 2019 (ADAMS Accession No.
ML19143A347), July 22, 2019 (ADAMS Accession No. ML19203A176),
February 24, 2020 (ADAMS Accession No. ML20055E826), and March 31,
2020 (ADAMS Accession No., ML20091H576) EGC requested a permanent
exemption from the Part 50 of Title 10 of the Code of Federal
Regulations (10 CFR), Appendix J, Option B, Section III.A
requirements in order to permit exclusion of main steam isolation
valve (MSIV) leakage from the overall integrated leak rate Type A
test measurement, and from Option B, Section III.B, requirements in
order to permit exclusion of the MSIV pathway leakage contributions
from the combined leakage rate of all penetrations and valves
subject to Type B and Type C tests. The letters also requested
license amendments to revise Technical Specification (TS) 3.6.1.3,
``Primary Containment Isolation Valves (PCIVs),'' Surveillance
Requirement (SR) 3.6.1.3.10 that would increase the single and
combined MSIV leakage rate limits; add a new TS 3.6.2.6, ``Residual
Heat Removal (RHR) Drywell Spray,'' to reflect the crediting of
drywell spray for fission product removal; and revise TS 3.6.4.1,
``Secondary Containment,'' SR 3.6.4.1.1 to address short-duration
conditions during which the secondary containment pressure may not
meet the SR pressure requirement at QCNPS, Units 1 and 2. The
license amendment requests are addressed separately.
Under Part 50 of 10 CFR, paragraph 50.54(o), primary reactor
containments for water-cooled power reactors are subject to the
requirements of Appendix J to 10 CFR part 50. Appendix J specifies
the leakage rate test requirements, schedules, and acceptance
criteria for tests of the leak-tight integrity of the reactor
containment, and systems and components that penetrate the
containment. Option B of 10 CFR 50, Appendix J, ``Performance-Based
Requirements,'' paragraph III.A, ``Type A Test,'' requires, among
other things, that the overall integrated leakage rate must not
exceed the allowable leakage rate (La) with margin, as
specified in the TSs. The overall integrated leakage rate is defined
in 10 CFR part 50, Appendix J, as ``the total leakage rate through
all tested leakage paths, including containment welds, valves,
fittings, and components that penetrate the containment system.''
This includes the contribution through the four main steam (MS)
lines where each line contains two MSIVs in series. Paragraph III.B,
``Type B and C Tests,'' requires, among other things, that the sum
of the leakage rates of Type B and Type C local leakage rate tests
be less than the performance criterion (La) with margin
as specified in the TSs. The allowable leakage rates set in the TSs
ensure that the required dose limits, such as in 10 CFR 50.67,
``Accident source term,'' will not be exceeded.
This requested exemption concerns the MS system, which
penetrates containment. The licensee requested this exemption
because the MS pathway leakage is treated separately from the
remainder of the assumed leakage from primary containment in the
design basis loss of coolant accident (LOCA) analysis. The
radiological consequences of MSIV leakage are modeled as a separate
primary containment release path to the environment that bypasses
secondary containment, and therefore, it is not filtered through the
standby gas treatment system like other containment leakage. The
design basis LOCA dose calculation assumes all MSIV leakage migrates
to the turbine building and then to the environment. By currently
including the MS pathway leakage with the rest of the primary
containment leakage test results, it is being accounted for twice--
once as part of the actual containment leakage and again as part of
the MSIV leakage used in the LOCA dose calculations.
III. Discussion
Pursuant to 10 CFR 50.12, the Commission may, upon application
by any interested person or upon its own initiative, grant
exemptions from the requirements of 10 CFR part 50 when (1) the
exemptions are authorized by law, will not present an undue risk to
public health or safety, and are consistent with the common defense
and security; and (2) when special circumstances as described in 10
CFR 50.12(a)(2)(i)-(vi) are present. The licensee asserted that
special circumstances are present under 10 CFR 50.12(a)(2)(ii)
(stating that the application of the regulation in the particular
circumstances would not serve the underlying purpose of the rule or
is not necessary to achieve the underlying purpose of the rule).
The licensee's exemption request was submitted with license
amendments request to increase the allowable MSIV leakage rate. The
exemption and amendments together will permit an increase in
allowable MSIV leakage rate that is excluded from the overall
integrated leak rate Type A test measurement and excluded from the
combined Type B and Type C test total. The licensee described its
view on the special circumstances associated with the MSIV leakage
path testing in its application dated July 22, 2019.
A. The Exemption Is Authorized by Law
This exemption permits exclusion of the MSIV pathway leakage
contribution from the overall integrated leakage rate Type A test
measurement and from the combined leakage rate of all penetrations
and valves subject to Type B and Type C tests. As stated above, 10
CFR 50.12 allows the NRC to grant exemptions from the requirements
of 10 CFR part 50. The NRC staff has determined that granting of the
licensee's proposed exemption will not result in a violation of the
Atomic Energy Act of 1954, as amended, or the Commission's
regulations. Therefore, the exemption is authorized by law.
B. The Exemption Presents No Undue Risk to Public Health and Safety
Type A tests to measure the containment system overall
integrated leakage rate must be conducted under conditions
representing design basis LOCA containment peak pressure. Type B
pneumatic tests to detect and measure local leakage rates across
pressure retaining, leakage-limiting boundaries, and Type C
pneumatic tests to measure containment isolation valve leakage
rates, must be conducted to ensure the integrity of the overall
containment system as a barrier to fission product release to reduce
the risk from reactor accidents.
In license Amendment Nos. 233 and Amendment 229 (ADAMS Accession
No. ML062070290), the NRC approved the use of the alternative source
term (AST) (as
[[Page 37967]]
prescribed in 10 CFR 50.67) in the calculations of the radiological
dose consequences of design basis accidents (DBAs), including the
design basis LOCA, for QCNPS, Units 1 and 2. The NRC staff safety
evaluation accompanying these amendments acknowledged that once
fission products are dispersed in the primary containment, their
release to the environment is assumed to occur through three
pathways: (1) The leakage of primary containment atmosphere; (2) the
leakage of primary containment atmosphere through MSIVs; and (3) the
leakage from emergency core cooling systems that recirculate
suppression pool water outside of the primary containment. As noted
above, however, leakage through the MSIVs is considered a separate
pathway and is calculated as a separate contributor to the dose
consequence analysis. As such, the inclusion of MSIV leakage as part
of Type A and as part of Type B and C test results is not necessary
to ensure the actual radiological consequences of DBAs remain below
the regulatory limit.
The proposed exemption does not create any new accident
precursors. Therefore, the probability of postulated accidents is
not increased. Also, the consequences of postulated accidents are
not significantly changed from the previously evaluated consequences
associated with the design basis LOCA as described in the AST
amendments. Therefore, there is no undue risk to public health and
safety.
C. The Exemption Is Consistent With the Common Defense and Security
The proposed exemption excludes the MSIV pathway leakage
contribution from the overall integrated leakage rate Type A test
measurement and from the combined leakage rate of all penetrations
and valves subject to Type B and Type C tests. This change to
accounting for leakage rate measurement has no relation to security
issues. Therefore, the exemption is consistent with the common
defense and security.
D. Special Circumstances
Under 10 CFR 50.12(a)(2)(ii) special circumstances include when,
``[a]pplication of the regulation in the particular circumstances
would not serve the underlying purpose of the rule or is not
necessary to achieve the underlying purpose of the rule.''
The test requirements in Appendix J to 10 CFR part 50 ensure
that leakage through containments or systems and components
penetrating containments does not exceed allowable leakage rates
specified in the technical specifications, and integrity of the
containment structure is maintained during its service life. Option
B of Appendix J identifies the performance-based requirements and
criteria for preoperational and subsequent periodic leakage-rate
testing.
The licensee has analyzed the MS pathway leakage separately from
the overall containment integrated leakage; the local leakage across
pressure-containing or leakage-limiting boundaries; and the
containment isolation valve leakage in its dose consequence
analyses. The dose consequences were found to be within the
applicable acceptance criteria in 10 CFR 50.67, ``Accident source
term,'' and the guidance of NRC Regulatory Guide 1.183,
``Alternative Radiological Source Terms for Evaluating Design Basis
Accidents [DBAs] at Nuclear Power Reactors,'' dated July 2000 (ADAMS
Accession No. ML003716792). The staff has reviewed the licensee's
analysis and determined that the dose consequences of implementing
the proposed change are below the applicable acceptance criteria and
the containment leaks will continue to be limited by the QCNPS,
Units 1 and 2, TSs.
Therefore, because the underlying purposes of 10 CFR part 50,
Appendix J, is still achieved, the special circumstances required by
10 CFR 50.12(a)(2)(ii) for the granting of an exemption from 10 CFR
part 50, Appendix J, Option B, Sections lII.A and III.B, exist.
E. Environmental Considerations
The NRC staff determined that the issuance of the requested
exemption meets the provisions of categorical exclusion 10 CFR
51.22(c)(25) because: (i) No significant hazards consideration; (ii)
no significant change in the types or significant increase in the
amounts of any effluents that may be released offsite; (iii) no
significant increase in individual or cumulative public or
occupational radiation exposure; (iv) there is no significant
construction impact; (v) there is no significant increase in the
potential for or consequences from radiological accidents; and (vi)
the requirements from which an exemption is sought involve e.g.,
inspection or surveillance requirements. Therefore, in accordance
with 10 CFR 51.22(b), no environmental impact statement or
environmental assessment need be prepared in connection with the
NRC's issuance of this exemption. The basis for the NRC staff's
determination is provided in the following evaluation of the
requirements in 10 CFR 51.22(c)(25)(i)-(vi).
Requirements in 10 CFR 51.22(c)(25)(i)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(i), the exemption must involve ``no significant hazards
consideration.'' The NRC staff evaluated whether the exemption
involves no significant hazards consideration by using the standards
in 10 CFR 50.92(c), as presented below:
1. Does the requested exemption involve a significant increase
in the probability or consequences of an accident previously
evaluated?
Response: No.
The proposed exemption would permit exclusion of the MSIV
pathway leakage contribution from the overall integrated leakage
rate Type A test measurement and from the sum of the leakage rates
from Type B and Type C tests. The leakage of primary containment
atmosphere through MSIVs is accounted for as a separate contributor
to the design basis LOCA dose consequence analysis. This exemption
will allow the leakage testing to be performed in a manner
consistent with the way MSIV leakage is modeled in the revised
radiological consequence analysis included as part of the related
license amendment requests (LARs) submitted in the letter dated
March 5, 2019 as supplemented by the letters dated March 23, 2019,
February 24, 2020, and March 31, 2020. This change to the leakage
rate measurement does not increase the probability or consequences
of an accident previously evaluated.
Therefore, the exemption does not involve a significant increase
in the probability or consequences of an accident previously
evaluated.
2. Does the requested exemption create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed exemption does not involve a physical modification
to the plant (i.e., no new or different type of equipment will be
installed and there are no physical modifications to existing
equipment associated with the proposed change). Similarly, it does
not physically change any structures, systems, or components
involved in the mitigation of any accidents.
Therefore, the exemption does not create the possibility of a
new or different kind of accident from any accident previously
evaluated.
3. Does the requested exemption involve a significant reduction
in a margin of safety?
Response: No.
The proposed exemption does not alter a design basis or safety
limit nor cause a limit to be exceeded. The proposed exemption allows
the results of the TS required MSIV leakage pathway tests to no longer
be accounted for as part of the overall integrated leakage rate Type A
test measurement and as part of the sum of the local leakage rates from
Type B and Type C tests. This change only affects which leakage rates
are included in the Types A, B, and C results. This exemption will
allow the leakage testing to be performed in a manner consistent with
the way MSIV leakage is modeled in the revised radiological consequence
analysis submitted as part of the related LAR.
Therefore, the exemption does not involve a significant reduction
in a margin of safety.
Based on the evaluation above, the NRC staff has determined that
the proposed exemption involves no significant hazards consideration.
Therefore, the requirements of 10 CFR 51.22(c)(25)(i) are met.
Requirements in 10 CFR 51.22(c)(9)(ii)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(ii), the exemption must result in ``no significant change
in the types or significant increase in the amounts of any effluents
that may be released offsite.'' The proposed exemption allows the
results of the TS-required MSIV leakage pathway tests to be accounted
for only as part of the design basis LOCA
[[Page 37968]]
consequence analysis. This change only affects the total in which the
leakage rates are included and does not change the frequency or
pressure at which the testing must be performed. The underlying purpose
of 10 CFR part 50, Appendix J, is to demonstrate by periodic testing
and visual inspection that the primary reactor containment will be able
to perform its function of providing an essentially leak-tight barrier
against uncontrolled release of radioactivity to the environment. The
inclusion of the MSIV leakage testing results in the design basis LOCA
serves the same purpose as the inclusion in the rate Type A test
measurement and the sum of the leakage rates from Type B and Type C
tests required by Appendix J, Option B, paragraphs III.A and III.B.
Therefore, the proposed exemption will not significantly change the
types of effluents that may be released offsite, or significantly
increase the amount of effluents that may be released offsite.
Therefore, the requirements of 10 CFR 51.22(c)(25)(ii) are met.
Requirements in 10 CFR 51.22(c)(9)(iii)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(iii), the exemption must result in ``no significant
increase in individual or cumulative public or occupational radiation
exposure.'' The proposed exemption permits the exclusion of the MSIV
leakage pathway results from the Type A test measurement and the sum of
the leakage rates from Type B and Type C tests required by Appendix J,
Option B, paragraphs III.A and III.B, and has no impact on, or change
to, fuel or core design. Additionally, the TSs still require that the
MSIV leakage rates be tested and maintained below set limits. As such,
the calculated public and occupational doses will remain essentially
the same. Therefore, the proposed exemption will not significantly
increase individual or cumulative public or occupational radiation
exposure. Therefore, the requirements of 10 CFR 51.22(c)(25)(iii) are
met.
Requirement in 10 CFR 51.22(c)(25)(iv)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(iv), the exemption must result in ``no significant
construction impact.'' The exemption does not propose any changes to
the site, alter the site, or change the operation of the site.
Therefore, there is no significant construction impact. Therefore, the
requirements of 10 CFR 51.22(c)(25)(iv) are met.
Requirement in 10 CFR 51.22(c)(25)(v)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(v), the exemption must involve ``no significant increase
in the potential for or consequences from radiological accidents.'' The
proposed exemption does not remove the requirement to perform leakage
rate testing of the MSIVs. This exemption will allow the leakage
testing to be performed in a manner consistent with the way MSIV
leakage is modeled in the revised radiological consequence analysis
submitted as part of the related LAR. Therefore, this change to the
leakage rate measurement does not result in a significant increase in
the potential for or consequences from radiological accidents.
Therefore, the requirements of 10 CFR 51.22(c)(25)(v) are met.
Requirement in 10 CFR 51.22(c)(25)(vi)
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(vi)(C), the exemption must involve inspection or
surveillance requirements. The exemption seeks to permit exclusion of
the MSIV leakage from the overall integrated leak rate Type A test
measurement and the combined leakage rate of all penetrations and
valves subject to Type B and Type C tests required by Appendix J to 10
CFR part 50. Appendix J specifies the leakage rate test requirements,
schedules, and acceptance criteria for tests of the leak-tight
integrity of the reactor containment, and systems and components that
penetrate the containment. Therefore, the exemption involves a
surveillance requirement. Therefore, the requirements of 10 CFR
51.22(c)(25)(vi) are met.
Conclusion
Based on the above, the NRC staff concludes that the proposed
exemption meets the eligibility criteria for the categorical exclusion
set forth in 10 CFR 51.22(c)(25). Therefore, in accordance with 10 CFR
51.22(b), no environmental impact statement or environmental assessment
need be prepared in connection with the NRC's issuance of this
exemption.
IV. Conclusions
Accordingly, the NRC has determined that, pursuant to 10 CFR 50.12,
the exemption is authorized by law, will not present an undue risk to
the public health and safety, and is consistent with the common defense
and security. Also, special circumstances are present. Therefore, the
NRC hereby grants EGC a permanent exemption (1) from the requirements
of 10 CFR part 50, Appendix J, Option B, Section III.A, to allow
exclusion of the MSIV pathway leakage from the overall integrated
leakage rate measured when performing a Type A test; and (2) from the
requirements of 10 CFR part 50, Appendix J, Option B, Section III.B, to
allow exclusion of the MSIV pathway leakage from the combined leakage
rate of all penetrations and valves subject to Types B and C tests for
QCNPS, Units 1 and 2.
This exemption is effective upon issuance.
Dated: 18th day of June 2020.
For the Nuclear Regulatory Commission
Craig G. Erlanger,
Director, Division of Operating Reactor Licensing Office of Nuclear
Reactor Regulation.
[FR Doc. 2020-13651 Filed 6-23-20; 8:45 am]
BILLING CODE 7590-01-P
