[Federal Register Volume 71, Number 242 (Monday, December 18, 2006)]
[Notices]
[Pages 75774-75777]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-21462]
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NUCLEAR REGULATORY COMMISSION
Notice of Opportunity To Comment on Model Safety Evaluation and
Model License Amendment Request on Technical Specification Improvement
Regarding Adding an Action Statement for Two Inoperable Control Room
Air Conditioning Subsystems
AGENCY: Nuclear Regulatory Commission.
ACTION: Request for comment.
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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 Specification (STS) 3.7.5 (STS 3.7.4 for
BWR/6), ``Control Room Air Conditioning (AC) System'' for NUREG-1433
and NUREG-1434. The proposed changes would also revise the Bases for
STS 3.7.5 (STS 3.7.4 for BWR/6). The General Electric Boiling Water
Reactor Owners Group (BWROG) participants in the Technical
Specifications Task Force (TSTF) proposed these changes to the STS in
TSTF-477, Revision 3, ``Add an Action for Two Inoperable Control Room
AC Subsystems.''
The purpose of these models is to permit the NRC to efficiently
process amendments to incorporate changes into plant-specific Technical
Specifications (TS) for General Electric Boiling Water Reactors (BWR).
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.
ADDRESSES: Comments may be submitted either electronically or via U.S.
mail.
Submit written comments to: Chief, Rules and Directives 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, 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: Peter C. Hearn, 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) 415-1189.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process [CLIIP] for Adopting Standard Technical
Specifications 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 STS 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. This notice is
soliciting comments on a proposed change to the STS that adds an action
statement for two inoperable control room subsystems to the General
Electric BWR STS Revision 3.0 of NUREG-1433 and NUREG-1434. 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 for proposed adoption by
licensees. Those licensees opting to apply for the subject change to
TSs are responsible for reviewing the 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 adding an action statement for two inoperable
control room air conditioning subsystems. By letter dated September 8,
2006, the BWROG proposed these changes for incorporation into the STS
as TSTF-477, Revision 3. These changes are accessible electronically
from the Agency-wide Documents Access and Management System's (ADAMS)
Public Electronic Reading Room on the Internet (ADAMS Accession No.
ML062510321) at the NRC Web site http://frwebgate.access.gpo.gov/cgi-bin/leaving.cgi?from=leavingFR.html&log=linklog&to=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 Section 3.7.5 (Section 3.7.4 for
BWR/6) for the General Electric plants.
To efficiently process incoming license amendment applications, the
NRC staff requests that each licensee applying for the changes
addressed by TSTF-477, Revision 3, 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 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-477.
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
[[Page 75775]]
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.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 7th day of December, 2006.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and
Regional Support, Office of Nuclear Reactor Regulation.
ENCLOSURE 1
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 3.7.5
(3.7.4 for BWR/6) ``Control Room Air Conditioning (AC) System'' to add
an action statement for two inoperable control room subsystems.
Technical Specification Task Force (TSTF) change traveler TSTF-477,
Revision 3, ``Add Action for Two Inoperable Control Room AC
Subsystems'' 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-477, Revision 3, the proposed TS
changes include: Add an action statement for two inoperable control
room subsystems.
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-477,
Revision 3.
4.0 Technical Analysis
[LICENSEE] has reviewed References 1 and 2, and the model SE
published on [DATE] ([ ] FR [ ]) as part of the CLIIP Notice for
Comment. [LICENSEE] has applied the methodology in Reference 1 to
develop the proposed TS changes. [LICENSEE] has also concluded that the
justifications presented in TSTF-477, Revision 3 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 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-477, Revision 3.
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.
8.0 References
1. Federal Register Notices: Notice for Comment published on [DATE]
([ ] FR [ ]) Notice of Availability published on [DATE] ([ ] FR [ ])
Enclosure 2
Proposed Technical Specification Changes and Technical
Specification Bases Changes (Mark-Up)
Enclosure 3
Final Technical Specification and Bases Pages
[Clean copies of Licensee specific Technical Specification (TS)
pages, corresponding to the TS pages changed by TSTF-477, Rev 3, are to
be included in Enclosure 3]
Model Safety Evaluation--U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation--Technical Specification Task
Force TSTF-477, Revision 3, ``Add an Action for Two Inoperable Control
Room AC Subsystems.''
1.0 Introduction
By letter dated [--, 20--], [LICENSEE] (the licensee) proposed
changes to the technical specifications (TS) for [PLANT NAME]. The
requested changes are the adoption of TSTF-477, Revision 3, ``Add
Action for Two Inoperable Control Room AC Subsystems'' which was
proposed by the Technical Specification Task Force (TSTF) by letter on
August---- , 2006. The proposed changes revising Technical
Specification 3.7.5 (3.7.4 for BWR/6) ``Control Room Air Conditioning
(AC) System'' involve adding the following Limiting Conditions for
Operation (LCO):
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B. Two [control room AC] B.1 Verify control Once per 4
subsystems inoperable. room area Temperature hours.
< [90] [deg]F.
AND...................
B.2 Restore one 72 hours.
[control room AC] to
OPERABLE status.
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The Technical Specification Task Force (TSTF) change traveler TSTF-
477, Revision 3, was announced for availability in the Federal Register
on [DATE] as part of the consolidated line item improvement process
(CLIIP).
2.0 Regulatory Evaluation
Section 182a of the Atomic Energy Act (the ``Act'') requires
applicants for nuclear power plant operating licenses to include TS as
part of the license. The TS ensure the operational capability of
structures, systems and components that are required to protect the
health and safety of the public. The Commission's regulatory
requirements related to the content of the TS are contained in 10 CFR
Section 50.36. That regulation requires that the TS include items in
the following specific categories: (1) safety limits, limiting safety
systems settings, and limiting control settings
[[Page 75776]]
(50.36(c)(1)); (2) Limiting Conditions for Operation (50.36(c)(2)); (3)
Surveillance Requirements (50.36(c)(3)); (4) design features
(50.34(c)(4)); and (5) administrative controls (50.36(c)(5)).
In general, there are two classes of changes to TS: (1) Changes
needed to reflect modifications to the design basis (TS are derived
from the design basis), and (2) voluntary changes to take advantage of
the evolution in policy and guidance as to the required content and
preferred format of TS over time. This amendment deals with the second
class of changes.
In determining the acceptability of revising STS 3.7.5 (STS 3.7.4
for BWR/6), the staff used the accumulation of generically approved
guidance in NUREG-1433, ``Standard Technical Specifications, Revision 3
General Electric Plants, BWR/4'' dated June, 2004 and; NUREG-1434,
Revision 3, ``Standard Technical Specifications, General Electric
Plants, BWR/6'' dated June, 2004.
Licensees may revise the TS to adopt current improved STS (iSTS)
format and content provided that plant-specific review supports a
finding of continued adequate safety because: (1) The change is
editorial, administrative or provides clarification (i.e., no
requirements are materially altered), (2) the change is more
restrictive than the licensee's current requirement, or (3) the change
is less restrictive than the licensee's current requirement, but
nonetheless still affords adequate assurance of safety when judged
against current regulatory standards. The detailed application of this
general framework, and additional specialized guidance, are discussed
in Section 3.0 in the context of specific proposed changes.
3.0 Technical Evaluation
The BWR STS for the Control Room Air Conditioning AC System do not
contain an Action Statement for two inoperable subsystems. During the
TS Conversion of the BWR/6 Plants, the BWR/6 Plants adopted Action
Statements for the Ventilation and AC systems that contained Action
Statements for 2 inoperable subsystems similar to the proposed Action
Statements in TSTF-477. The STS for numerous safety related systems
also contain Action Statements for 2 inoperable subsystems. The TSTF
proposes to add an Action Statement for 2 inoperable CR AC subsystems
to the BWR STS in order to be consistent with the BWR/6 current iSTS.
Furthermore, the consistency of the BWR STS will be enhanced since most
safety related systems presently have Action Statements in the STS to
address two inoperable subsystems.
3.1 NUREG-1433, Revision 3, ``Standard Technical Specifications,
General Electric Plants, BWR/4''
The proposed BWR/4 Action statement allows 72 hours to restore 1
subsystem to the operable status for 2 inoperable subsystems. During
the 72 hour completion time the CR Temperature is verified < 90 degrees
every 4 hours. If 1 CRAC can not be restored to operable status or the
CR Temperature can not be maintained < 90 degrees then the unit must be
placed in at least Mode 3 within 12 hours and Mode 4 within 36 hours.
Maintaining the CR Temperature < 90 degrees assures that the Safety
Related Equipment in the CR will remain within the original licensed
design operating temperature, because the maximum allowable CR
Temperature is unchanged by TSTF-477. The NRC staff finds that the
proposed changes in TSTF-477 are acceptable for the BWR/4 because the
TSTF-477 changes provide TS requirements that the CR Temperature will
be maintained within the original licensed design operating temperature
of the CR equipment or the plant will be placed in the Cold Shutdown
Mode (Mode 4, Safe Shut Condition).
3.2 NUREG-1434, Revision 3, ``Standard Technical Specifications,
General Electric Plants, BWR/6''
The proposed BWR/6 Action statement allows 7 days to restore 1
subsystem to the operable status for 2 inoperable subsystems. This is
consistent with the current BWR/6 Plants iSTS. During the 7 days
completion time the CR Temperature is verified < 90 degrees every 4
hours. If 1 CR AC cannot be restored to operable status or the CR
Temperature cannot be maintained < 90 degrees then the unit must be
placed in at least Mode 3 within 12 hours and Mode 4 within 36 hours.
Maintaining the CR Temperature < 90 degrees assures that the Safety
Related Equipment in the CR will remain within the original licensed
design operating temperature, because the original allowable CR
Temperature remains unchanged by TSTF-477. The NRC staff confirms that
the proposed changes in TSTF-477 are acceptable for the BWR/6 because
the TSTF-477 changes provide TS requirements that the CR Temperature
will be maintained within the original licensed design operating
temperature of the CR equipment or the plant will be placed in the Cold
Shutdown Mode (Mode 4, Safe Shut Condition).
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 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
amendment will not be inimical to the common defense and security or to
the health and safety of the public. 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 Boiling Water Reactor (BWR) Plants (NUREG-1433
and NUREG-1434) and plant specific technical specifications (TS), to
add an action statement for two inoperable control room subsystems. The
changes are consistent with NRC approved Industry/Technical
Specification Task Force (TSTF) Standard Technical Specifcation Change
Traveler, TSTF-477, Revision 3.
[[Page 75777]]
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--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change is described in Technical Specification Task
Force (TSTF) Standard TS Change Traveler TSTF-477 adds an action
statement for two inoperable control room subsystems.
The proposed change does not involve a physical alteration of the
plant (no new or different type of equipment will be installed). The
proposed changes add an action statement for two inoperable control
room subsystems. The equipment qualification temperature of the control
room equipment is not affected. Future changes to the Bases or
licensee-controlled document will be evaluated pursuant to the
requirements of 10 CFR 50.59, `` Changes, test and experiments'', to
ensure that such changes do not result in more than a minimal increase
in the probability or consequences of an accident previously evaluated.
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 consequences of any accident previously evaluated.
Further, the proposed changes do not increase the types and the amounts
of radioactive effluent that may be released, nor significantly
increase individual or cumulative occupation/public radiation
exposures.
Therefore, the changes do not involve a significant increase in the
probability or consequences of any accident previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of
a New or Different Kind of Accident from any Previously Evaluated
The proposed changes add an action statement for two inoperable
control room subsystems. The changes do not involve a physical altering
of the plant (i.e., no new or different type of equipment will be
installed) or a change in methods governing normal pant operation. The
requirements in the TS continue to require maintaining the control room
temperature within the design limits.
Therefore, the changes do not create the possibility of a new or
different kind of accident from any previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed changes add an action statement for two inoperable
control room subsystems. Instituting the proposed changes will continue
to maintain the control room temperature within design limits. Changes
to the Bases or license controlled document are performed in accordance
with 10 CFR 50.59. This approach provides an effective level of
regulatory control and ensures that the control room temperature will
be maintained within design limits.
The proposed changes maintain sufficient controls to preserve the
current margins of safety.
Based upon the reasoning above, the NRC staff concludes that the
amendment request involves no significant hazards consideration.
For the Nuclear Regulatory Commission.
Project Manager, Plant Licensing Branch [ ], Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E6-21462 Filed 12-15-06; 8:45 am]
BILLING CODE 7590-01-P