67170 Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 

Matters To Be Considered 

Week of November 20, 2006 

There are no meetings scheduled for 

the Week of November 20, 2006. 

Week of November 27, 2006—Tentative 

Thursday, November 30, 2006 

12:55 p.m. Affirmation Session 

(Public Meeting) (Tentative), a. Hydro 

Resources, Inc. (Crownpoint, NM) 

Intervenors’ Petition for Review of LBP–

06–19 (Final Partial Initial Decision—

NEPA Issues) (Tentative). 

Week of December 4, 2006—Tentative 

Thursday, December 7, 2006 

9:30 a.m. Discussion of Management 

Issues (Closed—Ex. 2). 

Week of December 11, 2006—Tentative 

Monday, December 11, 2006 

1:30 p.m. Briefing on Status of 

Decommissioning Activities (Public 

Meeting) (Contact: Keith McConnell, 

301–415–7295). 

This meeting will be Webcast live at 

the Web address—http://www.nrc.gov. 

Tuesday, December 12, 2006 

9:30 a.m. Briefing on Threat 

Environment Assessment (Closed—Ex. 

1) 

1:30 p.m. Discussion of Security 

Issues (Closed—Ex. 1 & 3). 

Wednesday, December 13, 2006 

9:30 a.m. Briefing on Status of Equal 

Employment Opportunity (EEO) 

Programs (Public Meeting) (Contact: 

Barbara Williams, 301–415–7388). 

This meeting will be Webcast live at 

the Web address—http://www.nrc.gov. 

Thursday, December 14, 2006 

9:30 a.m. Meeting with Advisory 

Committee on Nuclear Waste (ACNW) 

(Public Meeting) (Contact: John Larkins, 

301–415–7360). 

This meeting will be webcast live at 

the Web address—http://www.nrc.gov. 

Week of December 18, 2006—Tentative 

There are no meetings scheduled for 

the Week of December 18, 2006. 

Week of December 25, 2006—Tentative 

There are no meetings scheduled for 

the Week of December 25, 2006. 

*The schedule for Commission 

meetings is subject to change on short 

notice. To verify the status of meetings 

call (recording)—301–415–1292. 

Contact person for more information: 

Michelle Schroll, 301–415–1662. 

The NRC Commission Meeting 

Schedule can be found on the Internet 

at: http://www.nrc.gov/what-we-do/ 

policy-making/schedule.html. 

The NRC provides reasonable 

accommodation to individuals with 

disabilities where appropriate. If you 

need a reasonable accommodation to 

participate in these public meetings, or 

need this meeting notice or the 

transcript or other information from the 

public meetings in another format (e.g. 

braille, large print), please notify the 

NRC’s Disability Program Coordinator, 

Deborah Chan, at 301–415–7041,TDD: 

301–415–2100, or by e-mail at 

DLC@nrc.gov. Determinations on 

requests for reasonable accommodation 

will be made on a case-by-case basis. 

This notice is distributed by mail to 

several hundred subscribers; if you no 

longer wish to receive it, or would like 

to be added to the distribution, please 

contact the Office of the Secretary, 

Washington, DC 20555 (301–415–1969). 

In addition, distribution of this meeting 

notice over the Internet system is 

available. If you are interested in 

receiving this Commission meeting 

schedule electronically, please send an 

electronic message to dkw@nrc.gov. 

Dated: November 14, 2006. 

R. Michelle Schroll, 

Office of the Secretary. 

[FR Doc. 06–9292 Filed 11–16–06; 10:17 am] 

BILLING CODE 7590–01–M 

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. 

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: CLIIP@nrc.gov. 

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 


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Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 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 Xe133 (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 NRCapproved 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] 


sroberts on PROD1PC70 with NOTICES
67172 Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 

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 


sroberts on PROD1PC70 with NOTICES
Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 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 Xe133 

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 


sroberts on PROD1PC70 with NOTICES
67174 Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 

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 preaccident 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 

μCi/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] μCi/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 

μCi/gm is contained in revised SR 3.4.16.1. 

The site specific limit of DEX μCi/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] μCi/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] μCi/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. 


sroberts on PROD1PC70 with NOTICES
Federal Register / Vol. 71, No. 223 / Monday, November 20, 2006 / Notices 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-hazardsconsideration 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 llday 

of llll, 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 

OVERSEAS PRIVATE INVESTMENT 

CORPORATION 

Agency Information Collection 

Activities: Proposed Collection; 

Comment Request 

AGENCY: Overseas Private Investment 

Corporation (OPIC). 

ACTION: Request for comments. 

SUMMARY: In compliance with the 

Paperwork Reduction Act (44 U.S.C. 

3501 et seq.), this notice announces that 

OPIC is planning to submit the 

following proposed Information 

Collection Request (ICR) to the Office of 

Management and Budget (OMB): OPIC 

2006 Client Satisfaction Survey. Before 

submitting the ICR to OMB for review 

and approval, OPIC is soliciting public 

comment on the client survey. 

Comments are being solicited on the 

need for the information, its practical 

utility, the accuracy of the Agency’s 

burden estimate, and on ways to 

minimize the reporting burden. The 

proposed ICR is summarized below. 

DATES: All comments must be received 

by OPIC within 60 calendar days from 

the publication date of this Notice. 

ADDRESSES: Information regarding this 

information collection request and/or a 

copy of the survey questions can be 

obtained from the Agency Submitting 

Officer below. Comments on the survey 

should be submitted to the Agency 

Submitting Officer. 

FOR FURTHER INFORMATION CONTACT: 

OPIC Agency Submitting Officer: Essie 

Bryant, Records Manager, Overseas 

Private Investment Corporation, 1100 

New York Avenue, NW., Washington, 

DC 20527, telephone (202) 336–8563. 

SUPPLEMENTARY INFORMATION:

Type of Request: New information 

collection. 

Title: 2006 OPIC Client Satisfaction 

Survey. 

OMB Approval Number: None. 

Frequency of Response: Once per 

client. 

Type of Respondents: Individual 

business officer representatives of U.S. 

companies sponsoring projects overseas. 

Respondent’s Obligation: Voluntary. 

Affected Public: U.S. companies or 

citizens sponsoring projects overseas. 

Estimated Number of Respondents: 

100. 

Estimated time Per Response: 30 

minutes. 

Estimated Total Annual Burden: $0. 

Authority for Information Collection: 

Sections 231 and 234 of the Foreign 

Assistance Act of 1961, as amended. 

Abstract (Needs and Uses of 

Information Collected): OPIC is 


sroberts on PROD1PC70 with NOTICES