[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: <a href="/cdn-cgi/l/email-protection#094a4540405949677b6a276e667f"><span class="__cf_email__" data-cfemail="e6a5aaafafb6a6889485c8818990">[email protected]</span></a>.
    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:
    <bullet> Revised definition of DOSE EQUIVALENT I-131
    <bullet> Deletion of the definition of ``E-Bar, AVERAGE 
DISINTEGRATION ENERGY
    <bullet> Adding a new definition for DOSE EQUIVALENT XE-133
    <bullet> 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.''
    <bullet> Revised Applicability of LCO 3.4.16 to indicate the LCO 
is applicable in MODES 1,2,3, and 4
    <bullet> [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]

    <bullet> 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.
    <bullet> 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:
    <bullet> Table III of TID-14844, AEC, 1962, ``Calculation of 
Distance Factors for Power and Test Reactor Sites.''
    <bullet> Table E-7 of Regulatory Guide 1.109, Revision 1, NRC, 
1977.
    <bullet> ICRP 30,1979, page 192-212, Table titled ``Committed 
Dose Equivalent in Target Organs or Tissues per Intake of Unit 
Activity.''
    <bullet> 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


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