[Federal Register Volume 72, Number 50 (Thursday, March 15, 2007)]
[Notices]
[Pages 12223-12227]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E7-4752]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Notice of Opportunity To Comment on 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: Request for comment.
-----------------------------------------------------------------------
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 would allow 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.''
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. The NRC staff is requesting comments on the model LAR, model
SE and NSHC determination before announcing their availability for
referencing in license amendment applications.
DATES: The comment period expires 30 days from the date of this
publication. Comments received after this date will be considered if it
is practical to do so, but the Commission is able to ensure
consideration only for comments received on or before this date.
[[Page 12224]]
ADDRESSES: Comments may be submitted either electronically or via U.S.
mail.
Submit written comments to: Chief, Rulemaking, Directives, and
Editing Branch, Division of Administrative Services, Office of
Administration, Mail Stop: T-6 D59, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001. Hand deliver comments to: 11545 Rockville
Pike, Rockville, Maryland 20852, between 7:45 a.m. and 4:15 p.m. on
Federal workdays. Submit comments by electronic mail to: [email protected].
Copies of comments received may be examined at the NRC's Public
Document Room, One White Flint North, Public File Area O1-F21, 11555
Rockville Pike (first floor), Rockville, Maryland.
FOR FURTHER INFORMATION CONTACT: Ross Telson, 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) 415-2256.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process [CLIIP] for STSs Changes for Power Reactors,'' was
issued on March 20, 2000. The CLIIP is intended to improve the
efficiency and transparency of NRC licensing processes. This is
accomplished by processing proposed changes to the TS in a manner that
supports subsequent license amendment applications. The CLIIP includes
an opportunity for the public to comment on proposed changes to the TS
following a preliminary assessment by the NRC staff and finding that
the change will likely be offered for adoption by licensees. At the
conclusion of the notice for comment period the NRC staff will evaluate
any comments received for the proposed TS change and either reconsider
the change or proceed with announcing the availability of the change
for proposed adoption by licensees. 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. Following the
public comment period, the model LAR and model SE will be finalized,
and posted on the NRC web page. Each amendment application made in
response to the notice of availability will be processed and noticed in
accordance with applicable NRC rules and procedures.
This notice involves the replacement of the departure from nucleate
boiling (DNB) parameter limits in TS 3.4.1 with references to the
defined formal COLR for the values of these limits. With this
alternative, reload license amendments for the sole purpose of updating
the cycle specific DNB parameter limits will be unnecessary. This
change would allow licensees of Combustion Engineering PWRs to
recalculate DNB parameter limits in the COLR using NRC-approved
methodologies. By letter dated June 20, 2005, the TSTF proposed these
changes for incorporation into the STSs as TSTF-487, Revision 0. These
changes are based on the NRC Generic Letter 88-16 ``Removal of Cycle-
Specific Parameter Limits from Technical Specifications.'' This
document is accessible electronically from the Agency-wide Documents
Access and Management System's (ADAMS) Public Electronic Reading Room
on the Internet (ADAMS Accession No. ML041830597) 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 LCO 3.4.1, SR 3.4.1, the Bases
associated with TS 3.4.1, and TS 5.6.3 for Combustion Engineering PWRs.
To efficiently process the incoming license amendment applications, the
NRC staff requests that each licensee applying for the changes
addressed by TSTF-487 Revision 0, using the CLIIP submit an 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 review by
the NRC staff, and may increase the time and resources needed for the
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 claim to
adopt TSTF-487.
Public Notices
This notice requests comments from interested members of the public
within 30 days of the date of this publication. Following the NRC
staff's evaluation of comments received as a result of this notice, the
NRC staff may reconsider the proposed change or may proceed with
announcing the availability of the change in a subsequent notice
(perhaps with some changes to the model LAR, model SE or model NSHC
determination as a result of public comments). If the NRC staff
announces the availability of the change, 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 7th day of March, 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, REVISION 0 ``RELOCATE DNB PARAMETERS TO
THE COLR.'' THE MODEL PROVIDES THE EXPECTED LEVEL OF DETAIL AND
CONTENT FOR AN APPLICATION TO ADOPT TSTF-487, REVISION 0. 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 0,
``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 0. 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).
[[Page 12225]]
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 under penalty of perjury under the laws of the United
States of America that I am authorized by [LICENSEE] to make this
request and that the foregoing is true and correct. [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 0 ``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 0, 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 [ ]),
the NRC Notice for Comment published on [DATE] ([ ] FR [ ]), and
TSTF-487, Revision 0.
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 0
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 0.
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 0, 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).
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
[[Page 12226]]
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.
Section 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 the following statement has been added to TS 5.6.3:
``The maximum thermal power from the COLR shall be equal to or
greater than the RTP defined in TS 1.1.''
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].
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.
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 5.6.5,
``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.
[[Page 12227]]
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.
[Lit. face SIG]
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. E7-4752 Filed 3-14-07; 8:45 am]
BILLING CODE 7590-01-P