[Federal Register Volume 72, Number 49 (Wednesday, March 14, 2007)]
[Notices]
[Pages 11914-11918]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E7-4675]
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NUCLEAR REGULATORY COMMISSION
Notice of Opportunity for Comment on Model Safety Evaluation for
Technical Specification Task Force (TSTF) Traveler To Provide Actions
for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable Using
the Consolidated Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Request for comment.
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SUMMARY: Notice is hereby given that the staff of the Nuclear
Regulatory Commission (NRC) has prepared a model safety evaluation (SE)
relating to proposed changes to Actions in the Standard Technical
Specifications (STS) relating to One Steam Supply to Turbine Driven
Auxiliary Feedwater / Emergency Feedwater (AFW/EFW) Pump Inoperable.
This change would establish a Completion Time in the Standard Technical
Specifications for the Condition where one steam supply to the turbine
driven AFW/EFW pump is inoperable concurrent with an inoperable motor
driven AFW/EFW train. The NRC staff has also prepared a model
application and model no significant hazards consideration (NSHC)
determination relating to this matter. The purpose of these models is
to permit the NRC to efficiently process amendments that propose to
adopt the associated changes into plant-specific technical
specifications (TS). Licensees of nuclear power reactors to which the
models apply can request amendments confirming the applicability of the
SE and NSHC determination to their reactors. The NRC staff is
requesting comments on the Model SE, Model Application and Model NSHC
determination prior to 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 can only ensure consideration
for comments received on or before this date.
ADDRESSES: Comments may be submitted either electronically or via U.S.
mail.
To submit comments or questions on a proposed standard technical
specification change via the Internet, use Form for Sending Comments on
NRC Documents, then select Proposed Changes to Technical
Specifications. If you are commenting on a proposed change, please
match your comments with the correct proposed change by copying the
title of the proposed change from column one to the previous table into
the appropriate field of the comment form.
Submit written comments to: Chief, Rulemaking, Directives and
Editing Branch, Division of Administrative Services, Office of
Administration, Mail Stop T-6D59, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
Hand deliver comments to 11545 Rockville Pike, Rockville, Maryland,
between 7:45 a.m. and 4:15 p.m. on Federal workdays.
Copies of comments received may be examined at the NRC's Public
Document Room, located at One White Flint North, 11555 Rockville Pike
(first floor), Rockville, Maryland.
Comments may be submitted by electronic mail to [email protected].
FOR FURTHER INFORMATION CONTACT: Trent L. Wertz, Technical
Specifications Branch, Division of Inspection and Regional Support,
Office of Nuclear Reactor Regulation, Mail Stop O-12H2, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone 301-415-
1568.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process for Adopting Standard Technical Specification
Changes for Power Reactors,'' was issued on March 20, 2000. The
consolidated line item improvement process (CLIIP) is intended to
improve the efficiency and transparency of NRC licensing processes.
This is accomplished by processing proposed changes to the Standard
Technical Specifications (STS) (NUREGs 1430-1434) in a manner that
supports subsequent license amendment applications. The CLIIP includes
an opportunity for the public to comment on proposed changes to the STS
following a preliminary assessment by the NRC staff and finding that
the change will likely be offered for adoption by licensees. The CLIIP
directs the NRC staff to evaluate any comments received for a proposed
change to the STS and to either reconsider the change or proceed with
announcing the availability of the change to licensees. Those licensees
opting to apply for the subject change to TS are responsible for
reviewing the NRC staff's evaluation, referencing the applicable
technical justifications, and providing any necessary plant specific
information. Each amendment application submitted in response to the
notice of availability would be processed and noticed in accordance
with applicable rules and NRC procedures.
This notice for comment involves establishing a Completion Time in
the Limiting Condition for Operation (LCO) 3.7.5 of the STS for the
Condition where one steam supply to the turbine driven AFW/EFW pump is
inoperable concurrent with an inoperable motor driven AFW/EFW train. In
addition, this notice for comment involves changes to the STS that
establish specific Conditions and Action requirements for
[[Page 11915]]
two motor driven AFW/EFW trains are inoperable at the same time and for
when the turbine driven AFW/EFW train is inoperable either (a) due
solely to one inoperable steam supply, or (b) due to reasons other than
one inoperable steam supply. The changes were proposed by the Technical
Specification Task Force (TSTF) in TSTF Traveler TSTF-412, Revision 3,
which is accessible electronically from the Agencywide Documents Access
and Management System (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site http://www.nrc.gov/reading-rm/adams.html
(Accession No. ML070100363). 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
This proposed change to adopt TSTF-412 is applicable to all
pressurized water reactors (PWRs) designed by Babcock and Wilcox (B&W),
Westinghouse, and Combustion Engineering (CE). If approved, to
efficiently process the incoming license amendment applications, the
NRC staff will request that each licensee applying for the changes
addressed by TSTF-412, Revision 3, use the CLIIP to submit a License
Amendment Request (LAR) that conforms to the enclosed Model Application
(Enclosure 1). Any deviations from the Model Application should be
explained in the licensee's submittal. Significant deviations from the
approach, or inclusion of additional changes to the license, will
result in 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-412. 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.
Public Notices
This notice requests comments from interested members of the public
within 30 days of the date of publication in the Federal Register.
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 SE or proposed 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 proposed
action, which includes a proposed NSHC determination. A notice of
issuance of an amendment of operating license will also be issued to
announce the adoption of TSTF-412 for each plant that applies for and
receives the requested change.
Dated at Rockville, Maryland, this 8th 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.
The following example of a license amendment request (LAR) was
prepared by the NRC staff to facilitate the adoption of Technical
Specifications Task Force (TSTF) Traveler TSTF-412, Revision 3
``Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump
Inoperable.'' The model provides the expected level of detail and
content for a LAR to adopt TSTF-412, Revision 3. Licensees remain
responsible for ensuring that their plant-specific LAR fulfills their
administrative requirements as well as NRC regulations.
Proposed Model License Amendment Request
U.S. Nuclear Regulatory Commission
Document Control Desk
Washington, DC 20555
Subject: Plant Name
Docket No. 50-
Application for Technical Specification Improvement To Revise
Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater/
Emergency Feedwater Pump Inoperable Using the Consolidated Line Item
Improvement Process
Gentlemen:
In accordance with the provisions of 10 CFR 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 amendment establishes Conditions, Required Actions,
and Completion Times in the Standard Technical Specifications (STS)
for the Condition where one steam supply to the turbine driven
Auxiliary Feedwater/Emergency Feedwater (AFW/EFW) pump is inoperable
concurrent with an inoperable motor driven AFW/EFW train. In
addition, this amendment establishes changes to the STS that
establish specific Actions when two motor driven AFW/EFW trains are
inoperable at the same time and the turbine driven AFW/EFW train is
inoperable either (a) due solely to one inoperable steam supply, or
(b) due to reasons other than one inoperable steam supply. The
change is consistent with NRC-approved Technical Specification Task
Force (TSTF) Traveler, TSTF-412, Revision 3, ``Provide Actions for
One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable.'' The
availability of this technical specification improvement was
announced in the Federal Register on [DATE OF NOTICE OF
AVAILABILITY] as part of the consolidated line item improvement
process (CLIIP).
Enclosure 1 provides a description of the proposed change and
confirmation of applicability.
Enclosure 2 provides the existing TS pages marked-up to show the
proposed change.
Enclosure 3 provides the existing TS Bases pages marked-up to
reflect the proposed change. There are no new regulatory commitments
associated with this proposed change.
[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
2. Proposed Technical Specification Changes
3. Proposed Technical Specification Bases Changes
cc: NRR Project Manager
Regional Office
Resident Inspector
State Contact
Enclosure 1 to Model License Amendment Request--Description and
Assessment
1.0 Description
The proposed License amendment establish a new Completion Time in
Standard Technical Specifications Section [3.7.5] where one steam
supply to the turbine driven AFW/EFW pump is inoperable concurrent with
an inoperable motor driven AFW/EFW train. This amendment also
establishes specific Conditions and Action requirements when two motor
driven AFW/EFW trains are inoperable at the same time and the turbine
driven AFW/EFW train is inoperable either (a) due solely to one
inoperable steam supply, or (b) due to reasons other than one
inoperable steam supply.
[[Page 11916]]
The changes are consistent with NRC approved Industry/Technical
Specification Task Force (TSTF) Standard Technical Specification Change
Traveler, TSTF-412, Revision 3, ``Provide Actions for One Steam Supply
to Turbine Driven AFW/EFW Pump Inoperable.'' The availability of this
technical specification improvement was announced in the Federal
Register on [DATE ] ([xx FR xxxxx]) as part of the consolidated line
item improvement process (CLIIP).
2.0 Assessment
2.1 Applicability of Published Safety Evaluation
[LICENSEE] has reviewed the safety evaluation published on [DATE ]
([xx FR xxxxx]) as part of the CLIIP. This verification included a
review of the NRC staff's evaluation as well as the supporting
information provided to support TSTF-412, Revision 3. [LICENSEE] has
concluded that the justifications presented in the TSTF proposal and
the safety evaluation prepared by the NRC staff are applicable to
[PLANT, UNIT NOS.] and justify this amendment for the incorporation of
the changes to the [PLANT] Technical Specifications.
2.2 Optional Changes and Variations
[LICENSEE] is not proposing any variations or deviations from the
technical specification changes described in TSTF-412, Revision 3, or
the NRC staff's model safety evaluation published in the Federal
Register on [DATE ] ([xx FR xxxxx]).
3.0 Regulatory Analysis
3.1 No Significant Hazards Determination
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination published on [DATE] 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).
3.2 Verification and Commitments
There are no new regulatory commitments associated with this
proposed change.
4.0 Environmental Evaluation
[LICENSEE] has reviewed the environmental evaluation included in
the model safety evaluation published in the Federal Register on [DATE
] ([xx FR xxxxx]) as part of the CLIIP. [LICENSEE] has concluded that
the NRC staff's findings presented in that evaluation are applicable to
[PLANT] and the evaluation is hereby incorporated by reference for this
application.
Enclosure 2 to Model License Amendment Request: PROPOSED TECHNICAL
SPECIFICATION CHANGES
Enclosure 3 to Model License Amendment Request: Changes to TS Bases
Pages
Proposed Model Safety Evaluation
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor
Regulation, Consolidated Line Item Improvement
Technical Specification Task Force Traveler TSTF-412, Revision 3,
Provide Actions for One Steam Supply to the Turbine Driven AFW/EFW Pump
Inoperable
1.0 Introduction
By application dated [DATE], [LICENSEE NAME] (the licensee),
submitted a request for changes to the [PLANT NAME], Technical
Specifications (TS) (Agencywide Documents Access and Management System
(ADAMS) Accession No. [MLxxxxxxxxx]). The requested change would
establish a Completion Time for the Condition where one steam supply to
the turbine driven AFW/EFW pump is inoperable concurrent with an
inoperable motor driven AFW/EFW train and establish specific Conditions
and Required Actions when two motor driven AFW/EFW trains are
inoperable at the same time and the turbine driven AFW/EFW train is
inoperable either (a) due solely to one inoperable steam supply, or (b)
due to reasons other than one inoperable steam supply.
These changes were described in a Notice of Availability published
in the Federal Register on [DATE ] ([xx FR xxxxx]).
2.0 Regulatory Evaluation
In 10 CFR 50.36, the Commission established its regulatory
requirements related to the content of Technical Specifications (TS).
Pursuant to 10 CFR 50.36(c), TS are required to include items in the
following categories: (1) Safety limits, limiting safety system
settings, and limiting control settings; (2) limiting conditions for
operation (LCOs); (3) surveillance requirements (SRs); (4) design
features; and (5) administrative controls. The rule does not specify
the particular requirements to be included in a plant's TS.
3.0 Technical Evaluation
TS 3.7.5, Auxiliary Feedwater (AFW)/Emergency Feedwater (EFW) System
The AFW/EFW System is designed to automatically supply sufficient
water to the steam generator(s) to remove decay heat upon the loss of
normal feedwater supply with steam generator pressure at the set point
of the Main Steam Safety Valves (MSSVs). Subsequently, the AFW/EFW
System supplies sufficient water to cool the unit to Residual Heat
Removal (RHR) System entry conditions, with steam being released
through the Atmospheric Dump Valves (ADVs).
AFW/EFW Systems typically consist of two motor driven AFW/EFW pumps
and one steam turbine driven pump configured into three trains. The
capacity of the motor driven and steam driven AFW/EFW pumps can vary by
plant. Motor driven pumps typically provide 50% or 100% of the required
AFW/EFW flow capacity as assumed in the accident analysis. Motor driven
AFW/EFW pumps are typically powered from an independent Class 1E power
supply and each pump train typically feeds half of the steam
generators, although each pump has the capability to be realigned from
the control room to feed other steam generators. The steam turbine
driven AFW/EFW pump provides either 100% or 200% of the required
capacity to all steam generators. The steam turbine driven pump
receives steam from two main steam lines upstream of the main steam
isolation valves. Each of the steam feed lines will supply 100% of the
requirements of the turbine driven AFW/EFW pump.
LCO 3.7.5, Condition A (as Proposed)
Condition A is modified to refer to the inoperability of a turbine
driven AFW/EFW train due to an inoperable steam supply, instead of
referring to the inoperability of a turbine driven AFW/EFW pump. This
change is being proposed in order to make Condition A train oriented
instead of component oriented, consistent with the other Conditions
that are included in STS 3.7.5. The train oriented approach is
consistent with the preferred approach that is generally reflected in
the STS, and therefore the proposed change is considered to be
acceptable.
STS 3.7.5, Condition C (as Proposed)
A new Condition C with two possible Required Actions (C.1 OR C.2)
is proposed for the turbine driven AFW/EFW train being inoperable due
to one inoperable steam supply and one motor driven AFW/EFW train being
inoperable
[[Page 11917]]
at the same time. Required Action C.1 requires restoration of the
affected steam supply to operable status within either 24 or 48 hours,
depending on the capability of the motor driven AFW/EFW train that
remains operable. Alternatively, Required Action C.2 requires
restoration of the inoperable motor driven AFW/EFW train within either
24 or 48 hours, again depending on the capability of the motor driven
AFW/EFW train that remains operable. New Condition C provides two
proposed Completion Times that are dependent upon the capacity of the
remaining operable motor driven AFW/EFW train to provide AFW/EFW to the
steam generators.
A proposed 24 hour Completion Time is applicable to plants that may
provide insufficient flow to the steam generators (SGs) in accordance
with accident analyses assumptions if a main steam line break (MSLB) or
feedwater line break (FLB) were to occur that renders the remaining
steam supply to the turbine driven AFW/EFW pump inoperable (a
concurrent single failure is not assumed). Insufficient feedwater flow
could result, for example, if a single motor driven AFW/EFW train does
not have sufficient capacity to satisfy accident analyses assumptions,
or if the operable pump is feeding the faulted SG (i.e. the SG that is
aligned to the operable steam supply for the turbine driven AFW/EFW
pump). [This would typically apply to plants with each AFW/EFW motor
driven pump having less than 100% of the required flow.] Likewise, a
proposed 48 hour Completion Time is applicable when the remaining
operable motor driven AFW/EFW train is capable of providing sufficient
feedwater flow in accordance with accident analyses assumptions. [This
would typically apply to plants with each AFW/EFW motor driven pump
having greater than or equal to 100% of the required flow.]
The STS typically allows a 72 hour Completion Time for Conditions
where the remaining operable equipment is able to mitigate postulated
accidents without assuming a concurrent single active failure. In this
particular case, a 24 hour Completion Time is proposed for the
situation where the AFW/EFW system would be able to perform its
function for most postulated events, and would only be challenged by a
MSLB or FLB that renders the remaining operable steam supply to the
turbine driven AFW/EFW pump inoperable. Additionally, depending on the
capacity of the operable motor driven AFW/EFW pump, it may be able to
mitigate MSLB and FLB accidents during those instances when it is not
aligned to the faulted SG. The selection of 24 hours for the Completion
Time is based on the remaining operable steam supply to the turbine
driven AFW/EFW pump and the continued functionality of the turbine
driven AFW/EFW train, the remaining operable motor driven AFW/EFW
train, and the low likelihood of an event occurring during this 24 hour
period that would challenge the capability of the AFW/EFW system to
provide feedwater to the SGs. The proposed Completion Time for this
particular situation is consistent with what was approved for Waterford
3 by License Amendment 173 for a similar Condition (ADAMS Accession No.
ML012840538), and it is commensurate with the STS in that the proposed
Completion Time is much less than the 72 hours that is allowed for the
situation where accident mitigation capability is maintained.
Therefore, the NRC staff agrees that the proposed 24 hour Completion
Time is acceptable for this particular situation.
A 48 hour Completion Time is proposed for the situation where the
remaining operable motor driven AFW/EFW train is able to mitigate
postulated accidents in accordance with accident analyses assumptions
without assuming a concurrent single active failure. The selection of
48 hours is based on the continued capability of the AFW/EFW system to
perform its function, while at the same time recognizing that this
Condition represents a higher level of degradation than one inoperable
AFW/EFW train which is currently allowed for up to 72 hours by STS
3.7.5. The proposed 48 hour Completion Time represents an appropriate
balance between the more severe 24 hour situation discussed in the
previous paragraph and the less severe Condition that is afforded a 72
hour Completion Time by the current STS. Therefore, the NRC staff
agrees that the proposed 48 hour Completion Time is acceptable for this
particular situation.
STS 3.7.5, Condition D (as Proposed)
The current Condition C is renamed as Condition D. This Condition
has been modified to incorporate changes brought on by the addition of
new Condition C. The first Condition has been modified and now applies
to the situation where the Required Action and associated Completion
Time of Condition A, B, or C are not met. This section of Condition D
is modified to also apply to the new Condition C when the Completion
Time that is specified for new Condition C is not met. The NRC staff
considers this to be appropriate and consistent with existing STS 3.7.5
requirements to place the plant in a mode where the Condition does not
apply when the Required Actions are not met.
The second Condition following the first ``OR'' in Condition D is
modified from ``Two AFW/EFW trains inoperable in MODE 1, 2, or 3'' to
``Two AFW/EFW trains inoperable in MODE 1, 2, or 3 for reasons other
than Condition C.'' This change is necessary to recognize the situation
specified by Condition C (as proposed) where one motor driven AFW/EFW
train is allowed to be inoperable at the same time that the turbine
driven AFW/EFW train is inoperable due to an inoperable steam supply to
the pump turbine. Therefore, the NRC staff considers the proposed
change to be acceptable.
The Required Actions associated with this Condition were renamed
from C.1 AND C.2 to D.1 AND D.2 but not otherwise changed. Required
Action D.1 requires the plant to be in Mode 3 in 6 hours, and Required
Action D.2 requires the plant to be in Mode 4 in 18 hours. This change
is purely editorial as no other changes are involved. Therefore, this
proposed change is acceptable.
STS 3.7.5, Condition E (as Proposed)
Because current Condition C is renamed as Condition D, current
Condition D is renamed as Condition E. This change is purely editorial
as no other changes are involved. Therefore, the proposed change is
acceptable.
STS 3.7.5, Condition F (as Proposed)
Because current Condition D is renamed as Condition E, current
Condition E is renamed as Condition F. This change is purely editorial
as no other changes are involved. Therefore, the proposed change is
acceptable.
STS 3.7.5, Bases (as Proposed)
Though changes to the STS Bases do not require NRC approval per se,
changes to the STS Bases were reviewed to assess their consistency with
the proposed changes to STS 3.7.5. The proposed changes to the STS
Bases appeared to be consistent with the proposed changes to STS 3.7.5.
4.0 State Consultation
In accordance with the Commission's regulations, the [STATE] State
official was notified of the proposed issuance of the amendments. The
State official had [(1) no comments or (2) the following comments--with
subsequent disposition by the NRC staff].
5.0 Environmental Consideration
The amendment changes a requirement with respect to the
installation or use of a facility component located within the
restricted
[[Page 11918]]
area as defined in 10 CFR Part 20 and changes 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 [(1) no public comment on such
finding (2) the following comments with subsequent disposition by the
NRC staff ([xx FR xxxxx, DATE]). 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 Commission has concluded, based on the considerations discussed
above, that (1) there is reasonable assurance that the health and
safety of the public will not be endangered by operation in the
proposed manner, (2) such activities will be conducted in compliance
with the Commission's regulations, and (3) the issuance of the
amendments will not be inimical to the common defense and security or
to the health and safety of the public.
The proposed changes are consistent with NRC practices and policies
as generally reflected in the STS and as reflected by applicable
precedents that have been approved. Therefore, the NRC staff has
determined that the proposed changes to STS 3.7.5 should be approved.
Model No Significant Hazards Consideration Determination
Description of amendment request: The requested change, applicable
to all pressurized water reactors (PWRs) designed by Babcock and Wilcox
(B&W), Westinghouse, and Combustion Engineering (CE), would provide
changes to the Actions in the Standard Technical Specifications (STS)
relating to One Steam Supply to Turbine Driven Auxiliary Feedwater/
Emergency Feedwater (AFW/EFW) Pump Inoperable. The proposed change is
described in Technical Specification Task Force (TSTF) Standard TS
Change Traveler TSTF-412, Revision 3, and was described in the Notice
of Availability published in the Federal Register on [DATE] ([xx FR
xxxxx]).
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:
1. Does the proposed change involve a significant increase in
the probability or consequences of any accident previously
evaluated?
Response: No.
The Auxiliary/Emergency Feedwater (AFW/EFW) System is not an
initiator of any design basis accident or event, and therefore the
proposed changes do not increase the probability of any accident
previously evaluated. The proposed changes to address the condition
of one or two motor driven AFW/EFW trains inoperable and the turbine
driven AFW/EFW train inoperable due to one steam supply inoperable
do not change the response of the plant to any accidents.
The proposed changes do not adversely affect accident initiators
or precursors nor alter the design assumptions, conditions, and
configuration of the facility or the manner in which the plant is
operated and maintained. The proposed changes do not adversely
affect the ability of structures, systems, and components (SSCs) to
perform their intended safety function to mitigate the consequences
of an initiating event within the assumed acceptance limits. The
proposed changes do not affect the source term, containment
isolation, or radiological release assumptions used in evaluating
the radiological consequences of any accident previously evaluated.
Further, the proposed changes do not increase the types and amounts
of radioactive effluent that may be released offsite, nor
significantly increase individual or cumulative occupational/public
radiation exposures.
Therefore, the changes do not involve a significant increase in
the probability or consequences of any accident previously
evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes do not result in a change in the manner in
which the AFW/EFW System provides plant protection. The AFW/EFW
System will continue to supply water to the steam generators to
remove decay heat and other residual heat by delivering at least the
minimum required flow rate to the steam generators. There are no
design changes associated with the proposed changes. The changes to
the Conditions and Required Actions do not change any existing
accident scenarios, nor create any new or different accident
scenarios.
The changes do not involve a physical alteration of the plant
(i.e., no new or different type of equipment will be installed) or a
change in the methods governing normal plant operation. In addition,
the changes do not impose any new or different requirements or
eliminate any existing requirements. The changes do not alter
assumptions made in the safety analysis. The proposed changes are
consistent with the safety analysis assumptions and current plant
operating practice.
Therefore, the changes do not create the possibility of a new or
different kind of accident from any accident previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed changes do not alter the manner in which safety
limits, limiting safety system settings or limiting conditions for
operation are determined. The safety analysis acceptance criteria
are not impacted by these changes. The proposed changes will not
result in plant operation in a configuration outside the design
basis.
Therefore, it is concluded that the proposed change does not
involve a significant reduction in a margin of safety.
Based on the above, the proposed change involves 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 xx day of xxxxxxx, 2007.
For the Nuclear Regulatory Commission.
Project Manager.
Plant Licensing Branch [ ], Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E7-4675 Filed 3-13-07; 8:45 am]
BILLING CODE 7590-01-P