[Federal Register Volume 71, Number 208 (Friday, October 27, 2006)]
[Notices]
[Pages 63050-63053]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-18076]
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NUCLEAR REGULATORY COMMISSION
Notice of Availability of Model Safety Evaluation on Technical
Specification Improvement To Modify Requirements Regarding LCO 3.10.1,
Inservice Leak and Hydrostatic Testing Operation 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 Nuclear
Regulatory Commission (NRC) has prepared a model safety evaluation (SE)
relating to the modification of shutdown testing requirements in
technical specifications (TS) for Boiling Water Reactors (BWR). The NRC
staff has also prepared a 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 modify LCO 3.10.1. The proposed changes would revise LCO
3.10.1, and the associated Bases, to expand its scope to include
provisions for temperature excursions greater than [200] [deg]F as a
consequence of inservice leak and hydrostatic testing, and as a
consequence of scram time testing initiated in conjunction with an
inservice leak or hydrostatic test, while considering operational
conditions to be in Mode 4. Licensees of nuclear power reactors to
which the models apply could then request amendments, confirming the
applicability of the SE and NSHC determination to their reactors.
DATES: The NRC staff issued a Federal Register notice on August 21,
2006 (71 FR 48561) that provided a model safety evaluation (SE) and a
model no significant hazards consideration (NSHC) determination
relating to modification of requirements regarding LCO 3.10.1,
``Inservice Leak and Hydrostatic Testing Operation.'' The NRC staff
hereby announces that the model SE and NSHC determination may be
referenced in plant-specific applications to adopt the changes. The
staff will post a model application on the NRC web site to assist
licensees in using the consolidated line item
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improvement process (CLIIP) to revise the TS on LCO 3.10.1, ``Inservice
Leak and Hydrostatic Testing Operation.''
FOR FURTHER INFORMATION CONTACT: Tim Kobetz, Mail Stop: O-12H2,
Division of Inspections and Regional Support, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone 301-415-1932.
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 of NRC licensing processes by processing
proposed changes to the standard technical specifications (STS) in a
manner that supports subsequent license amendment applications. The
CLIIP includes an opportunity for the public to comment on a proposed
change to the STS after a preliminary assessment by the NRC staff and a
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 announce the availability of the change for adoption by
licensees.
This notice involves the modification of LCO 3.10.1. The proposed
changes would revise LCO 3.10.1, and the associated Bases, to expand
its scope to include provisions for temperature excursions greater than
[200] [deg]F as a consequence of inservice leak and hydrostatic
testing, and as a consequence of scram time testing initiated in
conjunction with an inservice leak or hydrostatic test, while
considering operational conditions to be in Mode 4. This change was
proposed for incorporation into the standard technical specifications
by the owners groups participants in the Technical Specification Task
Force (TSTF) and is designated TSTF-484. TSTF-484 can be viewed on the
NRC's web page utilizing the Agencywide Documents Access and Management
System (ADAMS). ADAMS accession numbers are ML052930102 (TSTF-484
Submittal), ML060970568 (NRC Request for Additional Information, RAI),
ML061560523 (TSTF Response to NRC RAIs), and ML062650171 (TSTF Response
to NRC Notice for Comment).
Applicability
Licensees opting to apply for this TS change are responsible for
reviewing the staff's evaluation, referencing the applicable technical
justifications, and providing any necessary plant-specific information.
Each amendment application made in response to the notice of
availability will be processed and noticed in accordance with
applicable rules and NRC procedures.
Public Notices
In a notice in the Federal Register dated August 21, 2006 (71 FR
48561), the staff requested comment on the use of the CLIIP to process
requests to revise the TS regarding LCO 3.10.1, ``Inservice Leak and
Hydrostatic Testing Operation.'' In addition, there have been several
plant-specific amendment requests to adopt changes similar to those
described in TSTF-484 and notices have been published for these
applications. TSTF-484, as well as the NRC staff's safety evaluation
and model application, may be examined, and/or copied for a fee, at the
NRC/s Public Document Room, located at One White Flint North, 11555
Rockville Pike (first floor), Rockville, Maryland. Publicly available
records are accessible electronically from the ADAMS Public Library
component on the NRC Web site, (the Electronic Reading Room).
The staff received one response with seven comments following the
notice published August 21, 2006 (71 FR 48561), soliciting comments on
the model SE and NSHC determination related to TSTF-484, Revision 0.
The comments were offered by the TSTF in a letter dated September 20,
2006 (ADAMS ML062650171). The comments are administrative in
nature in that they provide clarification and do not have a material
impact on the model SE and NSHC determination published August 21, 2006
(71 FR 48561). TSTF comments that were incorporated include the comment
on the Federal Register Notice for Comment and comments 1, 3, 4, and 5
on the Model Safety Evaluation. The TSTF has been informed of NRC staff
decision not to incorporate comments 2 and 6. Comment 2 provides for
additional information about TSTF-484 regarding scram time testing to
be included in paragraph one of section 3.0. In the original Model
Safety Evaluation published for comment on August 21, 2006 (71 FR
48561), the first half of section 3.0 discusses hydrostatic and leakage
testing, while the second half of section 3.0 discusses scram time
testing. NRC staff believe that there may be confusion if the comment
is incorporated into the first section of 3.0 while scram time testing
is not discussed until the second half of section 3.0. The information
provided in the comment is captured in the second half of section 3.0.
Comment 6 was not incorporated due to possible confusion regarding the
term ``conservatively''. In reviewing the TSTF-484, Revision 0
submittal, the NRC has concluded that there is reasonable assurance
that the health and safety of the public will not be endangered by
operation in the proposed manner, such activities will be conducted in
compliance with the Commission's regulations, and the issuance of the
amendment will not be inimical to the common defense and security or to
the health and safety of the public. Therefore, it was decided that
comment 6 was not needed in order to justify TSTF-484, Revision 0
approval. The revised model SE is included in this notice for use by
licensees. As described in the model application prepared by the staff,
licensees may reference in their plant-specific applications to adopt
TSTF-484, the SE and NSHC determination.
Model Safety Evaluation
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor
Regulation, Consolidated Line Item Improvement, Technical Specification
Task Force Change TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time
Testing Activities
1.0 Introduction
By application dated [Date], [Name of Licensee] (the licensee)
requested changes to the Technical Specifications (TS) for the [Name of
Facility].
The proposed changes would revise Limiting Condition for Operation
(LCO) 3.10.1, and the associated Bases, to expand its scope to include
provisions for temperature excursions greater than [200] [deg]F as a
consequence of inservice leak and hydrostatic testing, and as a
consequence of scram time testing initiated in conjunction with an
inservice leak or hydrostatic test, while considering operational
conditions to be in Mode 4.
2.0 Regulatory Evaluation
2.1 Inservice Leak and Hydrostatic Testing. The Reactor Coolant
System (RCS) serves as a pressure boundary and also serves to provide a
flow path for the circulation of coolant past the fuel. In order to
maintain RCS integrity, Section XI of the American Society of
Mechanical Engineers (ASME) Pressure Vessel Code requires periodic
hydrostatic and leakage testing. Hydrostatic tests are required to be
[[Page 63052]]
performed once every ten years and leakage tests are required to be
performed each refueling outage. Appendix G to 10 CFR Part 50 states
that pressure tests and leak tests of the reactor vessel that are
required by Section XI of the American Society of Mechanical Engineers
(ASME) Pressure Vessel Code must be completed before the core is
critical.
NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard
Technical Specifications (STS) and NUREG-1434, General Electric Plants,
BWR/6, Revision 3, STS both currently contain LCO 3.10.1, ``Inservice
Leak and Hydrostatic Testing Operation.'' LCO 3.10.1 was created to
allow for hydrostatic and leakage testing to be conducted while in Mode
4 with average reactor coolant temperature greater than [200] [deg]F
provided certain secondary containment LCOs are met.
TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing
Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO
3.10.1, while hydrostatic and leakage testing is being conducted,
should average reactor coolant temperature exceed [200] [deg]F during
testing. This modification does not alter current requirements for
hydrostatic and leakage testing as required by Appendix G to 10 CFR
Part 50.
2.2 Control Rod Scram Time Testing. Control rods function to
control reactor power level and to provide adequate excess negative
reactivity to shut down the reactor from any normal operating or
accident condition at any time during core life. The control rods are
scrammed by using hydraulic pressure exerted by the control rod drive
(CRD) system. Criterion 10 of Appendix A to 10 CFR part 50 states that
the reactor core and associated coolant, control, and protection
systems shall be designed with appropriate margin to assure that
specified acceptable fuel limits are not exceeded during any condition
of normal operation, including the effects of anticipated operational
occurrences. The scram reactivity used in design basis accidents (DBA)
and transient analyses is based on an assumed control rod scram time.
NUREG-1433, General Electric Plants, BWR/4, Revision 3, STS and
NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both
currently contain surveillance requirements (SR) to conduct scram time
testing when certain conditions are met in order to ensure that
Criterion 10 of Appendix A to 10 CFR Part 50 is satisfied. SR 3.1.4.1
requires scram time testing to be conducted following a shutdown
greater than 120 days while SR 3.1.4.4 requires scram time testing to
be conducted following work on the CRD system or following fuel
movement within the affected core cell. Both SRs must be performed at
reactor steam dome pressure greater than or equal to [800] psig and
prior to exceeding 40 percent rated thermal power (RTP).
TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing
Activities, would modify LCO 3.10.1 to allow SR 3.1.4.1 and SR 3.1.4.4
to be conducted in Mode 4 with average reactor coolant temperature
greater than [200] [deg]F. Scram time testing would be performed in
accordance with LCO 3.10.4, ``Single Control Rod Withdrawal--Cold
Shutdown.'' This modification to LCO 3.10.1 does not alter the means of
compliance with Criterion 10 of Appendix A to 10 CFR Part 50.
3.0 Technical Evaluation
The existing provisions of LCO 3.10.1 allow for hydrostatic and
leakage testing to be conducted while in Mode 4 with average reactor
coolant temperature greater than [200] [deg]F, while imposing Mode 3
secondary containment requirements. Under the existing provision, LCO
3.10.1 would have to be implemented prior to hydrostatic and leakage
testing. As a result, if LCO 3.10.1 was not implemented prior to
hydrostatic and leakage testing, hydrostatic and leakage testing would
have to be terminated if average reactor coolant temperature exceeded
[200] [deg]F during the conduct of the hydrostatic and leakage test.
TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing
Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO
3.10.1, while hydrostatic and leakage testing is being conducted,
should average reactor coolant temperature exceed [200] [deg]F during
testing. The modification will allow completion of testing without the
potential for interrupting the test in order to reduce reactor vessel
pressure, cool the RCS, and restart the test below [200] [deg]F. Since
the current LCO 3.10.1 allows testing to be conducted while in Mode 4
with average reactor coolant temperature greater than [200] [deg]F, the
proposed change does not introduce any new operational conditions
beyond those currently allowed.
SR 3.1.4.1 and SR 3.1.4.4 require that control rod scram time be
tested at reactor steam dome pressure greater than or equal to [800]
psig and before exceeding 40 percent rated thermal power (RTP).
Performance of control rod scram time testing is typically scheduled
concurrent with inservice leak or hydrostatic testing while the RCS is
pressurized. Because of the number of control rods that must be tested,
it is possible for the inservice leak or hydrostatic test to be
completed prior to completing the scram time test. Under existing
provisions, if scram time testing can not be completed during the LCO
3.10.1 inservice leak or hydrostatic test, scram time testing must be
suspended. Additionally, if LCO 3.10.1 is not implemented and average
reactor coolant temperature exceeds [200] [deg]F while performing the
scram time test, scram time testing must also be suspended. In both
situations, scram time testing is resumed during startup and is
completed prior to exceeding 40 percent RTP. TSTF-484, Revision 0, Use
of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to
allow a licensee to complete scram time testing initiated during
inservice leak or hydrostatic testing. As stated earlier, since the
current LCO 3.10.1 allows testing to be conducted while in Mode 4 with
average reactor coolant temperature greater than [200] [deg]F, the
proposed change does not introduce any new operational conditions
beyond those currently allowed. Completion of scram time testing prior
to reactor criticality and power operations results in a more
conservative operating philosophy with attendant potential safety
benefits.
It is acceptable to perform other testing concurrent with the
inservice leak or hydrostatic test provided that this testing can be
performed safely and does not interfere with the leak or hydrostatic
test. However, it is not permissible to remain in TS 3.10.1 solely to
complete such testing following the completion of inservice leak or
hydrostatic testing and scram time testing.
Since the tests are performed with the reactor pressure vessel
(RPV) nearly water solid, at low decay heat values, and near Mode 4
conditions, the stored energy in the reactor core will be very low.
Small leaks from the RCS would be detected by inspections before a
significant loss of inventory occurred. In addition, two low-pressure
emergency core cooling systems (ECCS) injection/spray subsystems are
required to be operable in Mode 4 by TS 3.5.2, ECCS-Shutdown. In the
event of a large RCS leak, the RPV would rapidly depressurize and allow
operation of the low pressure ECCS. The capability of the low pressure
ECCS would be adequate to maintain the fuel covered under the low decay
heat conditions during these tests. Also, LCO 3.10.1 requires that
secondary containment and standby gas treatment system be operable and
capable of handling any
[[Page 63053]]
airborne radioactivity or steam leaks that may occur during performance
of testing.
The protection provided by the normally required Mode 4 applicable
LCOs, in addition to the secondary containment requirements required to
be met by LCO 3.10.1, minimizes potential consequences in the event of
any postulated abnormal event during testing. In addition, the
requested modification to LCO 3.10.1 does not create any new modes of
operation or operating conditions that are not currently allowed.
Therefore, the staff finds the proposed change acceptable.
4.0 State Consultation
In accordance with the Commission's regulations, the [Name of
State] State official was notified of the proposed issuance of the
amendment. The State official had [no] comments. [If comments were
provided, they should be addressed here].
5.0 Environmental Consideration
The amendment changes a requirement with respect to installation or
use of a facility component located within the restricted area as
defined in 10 CFR Part 20. 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 issued on [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.
7.0 References
1. NUREG-1433, ``General Electric Plants, BWR/4, Revision 3,
Standard Technical Specifications (STS)'', August 31, 2003.
2. NUREG-1434, General Electric Plants, BWR/6, Revision 3,
Standard Technical Specifications (STS)'', August 31, 2003.
3. Request for Additional Information (RAI) Regarding TSTF-484,
April 7, 2006, ADAMS accession number ML060970568.
4. Response to NRC RAIs Regarding TSTF-484, June 5, 2006, ADAMS
accession number ML061560523.
5. TSTF-484 Revision 0, ``Use of TS 3.10.1 for Scram Times
Testing Activities'', May 5, 2005, ADAMS accession number
ML052930102.
6. TSTF Response to NRC Notice for Comment, September 20, 2006,
ADAMS accession number ML062650171.
Principal Contributor: Aron Lewin.
Dated at Rockville, Maryland this 12th of October 2006.
For the Nuclear Regulatory Commission.
Timothy Kobetz,
Branch Chief, Technical Specifications Branch, Division of Inspections
and Regional Support, Office of Nuclear Reactor Regulation.
[FR Doc. E6-18076 Filed 10-26-06; 8:45 am]
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