Florida Power and Light Company, St. Lucie Plant, Unit No. 2, Exemption, 26793-26795 [2012-10928]
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Federal Register / Vol. 77, No. 88 / Monday, May 7, 2012 / Notices
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–389; NRC–2011–0194]
Florida Power and Light Company, St.
Lucie Plant, Unit No. 2, Exemption
1.0
Background
The Florida Power & Light Company
(FPL, the licensee) is the holder of
Renewed Facility Operating License No.
NPF–16, which authorizes operation of
St. Lucie Plant, Unit No. 2 (St. Lucie,
Unit 2). The license provides, among
other things, that the facility is subject
to all rules, regulations, and orders of
the U.S. Nuclear Regulatory
Commission (NRC or the Commission)
now or hereafter in effect. The facility
consists of two pressurized-water
reactors located in Jensen Beach,
Florida. However, this exemption is
applicable only to St. Lucie, Unit 2.
By letter dated April 28, 2011
(Agencywide Documents Access and
Management System (ADAMS)
Accession No. ML11119A136), the
licensee submitted a request for an
exemption from Title 10 of the Code of
Federal Regulations (10 CFR) Part 50,
Appendix G, to implement a revision of
the pressure-temperature (P–T)
operating limits for St. Lucie, Unit 2. In
requesting the revisions to the P–T
operating limits, the licensee referenced
a topical report with a methodology for
the P–T curves that did not meet some
of the requirements of 10 CFR part 50,
Appendix G, thus requiring the
exemption pursuant to 10 CFR 50.12.
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2.0
Request/Action
Part 50 of 10 CFR, Appendix G,
‘‘Fracture Toughness Requirements,’’
which is invoked by 10 CFR 50.60,
requires that P–T limits be established
for the reactor coolant pressure
boundary during normal operating and
hydrostatic or leak rate testing
conditions. Specifically, 10 CFR part 50,
Appendix G, Section IV.A.2, states that
‘‘[t]he appropriate requirements on both
the pressure-temperature limits and the
minimum permissible temperature must
be met for all conditions,’’ and ‘‘[t]he
pressure-temperature limits identified
as ‘ASME [American Society for
Mechanical Engineers] Appendix G
limits’ in [T]able 3 require that the
limits must be at least as conservative as
limits obtained by following the
methods of analysis and the margins of
safety of Appendix G of Section XI of
the ASME Code [Boiler and Pressure
Vessel Code].’’ The regulations in 10
CFR part 50, Appendix G also specify
the use of the applicable editions and
addenda of the ASME Code, Section XI,
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which are incorporated by reference in
10 CFR 50.55a. In the 2009 Edition of
10 CFR, the 1977 Edition through the
2004 Edition of the ASME Code, Section
XI, are incorporated by reference in 10
CFR 50.55a. Finally, 10 CFR 50.60(b)
states that, ‘‘[p]roposed alternatives to
the described requirements in
Append[ix] G of this part or portions
thereof may be used when an exemption
is granted by the Commission under
[10 CFR] 50.12.’’
In its January 23, 2008, LAR to
implement the current St. Lucie 2
technical specification (TS) P–T limits,
the licensee provided the technical basis
document for developing these P–T
limits, Westinghouse Commercial
Atomic Power report WCAP–16817–NP,
Revision 2, ‘‘St. Lucie Unit 2 RCS
[reactor coolant system] Pressure and
Temperature Limits and Low
Temperature Overpressure Protection
Report for 55 Effective Full Power
Years’’ (ADAMS Accession No.
ML080290135). WCAP–16817–NP,
Revision 2, references Combustion
Engineering (CE) Owners Group Topical
Report CE NPSD–683–A, Revision 6,
‘‘Development of a RCS Pressure and
Temperature Limits Report (PTLR) for
the Removal of P–T Limits and LTOP
Requirements from the Technical
Specifications’’ (ADAMS Accession No.
ML011350387), as the methodology for
determining the P–T limits. While
WCAP–16917–NP, Revision 2, did not
develop a separate PTLR for removal of
the P–T limits from the St. Lucie 2 TSs,
this report did utilize the methodology
of CE NPSD–683–A, Revision 6, as the
basis for calculating the P–T limits
currently established in the St. Lucie 2
TSs. Use of the CE topical report
requires an exemption.
By letter dated April 28, 2011, the
licensee requested an exemption from
10 CFR part 50, Appendix G, consistent
with the requirements of 10 CFR 50.12
and 50.60, to apply the KIm calculational
methodology of CE NPSD–683–A,
Revision 6, in the development of the
St. Lucie, Unit 2, P–T limits. If a
licensee proposes to use the
methodology in CE NPSD–683–A,
Revision 6, for the calculation of KIm, an
exemption is required since the
methodology for the calculation of KIm
values in CE NPSD–683–A, Revision 6,
cannot be shown to be equally or more
conservative than the methodology for
the determination of KIm provided in
editions and addenda of the ASME
Code, Section XI, Appendix G, through
the 2004 Edition.
The NRC staff evaluated the specific
PTLR methodology in CE NPSD–683,
Revision 6. This evaluation was
documented in the NRC safety
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26793
evaluation (SE) of March 16, 2001
(ADAMS Accession No. ML010780017),
which specified additional licensee
actions that are necessary to support a
licensee’s adoption of CE NPSD–683,
Revision 6. The final approved version
of this report was reissued as CE NPSD–
683–A, Revision 6, which included the
NRC SE and the required additional
action items as an attachment to the
report. One of the additional specified
actions (#21) stated, ‘‘(applicable only if
the CE NSSS [nuclear steam supply
system] methods for calculating KIm and
KIt factors, as stated in Section 5.4 of CE
NPSD–683, Revision 6, are being used
as the basis for generating the P–T limits
for their facilities) [licensees will need
to] apply for an exemption against
requirements of Section IV.A.2. of
Appendix G to Part 50 to apply the CE
NSSS methods to their P–T curves.’’
The action item further stated,
‘‘Exemption requests to apply the CE
NSSS to the generation of P–T limit
curves should be submitted pursuant to
the provision of 10 CFR 50.60(b) and
will be evaluated on a case-by-case basis
against the exemption request
acceptance criteria of 10 CFR 50.12.’’
An exemption to use the methodology
of CE NPSD–683–A to calculate the KIt
factors is no longer necessary because
editions and addenda of the ASME
Code, Section XI, that have been
incorporated by reference into 10 CFR
50.55a subsequent to the issuance of the
final SE of CE NPSD–683–A, allow
methods for determining the KIt factors
that are equivalent to the methods
described in CE NPSD–683–A.
During the NRC staff’s review of CE
NPSD–683, Revision 6, the NRC staff
evaluated the KIm calculational
methodology of that report versus the
methodologies for the calculation of KIm
given in the ASME Code, Section XI,
Appendix G. In the NRC’s March 16,
2001, SE., the staff noted, ‘‘[t]he CE
NSSS methodology does not invoke the
methods in the 1995 edition of
Appendix G to the Code for calculating
KIm factors, and instead applies FEM
[finite element modeling] methods for
estimating the KIm factors for the RPV
[reactor pressure vessel] shell * * * the
staff has determined that the KIm
calculation methods apply FEM
modeling that is similar to that used for
the determination of the KIt factors [as
codified in the ASME Code, Section XI,
Appendix G]. The staff has also
determined that there is only a slight
non-conservative difference between the
P–T limits generated from the 1989
edition of [the ASME Code, Section XI,]
Appendix G to the Code and those
generated from CE NSSS methodology
as documented in [CE/ABB] Evaluation
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Federal Register / Vol. 77, No. 88 / Monday, May 7, 2012 / Notices
No. 063–PENG–ER–096, Revision 00,
[‘Technical Methodology Paper
Comparing ABB/CE PT Curve to ASME
Section III, Appendix G,’ dated January
22, 1998 (ADAMS Accession No.
ML100500514, nonproprietary version)].
The staff considers this difference to be
reasonable and should be consistent
with the expected improvements in P–
T generation methods that have been
incorporated into the 1995 edition of
Appendix G to the Code.’’ This
conclusion regarding the comparison
between the CE NSSS methodology and
the 1995 Edition of the ASME Code,
Section XI, Appendix G, methodology
also applies to the 2004 Edition of the
ASME Code, Section XI, Appendix G,
methodology because there were no
significant changes in the method of
calculating the KIm factors required by
the ASME Code, Section XI, Appendix
G, between the 1995 edition (through
1996 addenda) and the 2004 editions of
the ASME Code. In summary, the staff
concluded in its March 16, 2001, SE that
the calculation of KIm using the CE
NPSD–683, Revision 6 methodology
would lead to the development of P–T
limit curves that may be slightly
nonconservative with respect to those
that would be calculated using the
ASME Code, Section XI, Appendix G,
methods, and that such a difference was
to be expected with the development of
more refined calculational techniques.
Furthermore, the staff concluded in its
March 16, 2001, SE that P–T limit
curves that would be developed using
the methodology of CE NPSD–683,
Revision 6, would be adequate for
protecting the RPV from brittle fracture
under all normal operating and
hydrostatic/leak test conditions.
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3.0 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, are consistent with the
common defense and security; and (2)
when special circumstances are present.
Authorized by Law
This exemption allows the use of an
alternative methodology for calculating
flaw stress intensity factors in the RPV
due to membrane stress from pressure
loadings in lieu of meeting the
requirements in 10 CFR 50.60 and 10
CFR part 50, Appendix G. As stated
above, 10 CFR 50.12 allows the NRC to
grant exemptions from the requirements
of 10 CFR part 50. In addition, the
granting of the exemption will not result
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18:11 May 04, 2012
Jkt 226001
in violation of the Atomic Energy Act of
1954, as amended, or the Commission’s
regulations. Therefore, the exemption is
authorized by law.
No Undue Risk to Public Health and
Safety
The underlying purpose of 10 CFR
50.60 and 10 CFR part 50, Appendix G,
is to provide an acceptable margin of
safety against brittle failure of the RCS
during any condition of normal
operation to which the pressure
boundary may be subjected over its
service lifetime. Appropriate P–T limits
are necessary to achieve this underlying
purpose. The licensee’s alternative
methodology for establishing the P–T
limits and the LTOP setpoints is
described in CE NPSD–683–A, Revision
6, which has been approved by the NRC
staff. Based on the above, no new
accident precursors are created by using
the alternative methodology. Thus, the
probability of postulated accidents will
not increase. Also, based on the above,
the consequences of postulated
accidents will not increase. In addition,
the licensee used an NRC-approved
methodology for establishing P–T limits
and minimum permissible temperatures
for the RPV. Therefore, there is no
undue risk to the public health and
safety.
Consistent With Common Defense and
Security
The exemption results in changes to
the plant by allowing an alternative
methodology for calculating flaw stress
intensity factors in the RPV. This
change to the calculation of stress
intensity factors in the RPV material has
no negative implications for security
issues. Therefore, this exemption is
consistent with the common defense
and security.
Special Circumstances
Special circumstances, pursuant to
10 CFR 50.12(a)(2)(ii), are present in
that continued operation of St. Lucie,
Unit 2, with P–T limit curves developed
in accordance with the ASME Code,
Section XI, Appendix G, is not
necessary to achieve the underlying
purpose of 10 CFR part 50, Appendix G.
Application of the KIm calculational
methodology of CE NPSD–683–A,
Revision 6, in lieu of the calculational
methodology specified in the ASME
Code, Section XI, Appendix G, provides
an acceptable alternative evaluation
procedure that will continue to meet the
underlying purpose of 10 CFR part 50,
Appendix G. The underlying purpose of
the regulations in 10 CFR part 50,
Appendix G, is to provide an acceptable
margin of safety against brittle failure of
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Frm 00070
Fmt 4703
Sfmt 4703
the reactor coolant system during any
condition of normal operation to which
the pressure boundary may be subjected
over its service lifetime.
Based on the staff’s March 16, 2001,
SE regarding CE NPSD–683, Revision 6,
and the licensee’s rationale to support
the exemption request, the staff
determined that an exemption is
required to approve the use of the KIm
calculational methodology of CE NPSD–
683–A, Revision 6. By letter dated
January 29, 2009, in response to the
licensee’s January 23, 2008, LAR, the
NRC staff issued an SE that provided its
review of the licensee’s calculations in
WCAP–16917–NP, Revision 2, which
referenced CE NPSD–683–A, Revision 6.
Informed by these previous evaluations,
the staff concludes that the application
of the KIm calculational methodology of
CE NPSD–683–A, Revision 6, for St.
Lucie, Unit 2, provides sufficient margin
in the development of RPV P–T limit
curves such that the underlying purpose
of the regulations (10 CFR part 50,
Appendix G) continues to be met.
Therefore, the NRC staff concludes that
the exemption requested by the licensee
is justified based on the special
circumstances of 10 CFR 50.12(a)(2)(ii),
‘‘[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.’’ Based
upon a consideration of the
conservatism that is incorporated into
the methodologies of 10 CFR part 50,
Appendix G, and ASME Code, Section
XI, Appendix G, the staff concludes that
application of the KIm calculational
methodology of CE NPSD–683–A,
Revision 6, as described, would provide
an adequate margin of safety against
brittle failure of the RPV. Therefore, the
staff concludes that the exemption is
appropriate under the special
circumstances of 10 CFR 50.12(a)(2)(ii),
and that the application of the KIm
calculational methodology of CE NPSD–
683–A, Revision 6, is acceptable for use
as the basis for generating the St. Lucie,
Unit 2, P–T limits.
4.0 Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), 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 under 10 CFR
50.12(a)(2)(ii). Therefore, the
Commission hereby grants FPL an
exemption from the requirements of 10
CFR part 50, Appendix G, to allow
application of the KIm calculational
E:\FR\FM\07MYN1.SGM
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Federal Register / Vol. 77, No. 88 / Monday, May 7, 2012 / Notices
methodology of CE NPSD–683–A,
Revision 6, as the basis for the St. Lucie,
Unit 2, P–T limits.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (76 FR 53497;
August 26, 2011). This exemption is
effective upon issuance.
Dated at Rockville, Maryland, this 30th day
of April 2012.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2012–10928 Filed 5–4–12; 8:45 am]
BILLING CODE 7590–01–P
POSTAL REGULATORY COMMISSION
[Docket No. MC2012–13; Order No. 1328]
Product List Changes
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
The Commission is noticing a
recently-filed Postal Service request to
remove Parcel Post from the market
dominant product list and to add a
nearly identical ‘‘Parcel Post’’ to the
competitive product list. Alaska Bypass
Service would remain on the market
dominant product list. This notice
addresses procedural steps associated
with this filing.
DATES: Comments are due: May 31,
2012.
Reply Comments are due: June 15,
2012.
ADDRESSES: Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Commenters who cannot
submit their views electronically should
contact the person identified in FOR
FURTHER INFORMATION CONTACT by
telephone for advice on alternatives to
electronic filing.
FOR FURTHER INFORMATION CONTACT:
Stephen L. Sharfman, General Counsel,
stephen.sharfman@prc.gov or 202–789–
6820.
SUPPLEMENTARY INFORMATION: On April
26, 2012, the Postal Service filed a
notice with the Commission under 39
U.S.C. 3642 and 39 CFR 3020.30 et seq.
requesting that certain changes be made
to the market dominant and competitive
product lists.1 Specifically, the Postal
Service proposes to (1) remove Parcel
sroberts on DSK5SPTVN1PROD with NOTICES
SUMMARY:
1 Request of the United States Postal Service to
Transfer Parcel Post to the Competitive Product
List, April 26, 2012 (Request).
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Jkt 226001
Post from the market dominant product
list; (2) add ‘‘Parcel Post,’’ a nearly
identical product, to the competitive
product list; and (3) leave Alaska Bypass
Service, which is currently part of
Parcel Post, on the market dominant
product list.2 Id. at 1.
Parcel Post is an economical ground
package delivery service for less-thanurgent and oversize packages that
competes with comparable products
offered by competitors. Id. at 1–2. The
Postal Service asserts that Parcel Post
fulfills all criteria for competitive
products under 39 U.S.C. 3642. Id. at 2.
It requests that Parcel Post be removed
from the market dominant product list
and that a similar product called Parcel
Post be added to the competitive
product list. The Postal Service states
that the new competitive Parcel Post
product would be nearly identical to the
current Parcel Post offering, except that
Alaska Bypass Service would remain on
the market dominant product list. Id.
Supporting materials. To support its
Request, the Postal Service filed the
following attachments:
• Attachment A—Resolution of the
Governors of the United States Postal
Service, March 21, 2012 (Resolution No.
12–02);
• Attachment B—Statement of
Supporting Justification; and
• Attachment C—Proposed Mail
Classification Schedule changes.
In its Statement of Supporting
Justification, the Postal Service states
that Alaska shippers will still have
access to Alaska Bypass Service on the
market dominant product list after
Parcel Post is removed. Thus, it asserts
that the proposed changes will continue
to meet the objectives and factors in 39
U.S.C. 3622(b) and (c). Id., Attachment
B at 2.
The Postal Service explains why the
proposed changes will not violate the
standards of 39 U.S.C. 3633. It notes that
in FY 2011, Parcel Post had an
estimated cost coverage of 89.2 percent.
It recognizes that a price increase will
be necessary to ensure that Parcel Post
covers its attributable costs and
prohibits market dominant products
from subsidizing competitive products.
It asserts that the proposed changes
should also cover an appropriate share
of its institutional costs assuming that
the current 5.5 percent contribution rate
remains the same.3 Request, Attachment
B at 3.
2 Alaska Bypass Service allows shippers to send
shrink-wrapped pallets of goods intra-Alaska at
Parcel Post rates from designated ‘‘hub points’’ to
designated ‘‘bush points.’’ Id., Attachment B at 2.
3 See 39 U.S.C. 3633(a)(3); 39 CFR 3015.7(c). The
Commission is currently re-evaluating the
institutional cost contribution requirement for
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26795
The Postal Service contends that
Parcel Post has small market shares in
both the ground package retail market
(17.6 percent) and the broader ground
package market (1.1 percent), even
though Parcel Post prices are lower than
those charged by UPS and FedEx for
comparable products.4 Id., Attachment B
at 5. It notes that a comparison of the
service standards indicates that UPS
and FedEx provide faster guaranteed
delivery times than those currently
offered by Parcel Post. Id. For these
reasons, the Postal Service contends that
current Parcel Post customers would
have viable alternatives from
competitors if the Postal Service were to
raise prices, degrade service, or decrease
output. Id., Attachment B at 6.
In describing the views of current
Parcel Post customers, the Postal
Service asserts that their major concern
would likely be the price increases
resulting from the proposed changes.
The Postal Service acknowledges that a
modest price increase will be necessary
to attain full cost coverage. However, it
contends that Priority Mail prices will
effectively serve as a price cap because
the Postal Service cannot raise Parcel
Post prices above Priority Mail prices
without shifting Parcel Post volume to
Priority Mail. It explains that Parcel Post
will continue to have the same service
standards if the proposed changes are
implemented, ensuring that customers
in rural communities will continue to
receive reliable ground package delivery
service. Id., Attachment B at 8.
The Postal Service estimates that only
15 percent of Parcel Post’s volume is
attributable to small businesses. Thus, it
concludes that most small businesses
should not see significant changes to
their mailing options as a result of the
proposed changes. Id., Attachment B at
9. The Postal Service contends that the
contents of Parcel Post will fall outside
the scope of the letter monopoly and
that any letters contained in these
parcels will fall within the scope of the
exceptions or suspensions to the Private
Express Statutes. Id., Attachment B at 6–
7.
Notice of filings. The Commission
establishes Docket No. MC2012–13 to
consider the Postal Service’s proposals
described in its Request. Interested
persons may submit comments on
competitive products. See Docket No. RM2012–3,
Order No. 1108, Notice of Proposed Rulemaking to
Evaluate the Institutional Cost Contribution
Requirement for Competitive Products, January 6,
2012.
4 The Postal Service states that Parcel Post
primarily competes in the ground package retail
market, which includes households and small
businesses with fewer than nine employees. Id.,
Attachment B at 4.
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Agencies
[Federal Register Volume 77, Number 88 (Monday, May 7, 2012)]
[Notices]
[Pages 26793-26795]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-10928]
[[Page 26793]]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-389; NRC-2011-0194]
Florida Power and Light Company, St. Lucie Plant, Unit No. 2,
Exemption
1.0 Background
The Florida Power & Light Company (FPL, the licensee) is the holder
of Renewed Facility Operating License No. NPF-16, which authorizes
operation of St. Lucie Plant, Unit No. 2 (St. Lucie, Unit 2). The
license provides, among other things, that the facility is subject to
all rules, regulations, and orders of the U.S. Nuclear Regulatory
Commission (NRC or the Commission) now or hereafter in effect. The
facility consists of two pressurized-water reactors located in Jensen
Beach, Florida. However, this exemption is applicable only to St.
Lucie, Unit 2.
By letter dated April 28, 2011 (Agencywide Documents Access and
Management System (ADAMS) Accession No. ML11119A136), the licensee
submitted a request for an exemption from Title 10 of the Code of
Federal Regulations (10 CFR) Part 50, Appendix G, to implement a
revision of the pressure-temperature (P-T) operating limits for St.
Lucie, Unit 2. In requesting the revisions to the P-T operating limits,
the licensee referenced a topical report with a methodology for the P-T
curves that did not meet some of the requirements of 10 CFR part 50,
Appendix G, thus requiring the exemption pursuant to 10 CFR 50.12.
2.0 Request/Action
Part 50 of 10 CFR, Appendix G, ``Fracture Toughness Requirements,''
which is invoked by 10 CFR 50.60, requires that P-T limits be
established for the reactor coolant pressure boundary during normal
operating and hydrostatic or leak rate testing conditions.
Specifically, 10 CFR part 50, Appendix G, Section IV.A.2, states that
``[t]he appropriate requirements on both the pressure-temperature
limits and the minimum permissible temperature must be met for all
conditions,'' and ``[t]he pressure-temperature limits identified as
`ASME [American Society for Mechanical Engineers] Appendix G limits' in
[T]able 3 require that the limits must be at least as conservative as
limits obtained by following the methods of analysis and the margins of
safety of Appendix G of Section XI of the ASME Code [Boiler and
Pressure Vessel Code].'' The regulations in 10 CFR part 50, Appendix G
also specify the use of the applicable editions and addenda of the ASME
Code, Section XI, which are incorporated by reference in 10 CFR 50.55a.
In the 2009 Edition of 10 CFR, the 1977 Edition through the 2004
Edition of the ASME Code, Section XI, are incorporated by reference in
10 CFR 50.55a. Finally, 10 CFR 50.60(b) states that, ``[p]roposed
alternatives to the described requirements in Append[ix] G of this part
or portions thereof may be used when an exemption is granted by the
Commission under [10 CFR] 50.12.''
In its January 23, 2008, LAR to implement the current St. Lucie 2
technical specification (TS) P-T limits, the licensee provided the
technical basis document for developing these P-T limits, Westinghouse
Commercial Atomic Power report WCAP-16817-NP, Revision 2, ``St. Lucie
Unit 2 RCS [reactor coolant system] Pressure and Temperature Limits and
Low Temperature Overpressure Protection Report for 55 Effective Full
Power Years'' (ADAMS Accession No. ML080290135). WCAP-16817-NP,
Revision 2, references Combustion Engineering (CE) Owners Group Topical
Report CE NPSD-683-A, Revision 6, ``Development of a RCS Pressure and
Temperature Limits Report (PTLR) for the Removal of P-T Limits and LTOP
Requirements from the Technical Specifications'' (ADAMS Accession No.
ML011350387), as the methodology for determining the P-T limits. While
WCAP-16917-NP, Revision 2, did not develop a separate PTLR for removal
of the P-T limits from the St. Lucie 2 TSs, this report did utilize the
methodology of CE NPSD-683-A, Revision 6, as the basis for calculating
the P-T limits currently established in the St. Lucie 2 TSs. Use of the
CE topical report requires an exemption.
By letter dated April 28, 2011, the licensee requested an exemption
from 10 CFR part 50, Appendix G, consistent with the requirements of 10
CFR 50.12 and 50.60, to apply the KIm calculational
methodology of CE NPSD-683-A, Revision 6, in the development of the St.
Lucie, Unit 2, P-T limits. If a licensee proposes to use the
methodology in CE NPSD-683-A, Revision 6, for the calculation of
KIm, an exemption is required since the methodology for the
calculation of KIm values in CE NPSD-683-A, Revision 6,
cannot be shown to be equally or more conservative than the methodology
for the determination of KIm provided in editions and
addenda of the ASME Code, Section XI, Appendix G, through the 2004
Edition.
The NRC staff evaluated the specific PTLR methodology in CE NPSD-
683, Revision 6. This evaluation was documented in the NRC safety
evaluation (SE) of March 16, 2001 (ADAMS Accession No. ML010780017),
which specified additional licensee actions that are necessary to
support a licensee's adoption of CE NPSD-683, Revision 6. The final
approved version of this report was reissued as CE NPSD-683-A, Revision
6, which included the NRC SE and the required additional action items
as an attachment to the report. One of the additional specified actions
(21) stated, ``(applicable only if the CE NSSS [nuclear steam
supply system] methods for calculating KIm and
KIt factors, as stated in Section 5.4 of CE NPSD-683,
Revision 6, are being used as the basis for generating the P-T limits
for their facilities) [licensees will need to] apply for an exemption
against requirements of Section IV.A.2. of Appendix G to Part 50 to
apply the CE NSSS methods to their P-T curves.'' The action item
further stated, ``Exemption requests to apply the CE NSSS to the
generation of P-T limit curves should be submitted pursuant to the
provision of 10 CFR 50.60(b) and will be evaluated on a case-by-case
basis against the exemption request acceptance criteria of 10 CFR
50.12.''
An exemption to use the methodology of CE NPSD-683-A to calculate
the KIt factors is no longer necessary because editions and
addenda of the ASME Code, Section XI, that have been incorporated by
reference into 10 CFR 50.55a subsequent to the issuance of the final SE
of CE NPSD-683-A, allow methods for determining the KIt
factors that are equivalent to the methods described in CE NPSD-683-A.
During the NRC staff's review of CE NPSD-683, Revision 6, the NRC
staff evaluated the KIm calculational methodology of that
report versus the methodologies for the calculation of KIm
given in the ASME Code, Section XI, Appendix G. In the NRC's March 16,
2001, SE., the staff noted, ``[t]he CE NSSS methodology does not invoke
the methods in the 1995 edition of Appendix G to the Code for
calculating KIm factors, and instead applies FEM [finite
element modeling] methods for estimating the KIm factors for
the RPV [reactor pressure vessel] shell * * * the staff has determined
that the KIm calculation methods apply FEM modeling that is
similar to that used for the determination of the KIt
factors [as codified in the ASME Code, Section XI, Appendix G]. The
staff has also determined that there is only a slight non-conservative
difference between the P-T limits generated from the 1989 edition of
[the ASME Code, Section XI,] Appendix G to the Code and those generated
from CE NSSS methodology as documented in [CE/ABB] Evaluation
[[Page 26794]]
No. 063-PENG-ER-096, Revision 00, [`Technical Methodology Paper
Comparing ABB/CE PT Curve to ASME Section III, Appendix G,' dated
January 22, 1998 (ADAMS Accession No. ML100500514, nonproprietary
version)]. The staff considers this difference to be reasonable and
should be consistent with the expected improvements in P-T generation
methods that have been incorporated into the 1995 edition of Appendix G
to the Code.'' This conclusion regarding the comparison between the CE
NSSS methodology and the 1995 Edition of the ASME Code, Section XI,
Appendix G, methodology also applies to the 2004 Edition of the ASME
Code, Section XI, Appendix G, methodology because there were no
significant changes in the method of calculating the KIm
factors required by the ASME Code, Section XI, Appendix G, between the
1995 edition (through 1996 addenda) and the 2004 editions of the ASME
Code. In summary, the staff concluded in its March 16, 2001, SE that
the calculation of KIm using the CE NPSD-683, Revision 6
methodology would lead to the development of P-T limit curves that may
be slightly nonconservative with respect to those that would be
calculated using the ASME Code, Section XI, Appendix G, methods, and
that such a difference was to be expected with the development of more
refined calculational techniques. Furthermore, the staff concluded in
its March 16, 2001, SE that P-T limit curves that would be developed
using the methodology of CE NPSD-683, Revision 6, would be adequate for
protecting the RPV from brittle fracture under all normal operating and
hydrostatic/leak test conditions.
3.0 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, are consistent with the common defense and security; and (2)
when special circumstances are present.
Authorized by Law
This exemption allows the use of an alternative methodology for
calculating flaw stress intensity factors in the RPV due to membrane
stress from pressure loadings in lieu of meeting the requirements in 10
CFR 50.60 and 10 CFR part 50, Appendix G. As stated above, 10 CFR 50.12
allows the NRC to grant exemptions from the requirements of 10 CFR part
50. In addition, the granting of the exemption will not result in
violation of the Atomic Energy Act of 1954, as amended, or the
Commission's regulations. Therefore, the exemption is authorized by
law.
No Undue Risk to Public Health and Safety
The underlying purpose of 10 CFR 50.60 and 10 CFR part 50, Appendix
G, is to provide an acceptable margin of safety against brittle failure
of the RCS during any condition of normal operation to which the
pressure boundary may be subjected over its service lifetime.
Appropriate P-T limits are necessary to achieve this underlying
purpose. The licensee's alternative methodology for establishing the P-
T limits and the LTOP setpoints is described in CE NPSD-683-A, Revision
6, which has been approved by the NRC staff. Based on the above, no new
accident precursors are created by using the alternative methodology.
Thus, the probability of postulated accidents will not increase. Also,
based on the above, the consequences of postulated accidents will not
increase. In addition, the licensee used an NRC-approved methodology
for establishing P-T limits and minimum permissible temperatures for
the RPV. Therefore, there is no undue risk to the public health and
safety.
Consistent With Common Defense and Security
The exemption results in changes to the plant by allowing an
alternative methodology for calculating flaw stress intensity factors
in the RPV. This change to the calculation of stress intensity factors
in the RPV material has no negative implications for security issues.
Therefore, this exemption is consistent with the common defense and
security.
Special Circumstances
Special circumstances, pursuant to 10 CFR 50.12(a)(2)(ii), are
present in that continued operation of St. Lucie, Unit 2, with P-T
limit curves developed in accordance with the ASME Code, Section XI,
Appendix G, is not necessary to achieve the underlying purpose of 10
CFR part 50, Appendix G. Application of the KIm
calculational methodology of CE NPSD-683-A, Revision 6, in lieu of the
calculational methodology specified in the ASME Code, Section XI,
Appendix G, provides an acceptable alternative evaluation procedure
that will continue to meet the underlying purpose of 10 CFR part 50,
Appendix G. The underlying purpose of the regulations in 10 CFR part
50, Appendix G, is to provide an acceptable margin of safety against
brittle failure of the reactor coolant system during any condition of
normal operation to which the pressure boundary may be subjected over
its service lifetime.
Based on the staff's March 16, 2001, SE regarding CE NPSD-683,
Revision 6, and the licensee's rationale to support the exemption
request, the staff determined that an exemption is required to approve
the use of the KIm calculational methodology of CE NPSD-683-
A, Revision 6. By letter dated January 29, 2009, in response to the
licensee's January 23, 2008, LAR, the NRC staff issued an SE that
provided its review of the licensee's calculations in WCAP-16917-NP,
Revision 2, which referenced CE NPSD-683-A, Revision 6. Informed by
these previous evaluations, the staff concludes that the application of
the KIm calculational methodology of CE NPSD-683-A, Revision
6, for St. Lucie, Unit 2, provides sufficient margin in the development
of RPV P-T limit curves such that the underlying purpose of the
regulations (10 CFR part 50, Appendix G) continues to be met.
Therefore, the NRC staff concludes that the exemption requested by the
licensee is justified based on the special circumstances of 10 CFR
50.12(a)(2)(ii), ``[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.'' Based
upon a consideration of the conservatism that is incorporated into the
methodologies of 10 CFR part 50, Appendix G, and ASME Code, Section XI,
Appendix G, the staff concludes that application of the KIm
calculational methodology of CE NPSD-683-A, Revision 6, as described,
would provide an adequate margin of safety against brittle failure of
the RPV. Therefore, the staff concludes that the exemption is
appropriate under the special circumstances of 10 CFR 50.12(a)(2)(ii),
and that the application of the KIm calculational
methodology of CE NPSD-683-A, Revision 6, is acceptable for use as the
basis for generating the St. Lucie, Unit 2, P-T limits.
4.0 Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
50.12(a), 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 under 10
CFR 50.12(a)(2)(ii). Therefore, the Commission hereby grants FPL an
exemption from the requirements of 10 CFR part 50, Appendix G, to allow
application of the KIm calculational
[[Page 26795]]
methodology of CE NPSD-683-A, Revision 6, as the basis for the St.
Lucie, Unit 2, P-T limits.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this exemption will not have a significant effect on the
quality of the human environment (76 FR 53497; August 26, 2011). This
exemption is effective upon issuance.
Dated at Rockville, Maryland, this 30th day of April 2012.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2012-10928 Filed 5-4-12; 8:45 am]
BILLING CODE 7590-01-P