52268 Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 

DISPOSITION: On July 31, 2008, the staff 

issued the proposed ISG ‘‘Evaluation 

and Acceptance Criteria for 10 CFR 

20.1406 to Support Design Certification 

and Combined License Applications,’’ 

(DC/COL–ISG–06) (ADAMS Accession 

No. ML081850160). There were no 

comments received on the proposed 

ISG. At a March 12, 2009 public meeting 

with Nuclear Energy Institute (NEI) to 

discuss Health Physics Issues for New 

Reactors (ADAMS Accession No. 

ML090890093), the staff provided 

copies of draft Revision 7 of ‘‘Interim 

Staff Guidance for Evaluation and 

Acceptance Criteria for 10 CFR 20.1406 

to Support Design Certification and 

Combined License Applications’’ 

(ADAMS Accession No. ML090640183) 

to NEI and requested input back by 

April 3, 2009. Some of the comments 

received (ADAMS Accession No. 

ML090990781) were subsequently 

incorporated into this document. Staff 

responses to public comments on DC/ 

COL–ISG–06 can be found in ADAMS 

as Accession Number ML092740151. 

ADDRESSES: The NRC maintains 

ADAMS which provides text and image 

files of NRC’s public documents. These 

documents may be accessed through the 

NRC’s Public Electronic Reading Room 

on the Internet at http://www.nrc.gov/ 

reading-rm/adams.html. Persons who 

do not have access to ADAMS or who 

encounter problems in accessing the 

documents located in ADAMS should 

contact the NRC Public Document 

reference staff at 1–800–397–4209, 

301–415–4737, or by e-mail at 

pdr.resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: Mr. 

Timothy J. Frye, Chief, Health Physics 

Branch, Division of Construction 

Inspection and Operational Programs, 

Office of the New Reactors, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; telephone at 301–415– 

3900 or e-mail at timothy.frye@nrc.gov. 

SUPPLEMENTARY INFORMATION: The 

agency posts its issued staff guidance in 

the agency external Web page (http:// 

www.nrc.gov/reading-rm/doccollections/isg/). 

Dated at Rockville, Maryland, this 2nd day 

of October 2009. 

For the Nuclear Regulatory Commission. 

George M. Tartal, 

Acting Branch Chief, Rulemaking and 

Guidance Development Branch, Division of 

New Reactor Licensing, Office of New 

Reactors. 

[FR Doc. E9–24424 Filed 10–8–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Sunshine Act; Federal Register Notice 

AGENCY HOLDING THE MEETINGS: Nuclear 

Regulatory Commission. 

DATE: Week of October 12, 2009. 

PLACE: Commissioners’ Conference 

Room, 11555 Rockville Pike, Rockville, 

Maryland. 

STATUS: Public and Closed. 

ADDITIONAL ITEMS TO BE CONSIDERED: 

Week of October 12, 2009 

Tuesday, October 13, 2009 

9:15 a.m. Affirmation Session (Public 

Meeting) (Tentative). Calvert Cliffs 

3 Nuclear Project LLC & UniStar 

Nuclear Operating Services LLC 

(Combined License App. Calvert 

Cliffs, Unit 3) Docket Nos. 52–016– 

COL, Calvert Cliffs 3 Nuclear 

Project LLC & UniStar Nuclear 

Operating Services, LLC, Appeal 

from LBP–09–4 (Tentative). 

*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: 

Rochelle Bavol, (301) 415–1651. 

The NRC Commission Meeting 

Schedule can be found on the Internet 

at: http://www.nrc.gov/about-nrc/policymaking/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, 

Rohn Brown, at 301–492–2279, TDD: 

301–415–2100, or by e-mail at 

rohn.brown@nrc.gov. Determinations on 

requests for reasonable accommodation 

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

This notice is distributed 

electronically to 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), 

or send an e-mail to 

darlene.wright@nrc.gov. 

Dated: October 5, 2009. 

Rochelle C. Bavol, 

Office of the Secretary. 

[FR Doc. E9–24530 Filed 10–7–09; 4:15 pm] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0444] 

Notice of Opportunity for Public 

Comment on the Proposed Model 

Safety Evaluation for Plant-Specific 

Adoption of Technical Specification 

Task Force Traveler-513, Revision 2, 

‘‘Revise PWR Operability 

Requirements and Actions for RCS 

Leakage Instrumentation’’ 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Notice of opportunity for public 

comment. 

SUMMARY: The NRC is requesting public 

comment on the enclosed proposed 

model safety evaluation, model no 

significant hazards consideration 

determination, and model application 

for plant-specific adoption of Technical 

Specification Task Force (TSTF) 

Traveler-513, Revision 2, ‘‘Revise PWR 

Operability Requirements and Actions 

for RCS Leakage Instrumentation.’’ The 

TSTF Traveler-513, Revision 2, is 

available in the Agencywide Documents 

Access Management System (ADAMS) 

under Accession Number 

ML091810158. The proposed changes 

revise Standard Technical Specification 

(STS) [3.4.15], ‘‘[Reactor Coolant System 

(RCS) Leakage Detection 

Instrumentation].’’ The proposed 

changes also revise the STS Bases to 

clearly define the RCS leakage detection 

instrumentation Operability 

requirements in the Limiting Condition 

for Operation (LCO) Bases, eliminate 

discussion from the STS Bases that 

could be erroneously construed as 

Operability requirements, and reflect 

the changes to the TSs. This model 

safety evaluation will facilitate 

expedited approval of plant-specific 

adoption of TSTF Traveler-513, 

Revision 2. 

DATES: Comment period expires 

November 9, 2009 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: You may submit comments 

by any one of the following methods. 

Please include Docket ID NRC–2009– 

0444 in the subject line of your 

comments. Comments submitted in 

writing or in electronic form will be 

posted on the NRC Web site and on the 

Federal rulemaking Web site 

Regulations.gov. Because your 

comments will not be edited to remove 

any identifying or contact information, 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 52269 

the NRC cautions you against including 

any information in your submission that 

you do not want to be publicly 

disclosed. 

The NRC requests that any party 

soliciting or aggregating comments 

received from other persons for 

submission to the NRC inform those 

persons that the NRC will not edit their 

comments to remove any identifying or 

contact information, and therefore, they 

should not include any information in 

their comments that they do not want 

publicly disclosed. 

Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for documents filed under Docket ID 

NRC–2009–0444. Address questions 

about NRC dockets to Carol Gallagher 

301–492–3668; e-mail 

Carol.Gallagher@nrc.gov. 

Mail comments to: Michael T. Lesar, 

Chief, Rulemaking and Directives 

Branch (RDB), Division of 

Administrative Services, Office of 

Administration, Mail Stop: TWB–05– 

B01M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, or by fax to RDB at (301) 492– 

3446. 

You can access publicly available 

documents related to this notice using 

the following methods: 

NRC’s Public Document Room (PDR): 

The public may examine and have 

copied for a fee publicly available 

documents at the NRC’s PDR, Public 

File Area O1 F21, One White Flint 

North, 11555 Rockville Pike, Rockville, 

Maryland. 

NRC’s Agencywide Documents Access 

and Management System (ADAMS): 

Publicly available documents created or 

received at the NRC are available 

electronically at the NRC’s Electronic 

Reading Room at http://www.nrc.gov/ 

reading-rm/adams.html. From this page, 

the public can gain entry into ADAMS, 

which provides text and image files of 

NRC’s public documents. If you do not 

have access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC’s 

PDR reference staff at 1–800–397–4209, 

301–415–4737, or by e-mail to 

pdr.resource@nrc.gov. The Proposed 

Model Safety Evaluation for PlantSpecific Adoption of TSTF Traveler513, Revision 2, available electronically 

under ADAMS Accession Number 

ML092460664. 

Federal Rulemaking Web site: Public 

comments and supporting materials 

related to this notice can be found at 

http://www.regulations.gov by searching 

on Docket ID: NRC–2009–0444. 

FOR FURTHER INFORMATION CONTACT: Ms. 

Michelle C. Honcharik, Senior Project 

Manager, Special Projects Branch, Mail 

Stop: O–12D1, Division of Policy and 

Rulemaking, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC, 20555– 

0001; telephone 301–415–1774 or e-mail 

at michelle.honcharik@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

Background 

This notice provides an opportunity 

for the public to comment on proposed 

changes to the Standard TS (STS) after 

a preliminary assessment and finding by 

the NRC staff that the agency will likely 

offer the changes for adoption by 

licensees. This notice solicits comment 

on a proposed change to the STS, which 

if implemented by a licensee will 

modify the plant-specific TS. The NRC 

staff will evaluate any comments 

received for the proposed change to the 

STS and reconsider the change or 

announce the availability of the change 

for adoption by licensees. Licensees 

opting to apply for this TS change are 

responsible for reviewing the NRC 

staff’s evaluation, referencing the 

applicable technical justifications, and 

providing any necessary plant-specific 

information. The NRC will process and 

note each amendment application 

responding to the notice of availability 

according to applicable NRC rules and 

procedures. 

Applicability 

TSTF Traveler-513, Revision 2, is 

applicable to pressurized water reactors. 

The Traveler revises the TS and TS 

Bases to clearly define the RCS leakage 

detection instrumentation Operability 

requirements as well as revise 

Conditions and Required Actions 

related to leakage detection 

instrumentation. 

The proposed change does not 

prevent licensees from requesting an 

alternate approach or proposing changes 

other than those proposed in TSTF 

Traveler-513, Revision 2. However, 

significant deviations from the approach 

recommended in this notice or the 

inclusion of additional changes to the 

license require additional NRC staff 

review. This may increase the time and 

resources needed for the review or 

result in NRC staff rejection of the 

license amendment request (LAR). 

Licensees desiring significant deviations 

or additional changes should instead 

submit an LAR that does not claim to 

adopt TSTF Traveler-513, Revision 2. 

Dated at Rockville, Maryland, this 24th day 

of September 2009. 

For the Nuclear Regulatory Commission. 

Stacey L. Rosenberg, 

Chief, Special Projects Branch, Division of 

Policy and Rulemaking, Office of Nuclear 

Reactor Regulation. 

Proposed Model Application for PlantSpecific Adoption of TSTF Traveler513, Revision 2, ‘‘Revise PWR 

Operability Requirements and Actions 

for RCS Leakage Instrumentation’’ 

U.S. Nuclear Regulatory Commission, 

Document Control Desk, Washington, 

DC 20555. 

Subject: [Plant Name] 

DOCKET NO. 50–[XXX] 

LICENSE AMENDMENT REQUEST 

FOR ADOPTION OF TECHNICAL 

SPECIFICATION TASK FORCE 

(TSTF) TRAVLER-513, REVISION 

2, ‘‘REVISE PWR OPERABILITY 

REQUIREMENTS AND ACTIONS 

FOR RCS LEAKAGE 

INSTRUMENTATION’’ 

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 NO.]. 

The proposed amendment would 

revise the TS and TS Bases to clearly 

define the Reactor Coolant System (RCS) 

leakage detection instrumentation 

Operability requirements as well as 

revise Conditions and Required Actions 

related to leakage detection 

instrumentation. The revised Required 

Actions employ alternate methods of 

monitoring RCS leakage when one or 

more required monitors are inoperable. 

This change is consistent with NRC 

approved Revision 2 to TSTF Improved 

Standard Technical Specification (STS) 

Change Traveler-513, ‘‘Revise PWR 

Operability Requirements and Actions 

for RCS Leakage Instrumentation’’ 

[Discuss any differences with Traveler513, Revision 2.] 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). 

The proposed amendment contains a 

less restrictive TS change. The less 

restrictive change is justified because 

alternate RCS leakage monitoring 

methods are required to be performed 

when no required monitoring methods 

are Operable. Further detailed 

justification is contained in Attachment 

1. 

Attachment 1 provides a description 

of the proposed change. Attachment 2 

provides the existing TS pages marked 

to show the proposed change. 

Attachment 3 provides the existing TS 

mstockstill on DSKH9S0YB1PROD with NOTICES

52270 Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 

Bases pages marked up to show the 

proposed change. Attachment 4 

provides the proposed TS changes in 

final typed format. Attachment 5 

provides the proposed TS Bases changes 

in final typed format. Attachment 6 

provides the regulatory commitment[s]. 

[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, 

‘‘Notice for Public Comment; State 

Consultation,’’ a copy of this 

application, with attachments, is being 

provided to the designated [STATE] 

Official. 

I declare [or certify, verify, state] 

under penalty of perjury that the 

foregoing is correct and true. 

Executed on [date] [Signature]. 

If you should have any questions 

about this submittal, please contact 

[NAME, TELEPHONE NUMBER]. 

Sincerely, 

[Name, Title] 

Attachments: 1. Evaluation of Proposed 

Change 

2. Proposed Technical Specification 

Changes (Mark-Up) 

3. Proposed Technical Specification 

Bases Changes (Mark-Up) 

4. Proposed Technical Specification 

Change (Re-Typed) 

5. Proposed Technical Specification 

Bases Changes (Re-Typed) 

6. List of Regulatory Commitments 

cc: [NRR Project Manager] 

[Regional Office] 

[Resident Inspector] 

[State Contact] 

Evaluation of Proposed Change 

1.0 Description 

The proposed amendment would 

revise the Technical Specification (TS) 

and TS Bases to clearly define the 

Reactor Coolant System (RCS) leakage 

detection instrumentation Operability 

requirements as well as revise 

Conditions and Required Actions 

related to leakage detection 

instrumentation. This change is 

consistent with NRC-approved Revision 

2 to Technical Specification Task Force 

(TSTF) Improved Standard Technical 

Specification (STS) Change Traveler513, ‘‘Revise PWR Operability 

Requirements and Actions for RCS 

Leakage Instrumentation.’’ [Minor 

differences between the proposed plantspecific TS changes, and the changes 

proposed by Traveler-513 are listed in 

Section 2.0.] 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). 

2.0 Proposed Change 

Consistent with the NRC-approved 

Revision 2 of Traveler-513, the proposed 

changes revise and add a new Condition 

to TS [3.4.15], ‘‘[RCS Leakage Detection 

Instrumentation],’’ and revise the 

associated bases. New Condition [D] is 

applicable when the containment 

atmosphere gaseous radioactivity 

monitor is the only Operable monitor 

(i.e., all other monitors are inoperable). 

The Required Actions require analyzing 

grab samples of the containment 

atmosphere or performing an RCS water 

inventory balance every 12 hours and 

restoring another monitor within 7 days. 

Existing Condition [F] applies when all 

required monitors are inoperable and 

requires immediate entry into Limiting 

Condition for Operation (LCO) 3.0.3. 

This Condition is revised to require 

obtaining and analyzing a containment 

atmosphere grab sample and 

performance of an RCS water inventory 

balance every 6 hours. At least one RCS 

leakage detection monitor must be 

restored within 72 hours or a plant 

shutdown is required. Existing 

Condition [E] applies when the 

Required Actions and associated 

Completion Times are not met. It is 

moved to the last Condition and applies 

to all the previous Conditions. The TS 

Bases are revised to clearly define the 

RCS leakage detection instrumentation 

Operability requirements in the LCO 

Bases, eliminate discussion from the 

Bases that could be erroneously 

construed as Operability requirements, 

and reflect the changes to the TSs. 

[The proposed changes also correct 

inappropriate references to ‘‘required’’ 

equipment in TS [3.4.15]. In several 

locations the specifications incorrectly 

refer to a ‘‘required’’ [equipment name]. 

The term ‘‘required’’ is reserved for 

situations in which there are multiple 

ways to meet the LCO, such as the 

requirement for either a gaseous or 

particulate radiation monitor. The 

incorrect use of the term ‘‘required’’ is 

removed from TS [3.4.15] Conditions 

[A, B, and C]. 

[LICENSEE] is [not] proposing 

variations or deviations from the TS 

changes described in Traveler-513, 

Revision 2, or the NRC staff’s model 

safety evaluation published on [DATE] 

([ ] FR [ ]) as part of the CLIIP Notice 

of Availability. [Discuss any differences 

with Traveler-513, Revision 2 and the 

effect of any changes on the NRC staff’s 

model safety evaluation.] 

3.0 Background 

The background for this application is 

adequately addressed by the NRC Notice 

of Availability published on [DATE] 

([ ] FR [ ]). 

4.0 Technical Analysis 

The proposed amendment contains a 

less restrictive TS change to existing 

Condition [F]. The proposed Required 

Actions for Condition [F] would 

eliminate the requirement to 

immediately enter LCO 3.0.3 and would 

add the requirement to analyze grab 

samples of the containment atmosphere 

once per 6 hours, perform an RCS water 

inventory balance once per 6 hours per 

Surveillance Requirement 3.4.13.1, and 

restore at least one RCS leakage 

detection monitor to Operable status 

within 72 hours. The less restrictive 

change is justified because alternate 

RCS leakage monitoring methods are 

required to be performed when no 

monitoring methods are operable. These 

alternate methods provide an RCS 

leakage detection capability similar to 

the required methods. The RCS mass 

balance is capable of identifying a one 

gallon per minute (gpm) RCS leak rate 

and uses instrumentation readily 

available to control room operators. The 

grab sample has an RCS leakage 

detection capability that is comparable 

to that of the containment particulate 

radiation monitor. The proposed 

Actions and Completion Times for grab 

samples and mass balance calculations 

are adequate because use of frequent 

grab samples and RCS mass balance 

calculations provide assurance that any 

significant RCS leakage will be detected 

prior to significant RCS pressure 

boundary degradation. The proposed 72 

hour Completion Time for Restoration 

of at least one RCS leakage detection 

monitor to Operable status is 

appropriate given the low probability of 

significant RCS leakage during the time 

when no required RCS leakage detection 

monitors are Operable, and the need for 

time to restore at least one monitor to 

Operable status. 

[LICENSEE] has reviewed the safety 

evaluation published on [DATE] 

([ ] FR [ ]) as part of the CLIIP Notice 

of Availability. [LICENSEE] has 

concluded that the technical 

justifications presented in the safety 

evaluation prepared by the NRC staff are 

applicable to [PLANT, UNIT NO.]. 

5.0 Regulatory Safety Analysis 

5.1 No Significant Hazards 

Determination 

[LICENSEE] has reviewed the no 

significant hazards determination 

published on [DATE] ([] FR []) as part 

of the CLIIP Notice of Availability. 

[LICENSEE] and has concluded that the 

determination presented in the notice is 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 52271 

applicable to [PLANT, UNIT NO.]. 

[LICENSEE] has evaluated the proposed 

changes to the TS using the criteria in 

10 CFR 50.92 and has determined that 

the proposed changes do not involve a 

significant hazards consideration. An 

analysis of the issue of no significant 

hazards consideration is presented 

below: 

[LICENSEE INSERT ANALYSIS 

HERE.] 

5.2 Applicable Regulatory 

Requirements/Criteria 

A description of the proposed TS 

change and its relationship to applicable 

regulatory requirements was provided 

in the NRC Notice of Availability 

published on [DATE] ([] FR []). 

[LICENSEE] has reviewed the NRC 

staff’s model safety evaluation 

published on [DATE] ([] FR[]) as part of 

the CLIIP Notice of Availability and 

concluded that the regulatory evaluation 

section is applicable to [PLANT, UNIT 

NO.]. 

6.0 Environmental Consideration 

[LICENSEE] has reviewed the 

environmental evaluation included in 

the model safety evaluation published 

on [DATE] ([] FR []) as part of the CLIIP 

Notice of Availability. [LICENSEE] has 

concluded that the NRC staff’s findings 

presented in that evaluation are 

applicable to [PLANT, NO.]. 

The proposed change would change a 

requirement with respect to installation 

or use of a facility component located 

within the restricted area, as defined in 

10 CFR 20, and would change an 

inspection or surveillance requirement. 

However, the proposed change does not 

involve (i) a significant hazards 

consideration, (ii) a significant change 

in the types or significant increase in 

the amounts of any effluent that may be 

released offsite, or (iii) a significant 

increase in individual or cumulative 

occupational radiation exposure. 

Accordingly, the proposed change meets 

the eligibility criterion for categorical 

exclusion set forth in 10 CFR 

51.22(c)(9). Therefore, pursuant to 10 

CFR 51.22(b), no environmental impact 

statement or environmental assessment 

need be prepared in connection with the 

proposed change. 

7.0 References 

1. Federal Register Notice, Notice of 

Availability published on [DATE] ([ ] 

FR [ ]). 

2. TSTF–513, Revision 2, ‘‘Revise 

PWR Operability Requirements and 

Actions for RCS Leakage 

Instrumentation.’’ 

[3. Other References] 

Proposed Model No Significant Hazards 

Consideration Determination for PlantSpecific Adoption of TSTF Traveler513, Revision 2, ‘‘Revise PWR 

Operability Requirements and Actions 

for RCS Leakage Instrumentation’’ 

Description of Amendment Request: 

The proposed amendment would revise 

Technical Specification (TS) [3.4.15], 

‘‘[Reactor Coolant System (RCS) Leakage 

Detection Instrumentation.]’’ Conditions 

and Required Actions as well as make 

associated TS Bases changes for TS 

[3.4.15]. 

Basis for proposed no significant 

hazards consideration: As required by 

Title10 of the Code of Federal 

Regulations (10 CFR) Section 50.91(a), 

the [LICENSEE] analysis of the issue of 

no significant hazards consideration is 

presented below: 

1: Does the Proposed Change Involve a 

Significant Increase in the Probability or 

Consequences of an Accident Previously 

Evaluated? 

Response: No. 

The proposed change clarifies the 

Operability requirements for the RCS leakage 

detection instrumentation and reduces the 

time allowed for the plant to operate when 

the only Operable RCS leakage 

instrumentation monitor is the containment 

atmosphere gaseous radiation monitor. The 

proposed change also extends the allowed 

operating time when all RCS leakage 

instrumentation is inoperable. The 

monitoring of RCS leakage is not a precursor 

to any accident previously evaluated. The 

monitoring of RCS leakage is not used to 

mitigate the consequences of any accident 

previously evaluated. Therefore, the 

proposed changes do not involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated. 

2: Does the Proposed Change Create the 

Possibility of a New or Different Kind of 

Accident from any Accident Previously 

Evaluated? 

Response: No. 

The proposed change clarifies the 

Operability requirements for the RCS leakage 

detection instrumentation and reduces the 

time allowed for the plant to operate when 

the only Operable RCS leakage 

instrumentation monitor is the containment 

atmosphere gaseous radiation monitor. The 

proposed change also extends the allowed 

operating time when all RCS leakage 

instrumentation is inoperable. The proposed 

change does not involve a physical alteration 

of the plant (no new or different type of 

equipment will be installed) or a change in 

the methods governing normal plant 

operation. The proposed change maintains 

sufficient continuity and diversity of leak 

detection capability that the probability of 

piping evaluated and approved for LeakBefore-Break progressing to pipe rupture 

remains extremely low. Therefore, the 

proposed change does not create the 

possibility of a new or different kind of 

accident from any previously evaluated. 

3: Does the Proposed Change Involve a 

Significant Reduction in a Margin of Safety? 

Response: No. 

The proposed change clarifies the 

Operability requirements for the RCS leakage 

detection instrumentation and reduces the 

time allowed for the plant to operate when 

the only Operable RCS leakage 

instrumentation monitor is the containment 

atmosphere gaseous radiation monitor. The 

proposed change also extends the allowed 

operating time when all RCS leakage 

instrumentation is inoperable to allow time 

to restore at least one RCS leakage monitoring 

instrument to Operable status. Reducing the 

amount of time the plant is allowed to 

operate with only the containment 

atmosphere gaseous radiation monitor 

Operable increases the margin of safety by 

increasing the likelihood that an increase in 

RCS leakage will be detected before it 

potentially results in gross failure. Allowing 

a limited period of time to restore at least one 

RCS leakage monitoring instrument to 

Operable status before requiring a plant 

shutdown avoids putting the plant through a 

thermal transient without RCS leakage 

monitoring. Therefore, the proposed change 

does not involve a significant reduction in a 

margin of safety. 

Based upon the reasoning presented 

above, the NRC staff concludes that the 

requested change does not involve a 

significant hazards consideration, as set 

forth in 10 CFR 50.92(c), ‘‘Issuance of 

Amendment.’’ 

Proposed Model Safety Evaluation for 

Plant-Specific Adoption of Technical 

Specification Task Force Traveler-513, 

Revision 2, ‘‘Revise PWR Operability 

Requirements and Actions for RCS 

Leakage Instrumentation’’ 

1.0 Introduction 

By letter dated [DATE], [LICENSEE] 

(the licensee) proposed changes to the 

technical specifications (TS) for [PLANT 

NAME]. The proposed changes revise 

TS [3.4.15], ‘‘[Reactor Coolant System 

(RCS) Leakage Detection 

Instrumentation].’’ The proposed 

changes also revise the TS Bases to 

clearly define the RCS leakage detection 

instrumentation Operability 

requirements in the Limiting Condition 

for Operation (LCO) Bases, eliminate 

discussion from the TS Bases that could 

be erroneously construed as Operability 

requirements, and reflect the changes to 

the TSs. 

The licensee stated that the 

application is consistent with NRCapproved Revision 2 to Technical 

Specification Task Force (TSTF) 

Improved Standard Technical 

Specification (STS) Change Traveler513, ‘‘Revise PWR Operability 

Requirements and Actions for RCS 

Leakage Instrumentation.’’ [Discuss any 

differences with TSTF–513, Revision 2.] 

The availability of this TS improvement 

mstockstill on DSKH9S0YB1PROD with NOTICES

52272 Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 

was announced in the Federal Register 

on [Date] ([ ] FR [ ]) as part of the 

consolidated line item improvement 

process (CLIIP). 

2.0 Regulatory Evaluation 

The regulation in General Design 

Criterion (GDC) 30 of Appendix A to 

Title 10 of the Code of Federal 

Regulations (10 CFR) Part 50, ‘‘Quality 

of Reactor Coolant Pressure Boundary,’’ 

requires means for detecting and, to the 

extent practical, identifying the location 

of the source of RCS Leakage. 

Regulatory Guide (RG) 1.45, Revision 0, 

‘‘Reactor Coolant Pressure Boundary 

Leakage Detection Systems,’’ May 1973, 

describes acceptable methods of 

implementing the GDC 30 requirements 

with regard to the selection of leakage 

detection systems for the Reactor 

Coolant Pressure Boundary (RCPB). 

Revision 1 of RG 1.45 was issued in May 

2008. RG 1.45, Revision 1, describes 

different methods of implementing the 

GDC 30 requirements compared to RG 

1.45, Revision 0, and was intended to be 

applicable only to new reactors. 

Therefore, operating nuclear power 

plants are not committed to Revision 1 

of RG 1.45. 

RG 1.45, Revision 0, Regulatory 

Position C.2, states that ‘‘Leakage to the 

primary reactor containment from 

unidentified sources should be collected 

and the flow rate monitored with an 

accuracy of one gallon per minute (gpm) 

or better.’’ Regulatory Position C.3 

states, ‘‘At least three separate detection 

methods should be employed and two 

of these methods should be (1) sump 

level and flow monitoring and (2) 

airborne particulate radioactivity 

monitoring. The third method may be 

selected from the following: (a) 

monitoring of condensate flow rate from 

air coolers or (b) monitoring of airborne 

gaseous radioactivity. Humidity, 

temperature, or pressure monitoring of 

the containment atmosphere should be 

considered as alarms or indirect 

indication of leakage to the 

containment.’’ Regulatory Position C.5 

states, ‘‘The sensitivity and response 

time of each leakage detection system in 

regulatory position 3 above employed 

for unidentified leakage should be 

adequate to detect a leakage rate, or its 

equivalent, of one gpm in less than one 

hour.’’ RG 1.45, Revision 0, states, ‘‘In 

analyzing the sensitivity of leak 

detection systems using airborne 

particulate or gaseous radioactivity, a 

realistic primary coolant radioactivity 

concentration assumption should be 

used. The expected values used in the 

plant environmental report would be 

acceptable.’’ The appropriate sensitivity 

of a plant’s containment atmosphere 

gaseous radioactivity monitors is 

dependent on the design assumptions 

and the plant-specific licensing basis as 

described in the plant’s updated final 

safety analysis report (UFSAR). 

As stated in NRC Information Notice 

(IN) 2005–24, ‘‘Nonconservatism in 

Leakage Detection Sensitivity,’’ the 

reactor coolant activity assumptions for 

containment atmosphere gaseous 

radioactivity monitors may be 

nonconservative. This means the 

monitors may not be able to detect a one 

gpm leak within one hour under all 

likely operating conditions. 

The NRC’s regulatory requirements 

related to the content of the TS are 

contained in 10 CFR Part 50.36. 

Paragraph (c)(2)(ii) of 10 CFR 50.36 lists 

criteria for determining whether 

particular items are required to be 

included in the TS LCOs. Criterion 1 of 

that regulation applies to installed 

instrumentation that is used to detect, 

and indicate in the control room, a 

significant abnormal degradation of the 

reactor coolant pressure boundary. As 

described in the Federal Register Notice 

associated with this regulation (60 FR 

36953, July 16, 1995), this criterion is 

intended to apply to process variables 

that alert the operator to a situation 

when accident initiation is more likely. 

The NRC’s guidance for the format 

and content of PWR TS can be found in 

NUREG–1430, Revision 3.0, ‘‘Standard 

Technical Specifications Babcock and 

Wilcox Plants,’’ NUREG–1431, Revision 

3.0, ‘‘Standard Technical Specifications 

Westinghouse Plants,’’ and NUREG– 

1432, Revision 3.0, ‘‘Standard Technical 

Specifications Combustion Engineering 

Plants.’’ STS 3.4.15, ‘‘RCS Leakage 

Detection Instrumentation’’ contains the 

guidance specific to the RCS leakage 

detection instrumentation for PWRs. 

The STS Bases provide a summary 

statement of the reasons for the STS. 

Operability requirements should be 

defined in the LCO section of the STS 

Bases. 

The STS Bases for STS 3.4.15 

contained in NUREG–1430, Revision 

3.0; NUREG–1431, Revision 3.0; and 

NUREG–1432, Revision 3.0, included 

information that could be construed as 

Operability requirements in the 

Background, Applicable Safety 

Analysis, and LCO sections. These STS 

Bases did not accurately describe the 

Operability of a detector as being based 

on the design assumptions and licensing 

basis for the plant. This situation and 

the issue described in IN 2005–24 have 

caused questions to arise regarding the 

Operability requirements for 

containment atmosphere gaseous 

radioactivity monitors. Traveler-513, 

Revision 2, contained changes to the 

STS Bases that revised PWR Operability 

requirements. In addition, Traveler-513, 

Revision 2, includes NRC-approved 

revisions to TS Actions for RCS Leakage 

Instrumentation that recognize the 

potentially reduced sensitivity of the 

gaseous radioactivity instrument and 

more appropriate actions when all RCS 

leakage detection instrumentation is 

inoperable. 

2.1 Adoption of Traveler-513, Revision 

2, by [Facility Name] 

Proper plant-specific adoption of 

Traveler-513, Revision 2, by [licensee] 

will revise the RCS Leakage Detection 

Instrumentation TS and TS Bases and 

clarify the Operability requirements for 

RCS Leakage Detection Instrumentation. 

The NRC staff reviewed the proposed 

changes for compliance with 10 CFR 

50.36 and agreement with the precedent 

as established in NUREG–[1430, 1431, 

or 1432]. In general, licensees cannot 

justify technical specification changes 

solely on the basis of adopting the 

model STS. To ensure this, the NRC 

staff makes a determination that 

proposed changes maintain adequate 

safety. Changes that result in relaxation 

(less restrictive condition) of current TS 

requirements require detailed 

justification. 

In general, there are two classes of 

changes to TSs: (1) Changes needed to 

reflect contents of the design basis (TSs 

are derived from the design basis), and 

(2) voluntary changes to take advantage 

of the evolution in policy and guidance 

as to the required content and preferred 

format of TSs over time. This 

amendment request deals with both 

classes of change. The amendment 

request includes proposed changes to 

the TS Bases to more accurately reflect 

the contents of the facility design basis 

related to operability of the RCS leakage 

detection instrumentation and proposed 

changes to the TS that take advantage of 

revised guidance on required actions for 

inoperable RCS leakage detection 

instrumentation. Guidelines for TS and 

TS Bases content are found in NUREG– 

[1430, 1431, or 1432], as amended by 

Traveler-513, Revision 2. 

Licensees may revise the TSs to adopt 

improved STS format and content 

provided that plant-specific review 

supports a finding of continued 

adequate safety because: (1) The change 

is editorial, administrative or provides 

clarification (i.e., no requirements are 

materially altered), (2) the change is 

more restrictive than the licensee’s 

current requirement, or (3) the change is 

less restrictive than the licensee’s 

current requirement, but nonetheless 

still affords adequate assurance of safety 

when judged against current regulatory 

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Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 52273 

standards. The detailed application of 

this general framework, and additional 

specialized guidance, are discussed in 

Section 3.0 in the context of specific 

proposed changes. 

3.0 Technical Evaluation 

The current Bases for TS [3.4.15], 

‘‘[Reactor Coolant System (RCS) Leakage 

Detection Instrumentation],’’ do not 

clearly define the basis for Operability 

for the RCS Leakage Instrumentation. 

The current TS Bases contain 

information that could be construed as 

Operability requirements in the 

Background, Applicable Safety 

Analysis, and LCO sections. In addition, 

the current TS Bases do not accurately 

describe the Operability of a detector as 

being based on the design assumptions 

and licensing basis for the plant. 

In adopting Traveler-513, Revision 2, 

the licensee proposed changes that 

would revise the Bases for TS [3.4.15] to 

clearly define the RCS leakage detection 

instrumentation Operability 

requirements in the LCO Bases and 

reflect the changes to the TSs. The 

proposed changes to the Operability 

requirements included in the LCO Bases 

are acceptable because they define, 

consistent with the design basis of the 

facility, the minimum set of diverse 

instruments that must be operable, the 

plant parameters monitored by the 

instrumentation, the design sensitivity 

of the leakage detection instruments, 

and factors that affect the operational 

sensitivity of the instrument. These 

instruments satisfy Criterion 1 of 10 

CFR 50.36(c)(2)(ii) in that they are 

installed instrumentation that is used to 

detect, and indicate in the control room, 

a significant abnormal degradation of 

the reactor coolant pressure boundary. 

In adopting the changes to TS 

included in Traveler-513, Revision 2, 

the licensee also proposed to revise TS 

[3.4.15], ‘‘[Reactor Coolant System (RCS) 

Leakage Detection Instrumentation]’’ 

Conditions and Required Actions. The 

licensee proposed adding new 

Condition [D] to TS [3.4.15]. New 

Condition [D] would be applicable 

when the containment atmosphere 

gaseous radioactivity monitor is the 

only operable RCS leakage detection 

monitor. The proposed Required 

Actions for new Condition [D] require 

the licensee to analyze grab samples of 

the containment atmosphere once per 

12 hours and restore the required 

containment sump monitor to Operable 

status within seven days, or analyze 

grab samples of the containment 

atmosphere once per 12 hours and 

restore the containment air cooler 

condensate flow rate monitor to 

Operable status within 7 days. The NRC 

staff determined that the proposed 

change is more restrictive than the 

current requirement, because there is no 

current Condition for the situation when 

the containment atmosphere gaseous 

radioactivity monitor is the only 

operable RCS leakage detection monitor. 

The proposed Actions and Completion 

Times are adequate because the grab 

samples will provide an alternate 

method of monitoring RCS leakage 

when the containment atmosphere 

gaseous radioactivity monitor is the 

only operable RCS leakage detection 

monitor and the 12-hour interval is 

sufficient to detect increasing RCS 

leakage. In addition, Surveillance 

Requirement (SR) 3.4.13.1 requires 

verification that RCS operational 

leakage is within limits by performance 

of an RCS water inventory balance at a 

frequency of once per 72 hours, which 

provides periodic confirmation that RCS 

leakage is within limits using diverse 

instrumentation. Allowing 7 days to 

restore another RCS leakage monitor to 

Operable status ensures that the plant 

will not be operated in a degraded 

configuration for a long time. 

Existing TS [3.4.15] Condition [F] is 

applicable when all required RCS 

leakage detection monitors are 

inoperable. The current Required Action 

for Condition [F] is to immediately enter 

LCO 3.0.3. The licensee proposed 

modifying the Required Actions for 

Condition [F]. The proposed Required 

Actions for Condition [F] would 

eliminate the requirement to 

immediately enter LCO 3.0.3 and would 

add the requirement to analyze grab 

samples of the containment atmosphere 

once per 6 hours, perform an RCS water 

inventory balance once per 6 hours per 

SR 3.4.13.1, and restore at least one RCS 

leakage detection monitor to Operable 

status within 72 hours. The NRC staff 

determined that the proposed change is 

less restrictive than the current 

requirement because it would allow a 

longer time to operate when all required 

RCS leakage detection monitors are 

inoperable. 

The licensee provided justification for 

the less restrictive change in its LAR, 

which the NRC staff reviewed. The grab 

sample has an RCS leakage detection 

capability that is comparable to that of 

the containment particulate radiation 

monitor. The RCS water inventory 

balance is capable of identifying a onegpm RCS leak rate and uses 

instrumentation readily available to 

control room operators. The proposed 

Actions and Completion Times for grab 

samples and water inventory balance 

calculations are adequate because use of 

frequent grab samples and RCS water 

inventory balance calculations provide 

assurance that any significant RCS 

leakage will be detected prior to 

significant RCS pressure boundary 

degradation. The proposed 72-hour 

Completion Time for Restoration of at 

least one RCS leakage detection monitor 

to Operable status is appropriate given 

the low probability of significant RCS 

leakage during the time when no 

required RCS leakage detection 

monitors are Operable, and the need for 

time to restore at least one monitor to 

Operable status. 

[Facility] has been licensed for LeakBefore-Break (LBB). The basic concept 

of LBB is that certain piping material 

has sufficient fracture toughness (i.e., 

ductility) to resist rapid flaw 

propagation. The licensee has evaluated 

postulated flaws in [RCS loop] piping 

and determined the piping has 

sufficient fracture toughness that the 

postulated flaw would not lead to pipe 

rupture and potential damage to 

adjacent safety related systems, 

structures and components before the 

plant could be placed in a safe, 

shutdown condition. The NRC staff has 

previously reviewed and approved these 

analyses. Before pipe rupture, the 

postulated flaw would lead to limited 

but detectable leakage, which would be 

identified by the leak detection systems 

in time for the operator to take action. 

The proposed actions for inoperable 

RCS leakage detection instrumentation 

maintain sufficient continuity and 

diversity of leakage detection capability 

that an extremely low probability of 

undetected leakage leading to pipe 

rupture is maintained. This extremely 

low probability of pipe rupture 

continues to satisfy the basis for 

acceptability of LBB. 

The licensee proposed minor changes 

to ensure continuity of the TS format. 

These changes re-lettered current 

Condition [D], which applies when the 

containment sump monitor is the only 

operable leakage detection instrument, 

to Condition [E], and current Condition 

[E], which applies when the required 

action and the associated completion 

time are not satisfied, to Condition [G]. 

Similar changes were made to the 

associated Required Actions. The NRC 

staff determined that these changes were 

editorial, and therefore acceptable. 

The NRC staff evaluated the licensee’s 

proposed change against the applicable 

regulatory requirements listed in 

Section 2 of this safety evaluation. The 

NRC staff also compared the proposed 

change to the change made to STS by 

Traveler-513, Revision 2. The NRC staff 

determined that all the proposed 

changes afford adequate assurance of 

safety when judged against current 

regulatory standards. Therefore, the 

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52274 Federal Register / Vol. 74, No. 195 / Friday, October 9, 2009 / Notices 

NRC staff finds the proposed changes 

acceptable. 

4.0 Conclusions 

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. 

5.0 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 NRC staff]. 

6.0 Environmental Consideration 

The amendment changes 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, 

‘‘Standards for Protection Against 

Radiation.’’ 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 considerations, and 

there has been no public comment on 

the finding [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 amendments. 

7.0 References 

1. [Licensee] Licensee Amendment 

Request to adopt TSTF–513, [DATE]. 

2. Federal Register Notice, Notice of 

Availability published on [DATE] ([ ] 

FR [ ]). 

3. TSTF Traveler-513, Revision 2, 

‘‘Revise PWR Operability Requirements 

and Actions for RCS Leakage 

Instrumentation’’. 

[FR Doc. E9–24407 Filed 10–8–09; 8:45 am] 

BILLING CODE 7590–01–P 

SMALL BUSINESS ADMINISTRATION 

[Disaster Declaration #11888 and #11889] 

Georgia Disaster Number GA–00028 

AGENCY: U.S. Small Business 

Administration. 

ACTION: Amendment 2. 

SUMMARY: This is an amendment of the 

Presidential declaration of a major 

disaster for Public Assistance Only for 

the State of Georgia (FEMA–1858–DR), 

dated 09/26/2009. 

Incident: Severe Storms and Flooding. 

Incident Period: 09/18/2009 and 

continuing. 

DATES: Effective Date: 09/30/2009. 

Physical Loan Application Deadline 

Date: 11/25/2009. 

Economic Injury (EIDL) Loan 

Application Deadline Date: 06/28/2010. 

ADDRESSES: Submit completed loan 

applications to: U.S. Small Business 

Administration, Processing and 

Disbursement Center, 14925 Kingsport 

Road, Fort Worth, TX 76155. 

FOR FURTHER INFORMATION CONTACT: A. 

Escobar, Office of Disaster Assistance, 

U.S. Small Business Administration, 

409 3rd Street, SW., Suite 6050, 

Washington, DC 20416. 

SUPPLEMENTARY INFORMATION: The notice 

of the President’s major disaster 

declaration for Private Non-Profit 

organizations in the State of GEORGIA, 

dated 09/26/2009, is hereby amended to 

include the following areas as adversely 

affected by the disaster. 

Primary Counties: Dooly, Dawson, 

Heard, Houston, Peach, Rockdale, 

Taylor. 

All other information in the original 

declaration remains unchanged. 

(Catalog of Federal Domestic Assistance 

Numbers 59002 and 59008) 

James E. Rivera, 

Acting Associate Administrator for Disaster 

Assistance. 

[FR Doc. E9–24419 Filed 10–8–09; 8:45 am] 

BILLING CODE 8025–01–P 

SMALL BUSINESS ADMINISTRATION 

[Disaster Declaration #11891 and #11892] 

New York Disaster #NY–00074 

AGENCY: U.S. Small Business 

Administration. 

ACTION: Notice. 

SUMMARY: This is a notice of an 

Administrative declaration of a disaster 

for the State of New York dated 10/02/ 

2009. 

Incident: Severe Storms, Straight-Line 

Winds, and Flooding. 

Incident Period: 07/06/2009 through 

07/07/2009. 

DATES: Effective Date: 10/02/2009. 

Physical Loan Application Deadline 

Date: 12/01/2009. 

Economic Injury (EIDL) Loan 

Application Deadline Date: 07/02/2010. 

ADDRESSES: Submit completed loan 

applications to: U.S. Small Business 

Administration, Processing and 

Disbursement Center, 14925 Kingsport 

Road, Fort Worth, TX 76155. 

FOR FURTHER INFORMATION CONTACT: A. 

Escobar, Office of Disaster Assistance, 

U.S. Small Business Administration, 

409 3rd Street, SW., Suite 6050, 

Washington, DC 20416. 

SUPPLEMENTARY INFORMATION: Notice is 

hereby given that as a result of the 

Administrator’s disaster declaration, 

applications for disaster loans may be 

filed at the address listed above or other 

locally announced locations. 

The following areas have been 

determined to be adversely affected by 

the disaster: 

Primary Counties: Westchester. 

Contiguous Counties: 

New York. Bronx, Orange, Putnam, 

Rockland. 

Connecticut. Fairfield. 

New Jersey. Bergen. 

The Interest Rates are: 

Percent 

Homeowners With Credit Available Elsewhere 4.875 

Homeowners Without Credit 

Available Elsewhere 2.437 

Businesses With Credit Available 

Elsewhere 6.000 

Businesses & Small Agricultural 

Cooperatives Without Credit 

Available Elsewhere 4.000 

Other (Including Non-Profit Organizations) With Credit Available 

Elsewhere 4.500 

Businesses And Non-Profit Organizations Without Credit Available Elsewhere 4.000 

The number assigned to this disaster for 

physical damage is 11891 6 and for economic 

injury is 11892 0. 

The States which received an EIDL Declaration # are New York, Connecticut, New 

Jersey. 

(Catalog of Federal Domestic Assistance 

Numbers 59002 and 59008) 

Dated: October 2, 2009. 

Karen G. Mills, 

Administrator. 

[FR Doc. E9–24411 Filed 10–8–09; 8:45 am] 

BILLING CODE 8025–01–P 

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