[Federal Register Volume 72, Number 107 (Tuesday, June 5, 2007)]
[Notices]
[Pages 31108-31112]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E7-10786]
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NUCLEAR REGULATORY COMMISSION
Notice of Availability of Model Safety Evaluation and Model
License Amendment Request on Technical Specification Improvement
Regarding Relocation of Departure From Nucleate Boiling Parameters to
the Core Operating Limits Report for Combustion Engineering Pressurized
Water Reactors Using the Consolidated Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability.
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SUMMARY: Notice is hereby given that the staff of the U.S. Nuclear
Regulatory Commission (NRC) has prepared a model license amendment
request (LAR), model safety evaluation (SE), and model proposed no
significant hazards consideration (NSHC) determination related to
changes to Standard Technical Specifications (STSs) for Combustion
Engineering Pressurized Water Reactors (PWRs), NUREG-1432, Revision
3.1. This change allows the numerical limits located in technical
specification (TS) 3.4.1, ``RCS Pressure, Temperature, and Flow
[Departure from Nucleate Boiling (DNB)] Limits'' to be replaced with
references to the Core Operating Limits Report (COLR). Associated
changes are also included for the TS 3.4.1 Bases, and TS 5.6.3 ``Core
Operating Limits Report (COLR).'' The Technical Specifications Task
Force (TSTF) proposed these changes to the TS in TSTF-487 Revision 0,
``Relocate DNB Parameters to the COLR.'' This request was slightly
modified in TSTF-487 Revision 1 on May 4, 2007.
The purpose of the model SE, LAR, and NSHC is to permit the NRC to
efficiently process amendments to incorporate these changes into plant-
specific TSs for Combustion Engineering PWRs. Licensees of nuclear
power reactors to which the models apply can request amendments
conforming to the models. In such a request, a licensee should confirm
the applicability of the model LAR, model SE and NSHC determination to
its plant.
DATES: The NRC staff issued a Federal Register Notice (72 FR 12223,
March 15, 2007) which provided a model LAR, model SE, and model NSHC
for comment related to replacing the DNB parameters in TS 3.4.1 with
references to the COLR. The revised model LAR, revised model SE, and
unchanged NSHC associated with this change are provided in this notice.
The NRC can most efficiently consider applications based upon the model
LAR, which references the model SE, if the application is submitted
within one year of this Federal Register Notice.
FOR FURTHER INFORMATION CONTACT: William Cartwright, Mail Stop: O-12H2,
Division of Inspection and Regional Support, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone (301) 415-8345.
SUPPLEMENTARY INFORMATION:
Background
This change was made using the Consolidated Line Item Improvement
Process [CLIIP] for STS Changes for Power Reactors, issued on March 20,
2000 as Regulatory Information Summary 2000-006. This document can be
viewed on the NRC's public Web page at http://www.nrc.gov/reading-rm/doc-collections/gen-comm/reg-issues/2000/ri00006.html. The CLIIP is
intended to improve the efficiency and transparency of NRC licensing
processes by processing proposed changes to the STS in a manner that
supports subsequent license amendment applications. Those licensees
opting to apply for the subject change to TSs are responsible for
reviewing the NRC staff's evaluation, referencing the applicable
technical justifications, and providing any necessary plant-specific
information. This notice finalizes the model LAR and model SE. Each
amendment application made in response to the notice of availability
will be processed and noticed in accordance with applicable NRC rules
and procedures.
The purpose of this change is to allow Combustion Engineering PWR
licensees to recalculate cycle specific departure from nucleate boiling
(DNB) parameter limits in the COLR using NRC-approved
[[Page 31109]]
methodologies. With this alternative, reload license amendments for the
sole purpose of updating the cycle specific DNB parameter limits will
be unnecessary. By letter dated June 20, 2005, the TSTF proposed these
changes for incorporation into the STSs as TSTF-487 Revision 0 (ADAMS
Accession No. ML051860302), followed by TSTF-487 Revision 1 on May 4,
2007 (ADAMS Accession No. ML071240259) . These changes are based on the
NRC Generic Letter 88-16 ``Removal of Cycle-Specific Parameter Limits
from Technical Specifications'' (ADAMS Accession No. ML041830597).
ADAMS documents are accessible electronically from the Agency-wide
Documents Access and Management System's (ADAMS) Public Electronic
Reading Room on the Internet at the NRC Web site http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who
encounter problems in accessing the documents located in ADAMS should
contact the NRC Public Document Room Reference staff by telephone at 1-
800-397-4209, 301-415-4737, or by e-mail to [email protected].
Applicability
These proposed changes will revise the limiting condition for
operation (LCO) 3.4.1, surveillance requirement (SR) 3.4.1, and TS
5.6.3 for Combustion Engineering PWRs. Licensees adopting this change
may also have to change the bases associated with TS 3.4.1 under their
bases control program. To efficiently process incoming license
amendment applications, the NRC staff requests that each licensee using
the CLIIP to adopt the changes addressed by TSTF-487 Revision 1, submit
a LAR that adheres to the following model. Any variations from the
model LAR should be explained in the licensee's submittal. Variations
from the approach recommended in this notice may require additional
time and resources by the NRC staff for review. Significant variations
from the approach, or inclusion of additional changes to the license,
will result in NRC staff rejection of the submittal. Instead, licensees
desiring significant variations and/or additional changes should submit
a LAR that does not request to adopt TSTF-487.
Public Notices
The staff issued a Federal Register Notice (72 FR 12223, March 15,
2007) that requested public comment on the NRC's pending action to
allow relocation of DNB parameters to the COLR for Combustion
Engineering PWRs using the CLIIP. One response was received from the
TSTF (ADAMS Accession No. ML071030076). The comments are summarized and
discussed below:
1. Comment: A statement did not need to be added to TS section
5.6.3 regarding the requirement to perform the COLR calculations at
rated thermal power (RTP). The justification for this was that it was a
restatement of existing regulatory requirements. In addition, the
wording proposed by the NRC staff was unclear to licensees. It was
proposed in the comment that licensees make a commitment as part of
their amendment request instead of making changes to the TS
administrative controls section 5.6.3.
Response: The NRC staff discussed this issue at a public meeting
held on March 22, 2007. In response to that meeting, the TSTF provided
modified wording that was acceptable to the NRC staff for TS section
5.6.3 in TSTF-487 Revision 1, on May 4, 2007 (ADAMS Accession No.
ML071240259). The modified wording has been incorporated into the model
SE.
2. Comment: References to the TS bases should be removed from the
model application as the bases are under the licensee's control, not
required to be approved by the NRC, and not required as part of TS
amendments.
Response: The Code of Federal Regulations (10 CFR 50.36 (a)) states
``A summary of the basis or reasons for such specifications, other than
those covering administrative controls, shall also be included in the
application, but shall not become part of the technical
specifications.'' The regulations supporting inclusion of the bases
into TS amendments are described in 10 CFR 50.90, which states that
applications for amendments should be made ``fully describing the
changes desired, and following as far as applicable, the form
prescribed for original applications.'' Providing the bases changes
with the amendment assists in assuring a common understanding of the
changed TS requirements between the licensee and the NRC staff. As the
licensee is required to maintain and update the TS bases, providing the
updated changes to the NRC as part of an amendment request does not
constitute an additional burden. This comment was not incorporated.
3. Comment: The oath or affirmation statement in the model
application was not consistent with RIS 2001-18, ``Requirements for
Oath or Affirmation.''
Response: The model application was revised to be consistent with
RIS 2001-18.
4. Comment: The last portion of the applicability section discussed
the consequences of a licensee submitting variations from the approach
described in the model application. The last sentence published in the
notice for comment reads ``Instead, licensees desiring significant
variations and/or additional changes should submit a LAR that does not
claim to adopt TSTF-487.'' The comment requested to revise that
sentence to ``Instead, licensees desiring significant variations and/or
additional changes should submit a LAR that does not claim to adopt
TSTF-487 under the CLIIP.'' The purpose of this change would be to
allow licensees to adopt model applications to facilitate NRC staff
review as part other amendment processes (for example, a license
amendment to adopt standard technical specifications).
Response: The CLIIP allows licensees to submit amendment requests
that closely adopt model applications developed under a streamlined
process. Amendments proposing to adopt TSTFs that substantially deviate
from model applications are not appropriate for a streamlined review
process. For amendments that substantially deviate from a model
application, licensees can reference or follow approved TSTF model
applications to support their amendment requests. These requests will
receive the normal NRC staff review process. This comment was not
incorporated.
The NRC staff has proceeded with announcing the availability of the
change in this notice with some minor changes to the model LAR and
model SE as a result of public comments. Licensees wishing to adopt the
change will submit an application in accordance with applicable rules
and other regulatory requirements. The NRC staff will, in turn, issue
for each application a notice of consideration of issuance of amendment
to facility operating license(s), a proposed NSHC determination, and an
opportunity for a hearing. A notice of issuance of an amendment to
operating license(s) will also be issued to announce the revised
requirements for each plant that applies for and receives the requested
change.
Dated at Rockville, Maryland, this 29th day of May, 2007.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and
Regional Support, Office of Nuclear Reactor Regulation.
For inclusion on the technical specification Web page the following
example of an application was prepared by the NRC staff to facilitate
the adoption of Technical Specifications Task Force (TSTF) Traveler
TSTF-487,
[[Page 31110]]
Revision 1 ``relocate DNB parameters to the COLR.'' The model provides
the expected level of detail and content for an application to adopt
TSTF-487, Revision 1. Licensees remain responsible for ensuring that
their actual application fulfills their administrative requirements as
well as NRC regulations.
U.S. Nuclear Regulatory Commission, Document Control Desk, Washington,
DC 20555.
SUBJECT: Plant name, Docket No. 50-[xxx,] Re: Application for technical
specification improvement to adopt TSTF-487, Revision 1, ``relocate DNB
parameters to the COLR''
Dear Sir or Madam: In accordance with the provisions of Section
50.90 of Title 10 of the Code of Federal Regulations (10 CFR),
[LICENSEE] is submitting a request for an amendment to the technical
specifications (TS) for [PLANT NAME, UNIT NOS.]. The proposed changes
would allow [PLANT NAME] to replace the DNB numeric limits in TS with
references to the core operating limits report (COLR).
The changes are consistent with NRC-approved Industry Technical
Specification Task Force (TSTF) Standard Technical Specification Change
Traveler, TSTF-487 Revision 1. The availability of this TS improvement
was announced in the Federal Register on [DATE] [ ] FR [ ]) as part of
the consolidated line item improvement process (CLIIP).
Enclosure 1 provides a description and assessment of the proposed
changes, as well as confirmation of applicability. Enclosure 2 provides
the existing TS pages and TS Bases marked-up to show the proposed
changes. Enclosure 3 provides final TS pages and TS Bases pages.
[LICENSEE] requests approval of the proposed license amendment by
[DATE], with the amendment being implemented [BY DATE OR WITHIN X
DAYS]. In accordance with 10 CFR 50.91, a copy of this application,
with enclosures, is being provided to the designated [STATE] Official.
I declare [or certify, verify, state] under penalty of perjury that
the foregoing is true and correct. Executed on [date] [Signature].
[Note that request may be notarized in lieu of using this oath or
affirmation statement].
If you should have any questions regarding this submittal, please
contact [ ].
Sincerely,
Name, Title
Enclosures:
1. Description and Assessment of Proposed Changes.
2. Proposed Technical Specification Changes and Technical
Specification Bases Changes.
3. Final Technical Specification and Bases pages.
cc: NRR Project Manager, Regional Office, Resident Inspector, State
Contact, ITSB Branch Chief.
1.0 Description
This letter is a request to amend Operating License(s) [LICENSE
NUMBER(S)] for [PLANT/UNIT NAME(S)]. The proposed changes would revise
Technical Specification (TS) 3.4.1, ``RCS Pressure, Temperature, and
Flow [Departure from Nucleate Boiling (DNB)] Limits,'' the bases for TS
3.4.1, and TS 5.6.3 ``Core Operating Limits Report (COLR),'' to allow
[PLANT NAME] to place the DNB numeric limits with references to the
COLR.
Technical Specification Task Force (TSTF) change traveler TSTF-487,
Revision 1 ``Relocate DNB Parameters to the COLR'' was announced for
availability in the Federal Register on [DATE] as part of the
consolidated line item improvement process (CLIIP).
2.0 Proposed Changes
Consistent with NRC-approved TSTF-487 Revision 1, the following
changes are proposed:
Revise the limiting conditions for operation and
surveillance requirements in TS 3.4.1 to replace the DNB numeric limits
for reactor coolant pressure, temperature, and flow with references to
limits for those parameters calculated in the COLR.
Revise the bases associated with TS 3.4.1 to reflect that
the DNB numeric limits are contained in the COLR.
Revise TS 5.6.3 to add the methodology requirements for
calculating the DNB numeric limits in the COLR.
3.0 Background
The background for this application is as stated in the model SE in
NRC's Notice of Availability published on [DATE ] ([ ] FR [ ]), and
TSTF-487, Revision 1.
4.0 Technical Analysis
[LICENSEE] has reviewed Generic Letter 88-16, and the model SE
published on [DATE] ([ ] FR [ ]) as part of the CLIIP Notice for
Comment. [LICENSEE] has applied the methodology in Generic Letter 88-16
to develop the proposed TS changes. [LICENSEE] has also concluded that
the justifications presented in TSTF-487, Revision 1 and the model SE
prepared by the NRC staff are applicable to [PLANT, UNIT NOS.], and
justify this amendment for the incorporation of the changes to the
[PLANT] TS.
5.0 Regulatory Analysis
A description of this proposed change and its relationship to
applicable regulatory requirements and guidance was provided in the NRC
Notice of Availability published on [DATE] ([ ] FR [ ]), the NRC Notice
for Comment published on [DATE] ([ ] FR [ ]), and TSTF-487, Revision 1.
6.0 No Significant Hazards Consideration
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination published in the Federal Register on [DATE]
([ ] FR [ ]) as part of the CLIIP. [LICENSEE] has concluded that the
proposed determination presented in the notice is applicable to [PLANT]
and the determination is hereby incorporated by reference to satisfy
the requirements of 10 CFR 50.91(a).
7.0 Environmental Evaluation
[LICENSEE] has reviewed the environmental consideration included in
the model SE published in the Federal Register on [DATE] ([ ] FR [ ])
as part of the CLIIP. [LICENSEE] has concluded that the staff's
findings presented therein are applicable to [PLANT] and the
determination is hereby incorporated by reference for this application.
Proposed Safety Evaluation,
U.S Nuclear Regulatory Commission,
Office of Nuclear Reactor Regulation.
Consolidated Line Item Improvement Technical Specification Task Force
(TSTF)
Change TSTF-487, Revision 1, RELOCATE DNB PARAMETERS TO THE COLR
1.0 Introduction
By application dated [Date], (Ref. 7.1), the [Name of Licensee]
(the licensee) requested changes to the Technical Specifications (TS)
for the [Name of Facility].
The proposed changes would revise TS 3.4.1, the associated bases of
TS 3.4.1, and TS 5.6.3 to replace the departure from nucleate boiling
(DNB) parameters limits in Technical Specifications (TSs) with
references to the Core Operating Limits Report (COLR). These changes
would allow the licensee to recalculate the DNB parameter limits using
NRC-approved methodologies without the need for a license amendment
request (LAR).
[[Page 31111]]
The proposed changes include the following:
Change TS 3.4.1, ``RCS Pressure, Temperature, and Flow
[Departure from Nucleate Boiling (DNB)] Limits,'' Limiting Conditions
for Operation (LCO) 3.4.1 and the associated Surveillance Requirements
(SRs) to replace the specific limit values of RCS pressurizer pressure,
cold leg temperature, and RCS total flow rate with ``the limits
specified in the COLR.''
Change the bases for LCO 3.4.1 to reflect that the DNB
limits are specified in the COLR.
Change Section 5.6.3 of TS, ``Core Operating Limits Report
(COLR)'' to include the NRC approved methodologies and requirements
used to calculate the DNB limits.
Generic Letter (GL) 88-16 titled ``Removal of Cycle-Specific
Parameter Limits from Technical Specifications'' (Ref. 7.2) is the
regulatory guidance for this change.
2.0 Regulatory Evaluation
The Commission's regulatory requirements related to the content of
Technical Specifications are specified in Title 10 CFR (Code of Federal
Regulations), Section 50.36, ``Technical Specifications.'' 10 CFR
50.36(c)(2)(i) defines that limiting conditions for operation are the
lowest functional capability or performance levels of equipment
required for safe operation of the facility. For the DNB parameters, 10
CFR 50.36(c)(2)(ii)(B) Criterion 2 applies, which requires that TS LCOs
be established for each process variable, design feature, or operating
restriction that is an initial condition of a design basis accident or
transient analysis that either assumes the failure of or presents a
challenge to the integrity of a fission product barrier.
LARs are required for each fuel cycle design that results in
changes to parameter limits specified in TS. To meet 10 CFR
50.36(c)(2)(ii) requirements and alleviate the need for LARs to update
parameter limits every fuel cycle, the NRC issued GL 88-16 with
specific guidance for replacing the limit values for cycle-specific
parameters in the TSs with references to an owner-controlled document,
namely, the COLR. The guidance in GL 88-16 includes the following three
actions:
1. The addition of the definition of a named formal report (i.e.,
Core Operating Limits Report) in TS that includes the values of cycle-
specific parameter limits that have been established using an NRC-
approved methodology and consistent with all applicable limits of the
safety analyses.
2. The addition of an administrative reporting requirement (in TS
5.6.3) to submit the formal report on cycle-specific parameter limits
to the Commission for information.
3. The modification of individual TS to note that the specific
parameters shall be maintained within the limits provided in the
defined formal report (COLR).
The proposed change has been evaluated against GL 88-16 and found
to be consistent with that regulatory guidance.
3.0 Technical Evaluation
TS LCO 3.4.1 specifies the limit values of the DNB parameters to
assure that the pressurizer pressure, the RCS cold leg temperature, and
RCS flow rate during operation at rated thermal power (RTP) will be
maintained within the limits assumed in the safety analyses in the
final safety analysis report (FSAR). The safety analyses of anticipated
operational occurrences (AOOs) and accidents assume initial conditions
within the envelope of normal steady state operation at the RTP to
demonstrate that the applicable acceptance criteria, including the
specified acceptable fuel design limits (such as DNB ratio) and RCS
pressure boundary design conditions, are met for each event analyzed.
The TS limits placed on the DNB-related parameters ensure that these
parameters, when appropriate measurement uncertainties are applied,
will be bounded by those assumed in the safety analyses, and thereby
provide assurance that the applicable acceptance criteria will not be
violated should a transient or accident occur while operating at the
RTP.
It is essential to safety that the plant is operated within the DNB
parameter limits. This change retains the requirement to maintain the
plant within the DNB parameter limits in LCO 3.4.1 along with the SR
verification for each of the DNB parameters. As these parameter limits
are calculated using NRC-approved methodologies and are consistent with
all applicable limits of the plant safety analyses, this change does
not affect nuclear safety.
TS 5.6.3, ``Core Operating Limits Report (COLR),'' specifies that
the core operating limits shall be determined such that all applicable
limits of the safety analyses are met, and that the analytical methods
used to determine the core operating limits shall be those previously
reviewed and approved by the NRC. This change modifies the list of NRC
approved methodologies in TS 5.6.3 to include those used to calculate
the DNB limits on pressurizer pressure, RCS cold leg temperature, and
RCS total flow rate. The limit values of these parameters in the COLR
will comply with existing operating fuel cycle analysis requirements,
and are initial conditions assumed in safety analyses. Replacing of the
DNB parameter values with references to the COLR does not lessen the
requirement for compliance with all applicable limits.
Any revisions to the safety analyses that require prior NRC
approval will be identified by the 10 CFR 50.59 review process. TS
5.6.3 also specifies that the COLR, including any midcycle revisions or
supplements, shall be provided upon issuance for each reload cycle to
the NRC. This will allow NRC staff to continue trending the information
even though prior NRC approval of the changes to these limits will not
be required.
10 CFR 50.36 requires LCOs to contain the lowest functional
capability or performance levels of equipment for safe operation of the
facility. The NRC staff finds that the proposed change to LCO 3.4.1
referencing the specific values of the DNB parameter limits in TS in
the COLR continues to meet the regulatory requirement of 10 CFR
50.36(c)(2)(ii)(B) (Criterion 2), and follows the guidance described in
GL 88-16. The NRC staff, therefore, concludes that this change is
acceptable.
For safety analyses of transients or accidents, various sections of
Chapter 15 of the Standard Review Plan (Ref. 7.3) specify that the
reactor is initially at the RTP plus uncertainty, and the RCS flow is
at nominal design flow including the measurement uncertainty. If one or
more DNB parameter limits change, and these changes do not support the
RTP, a license amendment would be required to either reduce the RTP or
limit the plant operation at a level below the RTP. 10 CFR 50 Appendix
K requires that the loss of coolant accident analysis be performed at
102% of the RTP. Other plant-specific analyses can contain an initial
condition to be performed at RTP. To insure a clear understanding of
this requirement TS 5.6.3.c. has been reworded to add the underlined
text: ``The core operating limits shall be determined assuming
operation at RATED THERMAL POWER such that all applicable limits * *
*.''
4.0 State Consultation
In accordance with the Commission's regulations, the [------] State
official was notified of the proposed issuance of the amendment. The
State official had [(1) no comments or (2) the following comments--with
subsequent disposition by the staff].
[[Page 31112]]
5.0 Environmental Consideration
The amendment[s] change[s] a requirement with respect to the
installation or use of a facility component located within the
restricted area as defined in 10 CFR part 20 or surveillance
requirements. The NRC staff has determined that the amendment involves
no significant increase in the amounts, and no significant change in
the types, of any effluents that may be released offsite, and that
there is no significant increase in individual or cumulative
occupational radiation exposure. The Commission has previously issued a
proposed finding that the amendment involves no significant hazards
consideration and there has been no public comment on such finding
published [DATE] ([ ] FR [ ]). Accordingly, the amendment meets the
eligibility criteria for categorical exclusion set forth in 10 CFR
51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment need be prepared in connection
with the issuance of the amendment.
6.0 Conclusion
The NRC staff has reviewed this proposed change to replace the
values of the DNB parameters in TS with references to the COLR. This
change will allow the licensee the flexibility to manage operating and
core design margins associated with the DNB parameters without the need
for cycle-specific LARs. Any future revisions to safety analyses that
require prior NRC approval will be identified by the 10 CFR 50.59
review process. Based on this evaluation the NRC staff concludes that
this change meets the regulatory requirements of 10 CFR 50.36, follows
the guidance described in GL 88-16, and is acceptable.
7.0 References
7.1 License Amendment Request dated [MMM, DD, YYYY], [Title of
Amendment Request], ADAMS Accession No. [MLXXXXXXXXX]
7.2 Generic Letter 88-16 dated October 4, 1988, ``Removal of Cycle-
Specific Parameter Limits from Technical Specifications,'' ADAMS
Accession No. ML041830597
7.3 NUREG-0800, ``Standard Review Plan.''
Proposed No Significant Hazards Consideration Determination
Description of Amendment Request: [Plant name] requests adoption of
an approved change to the standard technical specifications (STS) for
Combustion Engineering Pressurized Water Reactor (PWR) Plants (NUREG-
1432) and plant-specific technical specifications (TS), to allow
replacing the departure from nucleate boiling (DNB) parameter limits
with references to the core operating limits report (COLR) in
accordance with Generic Letter 88-16, ``Removal of Cycle Specific
Parameter Limits from Technical Specifications,'' dated October 4,
1988. The changes are consistent with NRC approved Industry/Technical
Specification Task Force (TSTF) Standard Technical Specification Change
Traveler, TSTF-487, Revision 1.
Basis for proposed no-significant-hazards-consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of no-significant-hazards-consideration is presented below:
Criterion 1: Does the Proposed Change Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated?
Response: No.
The proposed amendment replaces the limit values of the reactor
coolant system (RCS) DNB parameters (i.e., pressurizer pressure, RCS
cold leg temperature, and RCS flow rate) in TS with references to the
COLR, in accordance with the guidance of Generic Letter 88-16, to allow
these parameter limit values to be recalculated without a license
amendment. The proposed amendment does not involve operation of any
required structures, systems, or components (SSCs) in a manner or
configuration different from those previously recognized or evaluated.
The cycle-specific values in the COLR must be calculated using the NRC-
approved methodologies listed in TS 5.6.3, ``Core Operating Limits
Report (COLR).'' Replacing the RCS DNB parameter limits in TS with
references to the COLR will maintain existing operating fuel cycle
analysis requirements. Because these parameter limits are determined
using the NRC-approved methodologies, the acceptance criteria
established for the safety analyses of various transients and accidents
will continue to be met. Therefore, neither the probability nor
consequences of any accident previously evaluated will be increased by
the proposed change.
Therefore, operation of the facility in accordance with the
proposed amendment does not involve a significant increase in the
probability or consequences of an accident previously evaluated.
Criterion 2: Does the Proposed Change Create the Possibility of a
New or Different Kind of Accident from any Previously Evaluated?
Response: No.
The proposed amendment to replace the RCS DNB parameter limits in
TS with references to the COLR does not involve a physical alteration
of the plant, nor a change or addition of a system function. The
proposed amendment does not involve operation of any required SSCs in a
manner or configuration different from those previously recognized or
evaluated. No new failure mechanisms will be introduced by the proposed
change.
Therefore, the proposed amendment does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
Criterion 3: Does the Proposed Change Involve a Significant
Reduction in the Margin of Safety?
Response: No.
The proposed amendment to replace the RCS DNB parameter limits in
TS with references to the COLR will continue to maintain the margin of
safety. The DNB parameter limits specified in the COLR will be
determined based on the safety analyses of transients and accidents,
performed using the NRC-approved methodologies that show that, with
appropriate measurement uncertainties of these parameters accounted
for, the acceptance criteria for each of the analyzed transients are
met. This provides the same margin of safety as the limit values
currently specified in the TS. Any future revisions to the safety
analyses that require prior NRC approval are identified per the 10 CFR
50.59 review process.
Therefore, the proposed amendment would not involve a significant
reduction in a margin of safety.
Based on the staff's review of the licensee's analysis, the staff
concludes that the proposed amendment presents no significant hazards
consideration under the standards set forth in 10 CFR 50.92(c) and,
accordingly, a finding of ``no significant hazards consideration'' is
justified.
Dated at Rockville, Maryland, this ---- day of --------, 2007.
For the Nuclear Regulatory Commission.
Project Manager, Plant Licensing Branch [ ], Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E7-10786 Filed 6-4-07; 8:45 am]
BILLING CODE 7590-01-P