[Federal Register Volume 71, Number 223 (Monday, November 20, 2006)]
[Notices]
[Pages 67170-67175]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 06-9330]
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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 Deletion of E Bar Definition and Revision to Reactor Coolant
System Specific Activity Technical Specification; Babcock and Wilcox
Pressurized Water Reactors, Westinghouse Pressurized Water Reactors,
Combustion Engineering Pressurized Water Reactors 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 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
deletion of E Bar (average disintegration energy, E) definition and
revision to reactor coolant system (RCS) specific activity technical
specification. This request revises the RCS specific activity
specification for pressurized water reactors to utilize a new
indicator, Dose Equivalent Xenon-133 instead of the current indicator
known as E Bar.
The purpose of these models is to permit the NRC to efficiently
process amendments to incorporate these changes into plant-specific
Technical Specifications (TS) for Babcock and Wilcox, Westinghouse, and
Combustion Engineering Pressurized Water Reactors (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 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, 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, 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: Trent Wertz, 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) 415-1568.
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
[[Page 67171]]
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 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 comment on a proposed change to the STS that
deletes the E Bar definition and revises the RCS specific activity
technical specification of the Babcock and Wilcox PWR STS, Revision 3
of NUREG-1430, Westinghouse PWR STS Revision 3 NUREG-1431, and
Combustion Engineering PWR STS Revision 3 NUREG-1432. 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
webpage. 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 replacement of the current PWR TS 3.4.16
limits on RCS gross specific activity with a new limit on RCS noble gas
specific activity. The noble gas specific activity limit would be based
on a new dose equivalent Xe-133 (DEX) definition that would replace the
current E-Bar average disintegration energy definition. In addition,
the current dose equivalent I-131 (DEI) definition would be revised to
allow the use of additional thyroid dose conversion factors (DCFs). By
letter dated September 13, 2005, the Technical Specifications Task
Force (TSTF) proposed these changes for incorporation into the STS as
TSTF-490, Revision 0.
Applicability
These proposed changes will revise the definition of DOSE
EQUIVALENT I-131, delete the definition of ``E-Bar,'' AVERAGE
DISINTEGRATION ENERGY, add a new definition for DOSE EQUIVALENT XE-133,
and revise LCO 3.4.16 for Babcock and Wilcox, Westinghouse, and
Combustion Engineering PWRs, STS NUREGs 1430, 1431, and 1432.
To efficiently process the incoming license amendment applications,
the NRC staff requests that each licensee applying for the changes
addressed by TSTF-490, 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 amendment requests, may result in staff rejection of the
CLIIP adoption request. Instead, licensees desiring significant
variations and/or additional changes should submit a non-CLIIP LAR that
does not request to adopt TSTF-490 via CLIIP.
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 will announce the revised
requirements for each plant that applies for and receives the requested
change.
Dated at Rockville, Maryland this 14th day of November, 2006.
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-490, Revision 0 ``deletion of E-bar definition
and revision to RCS Specific Activity Tech Spec.'' The model
provides the expected level of detail and content for an application
to adopt TSTF-490, 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-490, Revision 0,
``deletion of E-bar definition and revision to RCS Specific Activity
Tech Spec''
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 replace the current pressurized water reactor (PWR)
Technical Specification (TS) 3.4.16 limits on reactor coolant system
(RCS) gross specific activity with a new limit on RCS noble gas
specific activity. The noble gas specific activity limit would be
based on a new dose equivalent Xe-133 (DEX) definition that would
replace the current E-Bar (E) average disintegration energy
definition. In addition, the current dose equivalent I-131 (DEI)
definition would be revised to allow the use of additional thyroid
dose conversion factors (DCFs).
The changes are consistent with NRC-approved Industry Technical
Specification Task Force (TSTF) Standard Technical Specification
Change Traveler, TSTF-490, Revision 0, ``Deletion of E-Bar
Definition and Revision to RCS Specific Activity Tech Spec.'' The
availability of this TS improvement was announced in the Federal
Register on [DATE] ([ ]FR[ ]) as part of the Consolidated Line Item
Improvement Process (CLIIP).
Enclosure 1 provides a description and assessment of the
proposed changes, as well as confirmation of applicability.
Enclosure 2 provides the existing TS pages and TS Bases marked-up to
show the proposed changes. Enclosure 3 provides final TS pages and
TS Bases pages.
[LICENSEE] requests approval of the proposed license amendment
by [DATE], with the amendment being implemented [BY DATE OR WITHIN X
DAYS]. In accordance with 10 CFR 50.91, a copy of this application,
with enclosures, is being provided to the designated [STATE]
Official.
I declare 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]
[[Page 67172]]
cc: NRR Project Manager, Regional Office, Resident Inspector,
State Contact, ITSB Branch Chief.
Enclosure 1--Description and Assessment of Proposed Changes
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 replace the current limits on primary
coolant gross specific activity with limits on primary coolant noble
gas activity. The noble gas activity would be based on DOSE
EQUIVALENT XE-133 and would take into account only the noble gas
activity in the primary coolant.
Technical Specification Task Force (TSTF) change traveler TSTF-
490, Revision 0, ``Deletion of E Bar Definition and Revision to RCS
Specific Activity Tech Spec'' 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-490, Revision 0, the proposed
TS changes include:
Revised definition of DOSE EQUIVALENT I-131
Deletion of the definition of ``E-Bar, AVERAGE
DISINTEGRATION ENERGY
Adding a new definition for DOSE EQUIVALENT XE-133
Revised LCO 3.4.16, ``RCS Specific Activity'' to delete
references to gross specific activity, and reference limits on DOSE
EQUIVALENT I-131 and DOSE EQUIVALENT XE-133, and delete Figure
3.4.16-1, ``Reactor Coolant DOSE EQUIVALENT I-131 Specific Activity
Limit versus Percent of RATED THERMAL POWER.''
Revised Applicability of LCO 3.4.16 to indicate the LCO
is applicable in MODES 1,2,3, and 4
[Modified ACTIONS Table as follows:
A. Condition A is modified to delete the reference to Figure 3.4.16-
1, and define an upper limit that is applicable at all power levels.
B. NUREG-1430 and NUREG-1432 ACTIONS are reordered, moving Condition
C to Condition B.
C. Condition B (was Condition C in NUREG-1430 and NUREG 1432) is
modified to provide a Condition and Required Action for DOSE
EQUIVALENT XE-133 instead of gross specific activity. The Completion
Time is changed from 6 hours to 48 hours. A Note stating the
applicability of LCO 3.0.4.c is added, consistent with the Note to
Required Action A.1.
D. Condition C (was Condition B in NUREG-1430 and NUREG-1432) is
modified based on the changes to Conditions A and B and to reflect
the change in the LCO Applicability]
Revised SR 3.4.16.1 to verify the limit for DOSE
EQUIVALENT XE-133. A Note is added, consistent with SR 3.4.16.2 to
allow entry into MODES 4,3, and 2 prior to performance of the SR.
Deleted SR 3.4.16.3
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-490, Revision 0.
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
Availability. [LICENSEE] has applied the methodology in Reference 1
to develop the proposed TS changes. [LICENSEE] has also concluded
that the justifications presented in TSTF-490, 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-490,
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.
8.0 References
1. Federal Register Notices:
Notice for Comment published on [DATE] ([ ] FR [ ])
Notice of Availability published on [DATE ] ([ ] FR [ ])
MODEL SAFETY EVALUATION
U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Technical Specification Task Force TSTF-490, Revision 0
``Deletion of E-Bar Definition and Revision to RCS Specific Activity
Tech Spec''
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-490, Revision 0,
``Deletion of E Bar Definition and Revision to RCS Specific Activity
Tech Spec'' to the Pressurized Water Reactor (PWR) Standard
Technical Specifications (STS), which was proposed by the Technical
Specifications Task Force (TSTF) by letter on September 13, 2005.
This TSTF involves changes to NUREG-1430, NUREG-1431, and NUREG-1432
Section 3.4.16 limits on reactor coolant system (RCS) gross specific
activity with a new limit on RCS noble gas specific activity. The
noble gas specific activity limit would be based on a new dose
equivalent Xe-133 (DEX) definition that would replace the current E-
Bar average disintegration energy definition. In addition, the
current dose equivalent I-131 (DEI) definition would be revised to
allow the use of additional thyroid dose conversion factors (DCFs).
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) staff evaluated the
impact of the proposed changes as they relate to the radiological
consequences of affected design basis accidents (DBAs) that use the
reactor coolant system (RCS) inventory as the source term. The
source term assumed in radiological analyses should be based on the
activity associated with the projected fuel damage or the maximum TS
RCS values, whichever maximizes the radiological consequences. The
limits on RCS specific activity ensure that the offsite doses are
appropriately limited for accidents that are based on releases from
the RCS with no significant amount of fuel damage.
The Steam Generator Tube Rupture (SGTR) accident and the Main
Steam Line Break (MSLB) accident, with a few exceptions, do not
result in fuel damage and therefore the radiological consequence
analyses are based on the release of primary coolant activity at
maximum TS limits. For accidents that result in fuel damage, the
additional dose contribution from the initial activity in the RCS is
not normally evaluated and is considered to be insignificant in
relation to the dose resulting from the release of fission products
from the damaged fuel.
[For licensees that incorporate the source term as defined in
Technical Information Document (TID) 14844, AEC, 1962, ``Calculation
of Distance Factors for Power and Test Reactors Sites,'' in their
dose consequence analyses, the staff uses the regulatory guidance
provided in NUREG-0800, ``Standard Review Plan (SRP) for the Review
of Safety Analysis Reports for Nuclear Power Plants,'' Section
15.1.5, ``Steam System Piping Failures Inside and Outside of
Containment (PWR),'' Appendix A, ``Radiological Consequences of Main
Steam Line Failures Outside Containment,'' Revision 2, for the
evaluation of MSLB accident analyses and NUREG-0800, SRP Section
15.6.3, ``Radiological Consequences of Steam Generator Tube Failure
(PWR),'' Revision 2, for evaluating SGTR accidents analyses. In
addition, the staff uses the guidance from RG 1.195, ``Methods and
Assumptions for Evaluating Radiological Consequences of Design Basis
Accidents at Light Water Nuclear Power Reactors,'' May 2003, for
those licensees that chose to use its
[[Page 67173]]
guidance for dose consequence analyses using the TID 14844 source
term.]
[For licensees using the alternative source term (AST) in their
dose consequence analyses, the staff uses the regulatory guidance
provided in NUREG-0800, SRP Section 15.0.1, ``Radiological
Consequence Analyses Using Alternative Source Terms,'' Revision 0,
July 2000, and the methodology and assumptions stated in Regulatory
Guide (RG) 1.183, ``Alternative Radiological Source Terms for
Evaluating Design Basis Accidents at Nuclear Power Reactors'', July
2000.]
The applicable dose criteria for the evaluation of DBAs depends
on the source term incorporated in the dose consequence analyses.
[For licensees using the TID 14844 source term, the maximum dose
criteria to the whole body and the thyroid that an individual at the
exclusion area boundary (EAB) can receive for the first 2 hours
following an accident, and at the low population zone (LPZ) outer
boundary for the duration of the radiological release, are specified
in Title 10 of the Code of Federal Regulations (10 CFR) Part 100.11.
These criteria are 25 roentgen equivalent man (rem) total whole body
dose and 300 rem thyroid dose from iodine exposure. The accident
dose criteria in 10 CFR 100.11 is supplemented by accident specific
dose acceptance criteria in SRP 15.1.5, Appendix A, SRP 15.6.3 or
Table 4 of RG 1.195, ``Methods and Assumptions for Evaluating
Radiological Consequences of Design Basis Accidents at Light Water
Nuclear Power Reactors,'' May 2003.]
[For control room dose consequence analyses that use the TID
14844 source term, the regulatory requirement for which the NRC
staff bases its acceptance is General Design Criterion (GDC) 19 of
Appendix A to 10 CFR Part 50, ``Control Room''. GDC 19 requires that
adequate radiation protection be provided to permit access and
occupancy of the control room under accident conditions without
personnel receiving radiation exposures in excess of 5 rem whole
body, or its equivalent to any part of the body, for the duration of
the accident. NUREG-0800, SRP Section 6.4, ``Control Room
Habitability System,'' Revision 2, July 1981, provides guidelines
defining the dose equivalency of 5 rem whole body as 30 rem for both
the thyroid and skin dose. For licensees adopting the guidance from
RG 1.196, ``Control Room Habitability at Light Water Nuclear Power
Reactors,'' May 2003, Section C.4.5 of RG 1.195, May 2003, states
that in lieu of the dose equivalency guidelines from Section 6.4 of
NUREG-0800, the 10 CFR 20.1201 annual organ dose limit of 50 rem can
be used for both the thyroid and skin dose equivalent of 5 rem whole
body.]
[Licensees using the AST are evaluated against the dose criteria
specified in 10 CFR Part 50.67. The off-site dose criteria are 25
rem total effective dose equivalent (TEDE) at the EAB for any 2-hour
period following the onset of the postulated fission product release
and 25 rem TEDE at the outer boundary of the LPZ for the duration of
the postulated fission product release. In addition, 10 CFR Part
50.67 requires that adequate radiation protection be provided to
permit access and occupancy of the control room under accident
conditions without personnel receiving radiation exposures in excess
of 5 rem TEDE for the duration of the accident.]
3.0 TECHNICAL EVALUATION
3.1 Technical Evaluation of TSTF-490 RCS TS Changes
3.1.1 Revision to the Definition of DEI
The list of acceptable DCFs for use in the determination of DEI
include the following:
Table III of TID-14844, AEC, 1962, ``Calculation of
Distance Factors for Power and Test Reactor Sites.''
Table E-7 of Regulatory Guide 1.109, Revision 1, NRC,
1977.
ICRP 30,1979, page 192-212, Table titled ``Committed
Dose Equivalent in Target Organs or Tissues per Intake of Unit
Activity.''
Table 2.1 of EPA Federal Guidance Report No. 11, 1988,
``Limiting Values of Radionuclide Intake and Air Concentration and
Dose Conversion Factors for Inhalation, Submersion, and Ingestion.''
Note: It is incumbent on the licensee to ensure that the DCFs
used in the determination of DEI are consistent with the applicable
dose consequence analyses.
3.1.2 Deletion of the Definition of E-Bar and the Addition of a New
Definition for DE Xe-133
The determination of DEX will be performed in a similar manner
to that currently used in determining DEI, except that the
calculation of DEX is based on the acute dose to the whole body and
considers the noble gases Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-
135m, Xe-135, and Xe-138 which are significant in terms of
contribution to whole body dose. Some noble gas isotopes are not
included due to low concentration, short half life, or small dose
conversion factor. The calculation of DEX would use either the
average gamma disintegration energies for the nuclides or the
effective dose conversion factors from Table III.1 of EPA Federal
Guidance Report No.12, ``External Exposure to Radionuclides in Air,
Water, and Soil'', 1993. Using this approach, the limit on the
amount of noble gas activity in the primary coolant would not
fluctuate with variations in the calculated values of E-Bar. If a
specified noble gas nuclide is not detected, the new definition
states that it should be assumed the nuclide is present at the
minimum detectable activity. This will result in a conservative
calculation of DEX.
When E-Bar is determined using a design basis approach in which
it is assumed that 1.0% of the power is being generated by fuel rods
having cladding defects and it is also assumed that there is no
removal of fission gases from the letdown flow, the value of E-Bar
is dominated by Xe-133. The other nuclides have relatively small
contributions. However, during normal plant operation there are
typically only a small amount of fuel clad defects and the
radioactive nuclide inventory can become dominated by tritium and
corrosion and or activation products, resulting in the determination
of a value of E-Bar that is very different than would be calculated
using the design basis approach. Because of this difference the
accident dose analyses become disconnected from plant operation and
the limiting condition for operation (LCO) becomes essentially
meaningless. It also results in a TS limit that can vary during
operation as different values for E-Bar are determined.
This change will implement a LCO that is consistent with the
whole body radiological consequence analyses which are sensitive to
the noble gas activity in the primary coolant but not to other, non-
gaseous activity currently captured in the E-Bar definition. SR
3.4.16.1 specifies the limit for primary coolant gross specific
activity as 100/E-Bar Ci/gm. The current E-Bar definition includes
radioisotopes that decay by the emission of both gamma and beta
radiation. The current Condition B of LCO 3.4.16 would rarely, if
ever, be met for exceeding 100/E-Bar since the calculated value is
very high (the denominator is very low) if beta emitters such as
tritium (H-3) are included in the determination, as required by the
E-Bar definition.
TS Section 1.1 definition for E--AVERAGE DISINTEGRATION ENERGY
(E-Bar) is deleted and replaced with a new definition for DEX which
states:
``DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133
(microcuries per gram) that alone would produce the same acute dose
to the whole body as the combined activities of noble gas nuclides
Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-
135, and Xe-138 actually present. If a specific noble gas nuclide is
not detected, it should be assumed to be present at the minimum
detectable activity. The determination of DOSE EQUIVALENT XE-133
shall be performed using effective dose conversion factors for air
submersion listed in Table III.1 of EPA Federal Guidance Report No.
12, or the average gamma disintegration energies as provided in ICRP
Publication 38, ``Radionuclide Transformations'' or similar
source.''
The change incorporating the newly defined quantity DEX is
acceptable from a radiological dose perspective since it will result
in an LCO that more closely relates the non-iodine RCS activity
limits to the dose consequence analyses which form their bases.
NOTE: IT IS INCUMBENT ON THE LICENSEE TO ENSURE THAT THE DCFS USED
IN THE DETERMINATION OF DEI AND THE NEWLY DEFINED DEX ARE CONSISTENT
WITH THE DCFS USED IN THE APPLICABLE DOSE CONSEQUENCE ANALYSIS.
3.1.3 Revision of LCO 3.4.16, ``RCS Specific Activity''
LCO 3.4.16 is modified to specify that iodine specific activity
in terms of DEI and noble gas specific activity in terms of DEX
shall be within limits. Currently the limiting indicators are not
explicitly identified in the LCO, but are instead defined in current
Condition C and Surveillance Requirement (SR) 3.4.16.1 for gross
non-iodine specific activity and in current Condition A and SR
3.4.16.2 for iodine specific activity.
The new LCO states ``RCS DOSE EQUIVALENT I-131 and DOSE
EQUIVALENT XE-133 specific activity shall be within limits.'' NOTE:
IT IS INCUMBENT
[[Page 67174]]
ON THE LICENSEE TO ENSURE THAT THE SITE SPECIFIC LIMITS FOR BOTH DEI
AND DEX ARE CONSISTENT WITH THE CURRENT SGTR AND MSLB RADIOLOGICAL
CONSEQUENCE ANALYSES.
TS 3.4.16 Required Action A.1 is revised to remove the reference
to Figure 3.4.16-1 ``Reactor Coolant DOSE EQUIVALENT I-131 Specific
Activity Limit versus Percent of RATED THERMAL POWER'' and insert a
limit of less than or equal to the site specific DEI spiking limit.
Radiological dose consequence analyses for SGTR and MSLB accidents,
which take into account the pre-accident iodine spike, do not
consider the elevated RCS iodine specific activities permitted by
Figure 3.4.16-1 for operation below 80% RTP. Instead, the pre-
accident iodine spike analyses assume a DEI concentration 60 times
higher than the corresponding long term equilibrium value, which
corresponds to the specific activity limit associated with 100% RTP
operation. TS 3.4.16 Required Action A.1 shall be based on the short
term site specific DEI spiking limit to be consistent with the
assumptions contained in the radiological consequence analyses.
3.1.4 TS 3.4.16 Applicability Revision
TS 3.4.16 Applicability is modified to include MODE 3 and MODE
4. It is necessary for the LCO to apply during MODES 1 through 4 to
limit the potential radiological consequences of a SGTR or MSLB that
may occur during these MODES. In MODES 5 and 6, the steam generators
are not used for decay heat removal, the RCS and steam generators
are depressurized, and primary to secondary leakage is minimal.
Therefore, the monitoring of RCS specific activity during MODES 5
and 6 is not required. The change to modify the TS 3.4.16
Applicability to include all of MODE 3 and MODE 4 is necessary to
limit the potential radiological consequences of an SGTR or MSLB
that may occur during these MODES and is therefore acceptable from a
radiological dose perspective.
3.1.5 TS 3.4.16 Condition A Revision
TS 3.4.16 Condition A is revised by replacing the DEI site
specific limit ``> 1.0 [mu]Ci/gm'' with the words ``not within
limit'' to be consistent with the revised TS 3.4.16 LCO format. The
site specific DEI limit of <= [1.0] [mu]Ci/gm and Required Action
A.1 is contained in SR 3.4.16.2. This change will maintain the
consistency of the proposed TS and is acceptable from a radiological
dose perspective.
3.1.6 TS 3.4.16 Condition B Revision to include Action for DEX Limit
TS 3.4.16 Condition C is replaced with a new Condition B for DEX
not within limits. This change is made to be consistent with the
change to the TS 3.4.16 LCO which requires the DEX specific activity
to be within limits as discussed above. The DEX limit is site
specific and the numerical value in units of [mu]Ci/gm is contained
in revised SR 3.4.16.1. The site specific limit of DEX [mu]Ci/gm is
established based on the maximum accident analysis RCS activity
corresponding to 1% fuel clad defects with sufficient margin to
accommodate the exclusion of those isotopes based on low
concentration, short half life, or small dose conversion factors.
The primary purpose of the TS 3.4.16 LCO on RCS specific activity
and its associated Conditions is to support the dose analyses for
DBAs. The whole body dose is primarily dependent on the noble gas
activity, not the non-gaseous activity currently captured in the E-
Bar definition.
The Completion Time for revised TS 3.4.16 Required Action B.1
will require restoration of DEX to within limit in 48 hours. This is
consistent with the Completion Time for current Required Action A.2
for DEI. The radiological consequences for the SGTR and the MSLB
accidents demonstrate that the calculated thyroid doses are
generally a greater percentage of the applicable acceptance criteria
than the calculated whole body doses (operation with iodine specific
activity levels greater than the LCO limit is permissible, if the
activity levels do not exceed the limits shown in Figure 3.4.16-1,
in the applicable specification, for more than 48 hours). Therefore
the Completion Time for noble gas activity being out of
specification in the revised Required Action B.1 should be at least
as great as the Completion Time for iodine specific activity being
out of specification in current Required Action A.2. Therefore the
Completion Time of 48 hours for revised Required Action B.1 is
acceptable from a radiological dose perspective.
3.1.7 TS 3.4.16 Condition C Revision
TS 3.4.16 Condition C is revised to include Condition B (DEX not
within limit) if the Required Action and associated Completion Time
of Condition B is not met. This is consistent with the changes made
to Condition B which now provides the same completion time for both
components of RCS specific activity as discussed in the revision to
Condition B. The revision to Condition C also replaces the limit on
DEI from the deleted Figure 3.4.16-1 with a site specific value of >
[60] [mu]Ci/gm. This change makes Condition C consistent with the
changes made to TS 3.4.16 Required Action A.1.
The change to TS 3.4.16 Required Action C.1 requires the plant
to be in MODE 3 within 6 hours and adds a new Required Action C.2
which requires the plant to be in MODE 5 within 36 hours. These
changes are consistent with the changes made to the TS 3.4.16
Applicability. The revised LCO is applicable throughout all of MODES
1 through 4 to limit the potential radiological consequences of an
SGTR or MSLB that may occur during these MODES. In MODES 5 and 6,
the steam generators are not used for decay heat removal, the RCS
and steam generators are depressurized, and primary to secondary
leakage is minimal. Therefore, the monitoring of RCS specific
activity during MODES 5 and 6 is not required.
A new TS 3.4.16 Required Action C.2 Completion Time of 36 hours
is added for the plant to reach MODE 5. This Completion Time is
reasonable, based on operating experience, to reach MODE 5 from full
power conditions in an orderly manner and without challenging plant
systems and the value of 36 hours is consistent with other TS which
have a Completion Time to reach MODE 5.
3.1.8 SR 3.4.16.1 Revision to include Surveillance for DEX
The change replaces the current SR 3.4.16.1 surveillance for RCS
gross specific activity with a surveillance to verify that the site
specific reactor coolant DEX specific activity is <= [280] [mu]Ci/
gm. This change provides a surveillance for the new LCO limit added
to TS 3.4.16 for DEX. The revised SR 3.4.16.1 surveillance requires
performing a gamma isotopic analysis as a measure of the noble gas
specific activity of the reactor coolant at least once every 7 days
which is the same frequency required under the current SR 3.4.16.1
surveillance for RCS gross non-iodine specific activity. The
surveillance provides an indication of any increase in the noble gas
specific activity. The results of the surveillance on DEX allow
proper remedial action to be taken before reaching the LCO limit
under normal operating conditions.
SR 3.4.16.1 is modified by inclusion of a NOTE which permits the
use of the provisions of LCO 3.0.4.c. This allowance permits entry
into the applicable MODE(S) while relying on the ACTIONS. This
allowance is acceptable due to the significant conservatism
incorporated into the specific activity limit, the low probability
of an event which is limiting due to exceeding this limit, and the
ability to restore transient specific activity excursions while the
plant remains at, or proceeds to power operation. This allows entry
into MODE 4, MODE 3, and MODE 2 prior to performing the
surveillance. This allows the surveillance to be performed in any of
those MODES, prior to entering MODE 1, similar to the current
surveillance SR 3.4.16.2 for DEI.
3.1.9 SR 3.4.16.3 Deletion
The current SR 3.4.16.3 which required the determination of E-
Bar is deleted. TS 3.4.16 LCO on RCS specific activity supports the
dose analyses for DBAs, in which the whole body dose is primarily
dependent on the noble gas concentration, not the non-gaseous
activity currently captured in the E-Bar definition. With the
elimination of the limit for RCS gross specific activity and the
addition of the new LCO limit for noble gas specific activity, this
SR to determine E-Bar is no longer required.
3.2 Precedent
The Technical Specifications developed for the Westinghouse
AP600 and AP1000 advanced reactor designs incorporate an LCO for RCS
DEX activity in place of the LCO on non-iodine gross specific
activity based on E-Bar. This approach was approved by the NRC for
the AP600 in NUREG-1512, ``Final Safety Evaluation Report Related to
the Certification of the AP600 Standard Design, Docket No. 52-003,''
dated August 1998 and for the AP1000 in the NRC letter to
Westinghouse Electric Company dated September 13, 2004. In addition
the curve describing the maximum allowable iodine concentration
during the 48-hour period of elevated activity as a function of
power level, was not included in the TS approved for the AP600 and
AP1000 advanced reactor designs.
[[Page 67175]]
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: [LICENSEE] requests adoption
of an approved change to the standard technical specifications (STS)
for Pressurized Water Reactor (PWR) Plants [NUREG-1430, NUREG-1431,
or NUREG-1432] and the [LICENSEE] technical specifications (TS), to
replace the current limits on primary coolant gross specific
activity with limits on primary coolant noble gas activity. The
noble gas activity would be based on DOSE EQUIVALENT XE-133 and
would take into account only the noble gas activity in the primary
coolant. The changes are consistent with NRC approved Industry/
Technical Specification Task Force (TSTF) Standard Technical
Specification Change Traveler, TSTF-490.
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
Reactor coolant specific activity is not an initiator for any
accident previously evaluated. The Completion Time when primary
coolant gross activity is not within limit is not an initiator for
any accident previously evaluated. The current variable limit on
primary coolant iodine concentration is not an initiator to any
accident previously evaluated. As a result, the proposed change does
not significantly increase the probability of an accident. The
proposed change will limit primary coolant noble gases to
concentrations consistent with the accident analyses. The proposed
change to the Completion Time has no impact on the consequences of
any design basis accident since the consequences of an accident
during the extended Completion Time are the same as the consequences
of an accident during the Completion Time. As a result, the
consequences of any accident previously evaluated are not
significantly increased.
Criterion 2--The Proposed Change Does Not Create the Possibility of
a New or Different Kind of Accident from any Previously Evaluated
The proposed change in specific activity limits does not alter
any physical part of the plant nor does it affect any plant
operating parameter. The change does not create the potential for a
new or different kind of accident from any previously calculated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed change revises the limits on noble gase
radioactivity in the primary coolant. The proposed change is
consistent with the assumptions in the safety analyses and will
ensure the monitored values protect the initial assumptions in the
safety analyses.
Based upon the reasoning presented above and the previous
discussion of the amendment request, the requested change does not
involve a significant hazards consideration.
Dated at Rockville, Maryland, this ----day of --------, XXXX.
For The Nuclear Regulatory Commission
Project Manager, Plant Licensing Branch [ ], Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation
Enclosure 2--[Proposed Technical Specification Changes and
Technical Specification Bases Changes]
Enclosure 3--[Final Technical Specification and Bases Pages]
[FR Doc. 06-9330 Filed 11-17-06; 8:45 am]
BILLING CODE 7590-01-P