6408 Federal Register / Vol. 75, No. 26 / Tuesday, February 9, 2010 / Notices 

FOR FURTHER INFORMATION CONTACT: Ms. 

Kathy Dakon, Aerospace Safety 

Advisory Panel Executive Director, 

National Aeronautics and Space 

Administration, Washington, DC 20546, 

(202) 358–0732. 

SUPPLEMENTARY INFORMATION: The 

Aerospace Safety Advisory Panel will 

hold its 1st Quarterly Meeting for 2010. 

This discussion is pursuant to carrying 

out its statutory duties for which the 

Panel reviews, identifies, evaluates, and 

advises on those program activities, 

systems, procedures, and management 

activities that can contribute to program 

risk. Priority is given to those programs 

that involve the safety of human flight. 

The agenda will include Marshall Space 

Flight Center Safety Mission Assurance 

Overview; NASA Safety and Mission 

Assurance Technical Excellence; 

Overview of Marshall Space Flight 

Center Launch Abort System 

Responsibilities; and Marshall Space 

Flight Center Industrial Safety, New 

Initiatives, Proactive Approaches, 

Specific Safety Issues, Identified 

Opportunities, and Near Misses. 

The meeting will be open to the 

public up to the seating capacity of the 

room. Seating will be on a first-come 

basis. Visitors will be requested to sign 

a visitor’s register. Photographs will 

only be permitted during the first 10 

minutes of the meeting. During the first 

30 minutes of the meeting, members of 

the public may make a 5-minute verbal 

presentation to the Panel on the subject 

of safety in NASA. To do so, please 

contact Ms. Susan Burch at 

susan.burch@nasa.gov at least 48 hours 

in advance. Any member of the public 

is permitted to file a written statement 

with the Panel at the time of the 

meeting. Verbal presentations and 

written comments should be limited to 

the subject of safety in NASA. All U.S. 

citizens desiring to attend the Aerospace 

Safety Advisory Panel meeting at the 

Marshall Space Flight Center must 

provide their full name, company 

affiliation (if applicable), citizenship, 

place of birth, and date of birth to the 

Marshall Space Flight Center Protective 

Services Office no later than close of 

business on February 17, 2010. All nonU.S. citizens must submit their name; 

current address; citizenship; company 

affiliation (if applicable) to include 

address, telephone number, and title; 

place of birth; date of birth; U.S. visa 

information to include type, number, 

and expiration date; U.S. Social Security 

Number (if applicable); Permanent 

Resident Alien card number and 

expiration date (if applicable); place and 

date of entry into the U.S.; and Passport 

information to include Country of issue, 

number, and expiration date to the 

Marshall Space Flight Center Security 

Office no later than close of business on 

February 11, 2010. If the above 

information is not received by the noted 

dates, attendees should expect a 

minimum delay of two (2) hours. All 

visitors to this meeting will be required 

to process in through the Redstone/ 

Marshall Space Flight Center Joint 

Visitor Control Center located on 

Rideout Road, north of Gate 9, prior to 

entering Marshall Space Flight Center. 

Please provide the appropriate data, via 

fax at (256) 544–2101, noting at the top 

of the page ‘‘Public Admission to the 

ASAP Meeting at MSFC.’’ For security 

questions, please call Becky Hopson at 

(256) 544–4541. It is imperative that the 

meeting be held on this date to 

accommodate the scheduling priorities 

of the key participants. 

Dated: February 2, 2010. 

P. Diane Rausch, 

Advisory Committee Management Officer, 

National Aeronautics and Space 

Administration. 

[FR Doc. 2010–2711 Filed 2–8–10; 8:45 am] 

BILLING CODE 7510–13–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0040] 

Biweekly Notice; Applications and 

Amendments to Facility Operating 

Licenses Involving No Significant 

Hazards Considerations 

I. Background 

Pursuant to section 189a. (2) of the 

Atomic Energy Act of 1954, as amended 

(the Act), the U.S. Nuclear Regulatory 

Commission (the Commission or NRC) 

is publishing this regular biweekly 

notice. The Act requires the 

Commission publish notice of any 

amendments issued, or proposed to be 

issued and grants the Commission the 

authority to issue and make 

immediately effective any amendment 

to an operating license upon a 

determination by the Commission that 

such amendment involves no significant 

hazards consideration, notwithstanding 

the pendency before the Commission of 

a request for a hearing from any person. 

This biweekly notice includes all 

notices of amendments issued, or 

proposed to be issued from January 14 

to January 27. The last biweekly notice 

was published on January 26, 2010 (75 

FR 4111). 

Notice of Consideration of Issuance of 

Amendments to Facility Operating 

Licenses, Proposed No Significant 

Hazards Consideration Determination, 

and Opportunity for a Hearing 

The Commission has made a 

proposed determination that the 

following amendment requests involve 

no significant hazards consideration. 

Under the Commission’s regulations in 

Title 10 of the Code of Federal 

Regulations (10 CFR), Section 50.92, 

this means that operation of the facility 

in accordance with the proposed 

amendment would not (1) Involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated; or (2) create the possibility of 

a new or different kind of accident from 

any accident previously evaluated; or 

(3) involve a significant reduction in a 

margin of safety. The basis for this 

proposed determination for each 

amendment request is shown below. 

The Commission is seeking public 

comments on this proposed 

determination. Any comments received 

within 30 days after the date of 

publication of this notice will be 

considered in making any final 

determination. 

Normally, the Commission will not 

issue the amendment until the 

expiration of 60 days after the date of 

publication of this notice. The 

Commission may issue the license 

amendment before expiration of the 60- 

day period provided that its final 

determination is that the amendment 

involves no significant hazards 

consideration. In addition, the 

Commission may issue the amendment 

prior to the expiration of the 30-day 

comment period should circumstances 

change during the 30-day comment 

period such that failure to act in a 

timely way would result, for example in 

derating or shutdown of the facility. 

Should the Commission take action 

prior to the expiration of either the 

comment period or the notice period, it 

will publish in the Federal Register a 

notice of issuance. Should the 

Commission make a final No Significant 

Hazards Consideration Determination, 

any hearing will take place after 

issuance. The Commission expects that 

the need to take this action will occur 

very infrequently. 

Written comments may be submitted 

by mail to the Chief, Rulemaking and 

Directives Branch (RDB), TWB–05– 

B01M, Division of Administrative 

Services, Office of Administration, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, and 

should cite the publication date and 

page number of this Federal Register 


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notice. Written comments may also be 

faxed to the RDB at 301–492–3446. 

Documents may be examined, and/or 

copied for a fee, at the NRC’s Public 

Document Room (PDR), located at One 

White Flint North, Public File Area 

O1F21, 11555 Rockville Pike (first 

floor), Rockville, Maryland. 

Within 60 days after the date of 

publication of this notice, any person(s) 

whose interest may be affected by this 

action may file a request for a hearing 

and a petition to intervene with respect 

to issuance of the amendment to the 

subject facility operating license. 

Requests for a hearing and a petition for 

leave to intervene shall be filed in 

accordance with the Commission’s 

‘‘Rules of Practice for Domestic 

Licensing Proceedings’’ in 10 CFR Part 

2. Interested person(s) should consult a 

current copy of 10 CFR 2.309, which is 

available at the Commission’s PDR, 

located at One White Flint North, Public 

File Area O1F21, 11555 Rockville Pike 

(first floor), Rockville, Maryland. 

Publicly available records will be 

accessible from the Agencywide 

Documents Access and Management 

System’s (ADAMS) Public Electronic 

Reading Room on the Internet at the 

NRC Web site, http://www.nrc.gov/ 

reading-rm/doc-collections/cfr/. If a 

request for a hearing or petition for 

leave to intervene is filed by the above 

date, the Commission or a presiding 

officer designated by the Commission or 

by the Chief Administrative Judge of the 

Atomic Safety and Licensing Board 

Panel, will rule on the request and/or 

petition; and the Secretary or the Chief 

Administrative Judge of the Atomic 

Safety and Licensing Board will issue a 

notice of a hearing or an appropriate 

order. 

As required by 10 CFR 2.309, a 

petition for leave to intervene shall set 

forth with particularity the interest of 

the petitioner in the proceeding, and 

how that interest may be affected by the 

results of the proceeding. The petition 

should specifically explain the reasons 

why intervention should be permitted 

with particular reference to the 

following general requirements: (1) The 

name, address, and telephone number of 

the requestor or petitioner; (2) the 

nature of the requestor’s/petitioner’s 

right under the Act to be made a party 

to the proceeding; (3) the nature and 

extent of the requestor’s/petitioner’s 

property, financial, or other interest in 

the proceeding; and (4) the possible 

effect of any decision or order which 

may be entered in the proceeding on the 

requestor’s/petitioner’s interest. The 

petition must also identify the specific 

contentions which the requestor/ 

petitioner seeks to have litigated at the 

proceeding. 

Each contention must consist of a 

specific statement of the issue of law or 

fact to be raised or controverted. In 

addition, the requestor/petitioner shall 

provide a brief explanation of the bases 

for the contention and a concise 

statement of the alleged facts or expert 

opinion which support the contention 

and on which the requestor/petitioner 

intends to rely in proving the contention 

at the hearing. The requestor/petitioner 

must also provide references to those 

specific sources and documents of 

which the petitioner is aware and on 

which the requestor/petitioner intends 

to rely to establish those facts or expert 

opinion. The petition must include 

sufficient information to show that a 

genuine dispute exists with the 

applicant on a material issue of law or 

fact. Contentions shall be limited to 

matters within the scope of the 

amendment under consideration. The 

contention must be one which, if 

proven, would entitle the requestor/ 

petitioner to relief. A requestor/ 

petitioner who fails to satisfy these 

requirements with respect to at least one 

contention will not be permitted to 

participate as a party. 

Those permitted to intervene become 

parties to the proceeding, subject to any 

limitations in the order granting leave to 

intervene, and have the opportunity to 

participate fully in the conduct of the 

hearing. 

If a hearing is requested, the 

Commission will make a final 

determination on the issue of no 

significant hazards consideration. The 

final determination will serve to decide 

when the hearing is held. If the final 

determination is that the amendment 

request involves no significant hazards 

consideration, the Commission may 

issue the amendment and make it 

immediately effective, notwithstanding 

the request for a hearing. Any hearing 

held would take place after issuance of 

the amendment. If the final 

determination is that the amendment 

request involves a significant hazards 

consideration, any hearing held would 

take place before the issuance of any 

amendment. 

All documents filed in NRC 

adjudicatory proceedings, including a 

request for hearing, a petition for leave 

to intervene, any motion or other 

document filed in the proceeding prior 

to the submission of a request for 

hearing or petition to intervene, and 

documents filed by interested 

governmental entities participating 

under 10 CFR 2.315(c), must be filed in 

accordance with the NRC E–Filing rule 

(72 FR 49139, August 28, 2007). The E– 

Filing process requires participants to 

submit and serve all adjudicatory 

documents over the Internet, or in some 

cases to mail copies on electronic 

storage media. Participants may not 

submit paper copies of their filings 

unless they seek an exemption in 

accordance with the procedures 

described below. 

To comply with the procedural 

requirements of E–Filing, at least ten 

(10) days prior to the filing deadline, the 

participant should contact the Office of 

the Secretary by e-mail at 

hearing.docket@nrc.gov, or by telephone 

at (301) 415–1677, to request (1) a 

digital ID certificate, which allows the 

participant (or its counsel or 

representative) to digitally sign 

documents and access the E–Submittal 

server for any proceeding in which it is 

participating; and (2) advise the 

Secretary that the participant will be 

submitting a request or petition for 

hearing (even in instances in which the 

participant, or its counsel or 

representative, already holds an NRCissued digital ID certificate). Based upon 

this information, the Secretary will 

establish an electronic docket for the 

hearing in this proceeding if the 

Secretary has not already established an 

electronic docket. 

Information about applying for a 

digital ID certificate is available on 

NRC’s public Web site at http:// 

www.nrc.gov/site-help/e-submittals/ 

apply-certificates.html. System 

requirements for accessing the E– 

Submittal server are detailed in NRC’s 

‘‘Guidance for Electronic Submission,’’ 

which is available on the agency’s 

public Web site at http://www.nrc.gov/ 

site-help/e-submittals.html. Participants 

may attempt to use other software not 

listed on the Web site, but should note 

that the NRC’s E–Filing system does not 

support unlisted software, and the NRC 

Meta System Help Desk will not be able 

to offer assistance in using unlisted 

software. 

If a participant is electronically 

submitting a document to the NRC in 

accordance with the E–Filing rule, the 

participant must file the document 

using the NRC’s online, Web-based 

submission form. In order to serve 

documents through EIE, users will be 

required to install a Web browser plugin from the NRC Web site. Further 

information on the Web-based 

submission form, including the 

installation of the Web browser plug-in, 

is available on the NRC’s public Web 

site at http://www.nrc.gov/site-help/esubmittals.html. 

Once a participant has obtained a 

digital ID certificate and a docket has 

been created, the participant can then 


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6410 Federal Register / Vol. 75, No. 26 / Tuesday, February 9, 2010 / Notices 

submit a request for hearing or petition 

for leave to intervene. Submissions 

should be in Portable Document Format 

(PDF) in accordance with NRC guidance 

available on the NRC public Web site at 

http://www.nrc.gov/site-help/esubmittals.html. A filing is considered 

complete at the time the documents are 

submitted through the NRC’s E–Filing 

system. To be timely, an electronic 

filing must be submitted to the E–Filing 

system no later than 11:59 p.m. Eastern 

Time on the due date. Upon receipt of 

a transmission, the E–Filing system 

time-stamps the document and sends 

the submitter an e-mail notice 

confirming receipt of the document. The 

E–Filing system also distributes an email notice that provides access to the 

document to the NRC Office of the 

General Counsel and any others who 

have advised the Office of the Secretary 

that they wish to participate in the 

proceeding, so that the filer need not 

serve the documents on those 

participants separately. Therefore, 

applicants and other participants (or 

their counsel or representative) must 

apply for and receive a digital ID 

certificate before a hearing request/ 

petition to intervene is filed so that they 

can obtain access to the document via 

the E–Filing system. 

A person filing electronically using 

the agency’s adjudicatory E–Filing 

system may seek assistance by 

contacting the NRC Meta System Help 

Desk through the ‘‘Contact Us’’ link 

located on the NRC Web site at http:// 

www.nrc.gov/site-help/esubmittals.html, by e-mail at 

MSHD.Resource@nrc.gov, or by a tollfree call at (866) 672–7640. The NRC 

Meta System Help Desk is available 

between 8 a.m. and 8 p.m., Eastern 

Time, Monday through Friday, 

excluding government holidays. 

Participants who believe that they 

have a good cause for not submitting 

documents electronically must file an 

exemption request, in accordance with 

10 CFR 2.302(g), with their initial paper 

filing requesting authorization to 

continue to submit documents in paper 

format. Such filings must be submitted 

by: (1) first class mail addressed to the 

Office of the Secretary of the 

Commission, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, Attention: Rulemaking and 

Adjudications Staff; or (2) courier, 

express mail, or expedited delivery 

service to the Office of the Secretary, 

Sixteenth Floor, One White Flint North, 

11555 Rockville Pike, Rockville, 

Maryland, 20852, Attention: 

Rulemaking and Adjudications Staff. 

Participants filing a document in this 

manner are responsible for serving the 

document on all other participants. 

Filing is considered complete by firstclass mail as of the time of deposit in 

the mail, or by courier, express mail, or 

expedited delivery service upon 

depositing the document with the 

provider of the service. A presiding 

officer, having granted an exemption 

request from using E–Filing, may 

require a participant or party to use E– 

Filing if the presiding officer 

subsequently determines that the reason 

for granting the exemption from use of 

E–Filing no longer exists. 

Documents submitted in adjudicatory 

proceedings will appear in NRC’s 

electronic hearing docket which is 

available to the public at http:// 

ehd.nrc.gov/EHD_Proceeding/home.asp, 

unless excluded pursuant to an order of 

the Commission, or the presiding 

officer. Participants are requested not to 

include personal privacy information, 

such as Social Security numbers, home 

addresses, or home phone numbers in 

their filings, unless an NRC regulation 

or other law requires submission of such 

information. With respect to 

copyrighted works, except for limited 

excerpts that serve the purpose of the 

adjudicatory filings and would 

constitute a Fair Use application, 

participants are requested not to include 

copyrighted materials in their 

submission. 

Petitions for leave to intervene must 

be filed no later than 60 days from 

February 9, 2010. Non-timely filings 

will not be entertained absent a 

determination by the presiding officer 

that the petition or request should be 

granted or the contentions should be 

admitted, based on a balancing of the 

factors specified in 10 CFR 

2.309(c)(1)(i)–(viii). 

For further details with respect to this 

license amendment application, see the 

application for amendment which is 

available for public inspection at the 

Commission’s PDR, located at One 

White Flint North, Public File Area 

O1F21, 11555 Rockville Pike (first 

floor), Rockville, Maryland. Publicly 

available records will be accessible from 

the ADAMS Public Electronic Reading 

Room on the Internet at the NRC Web 

site, 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 PDR Reference staff at 1–800–397– 

4209, 301–415–4737, or by e-mail to 

pdr.resource@nrc.gov. 

Exelon Generation Company, LLC, 

Docket Nos. 50–237 and 50–249, 

Dresden Nuclear Power Station, Units 2 

and 3, Grundy County, Illinois 

Docket Nos. 50–254 and 50–265, Quad 

Cities Nuclear Power Station, Units 1 

and 2, Rock Island County, Illinois 

Date of application for amendment 

request: November 10, 2009. 

Description of amendment request: 

The proposed amendment revises 

Technical Specification (TS) 3.1.7, 

‘‘Standby Liquid Control (SLC) System,’’ 

to extend the completion time (CT) for 

Condition B (i.e., ‘‘Two SLC subsystems 

inoperable’’) from 8 hours to 72 hours. 

Basis for proposed no significant 

hazards consideration determination: 

As required by 10 CFR 50.91(a), the 

licensee has provided its analysis of the 

issue of no significant hazards 

consideration, which is presented 

below: 

1. Does the proposed amendment involve 

a significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

The proposed amendment revises 

Technical Specification (TS) 3.1.7, ‘‘Standby 

Liquid Control (SLC) System,’’ to extend the 

completion time (CT) for Condition B (i.e., 

‘‘Two SLC subsystems inoperable.’’) from 

eight hours to 72 hours. 

The proposed change is based on a riskinformed evaluation performed in 

accordance with Regulatory Guides (RG) 

1.174, ‘‘An Approach for Using Probabilistic 

Risk Assessment in Risk-Informed Decisions 

On Plant-Specific Changes to the Licensing 

Basis,’’ and RG 1.177, ‘‘An Approach for 

Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications.’’ 

The proposed amendment modifies an 

existing CT for a dual-train SLC system 

inoperability. The condition evaluated, the 

action requirements, and the associated CT 

do not impact any initiating conditions for 

any accident previously evaluated. 

The proposed amendment does not 

increase postulated frequencies or the 

analyzed consequences of an Anticipated 

Transient Without Scram (ATWS). 

Requirements associated with 10 CFR 50.62 

will continue to be met. In addition, the 

proposed amendment does not increase 

postulated frequencies or the analyzed 

consequences or a large-break loss-of-coolant 

accident for which the SLC system is used for 

pH control. The new action requirement 

provides appropriate remedial actions to be 

taken in response to a dual-train SLC system 

inoperability while minimizing the risk 

associated with continued operation. 

Therefore, the proposed change does not 

involve a significant increase in the 

probability or consequences of an accident 

previously evaluated. 

2. Does the proposed amendment create 

the possibility of a new or different kind of 

accident from any accident previously 

evaluated? 


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Response: No. 

The proposed amendment revises TS 3.1.7 

to extend the CT for Condition B from eight 

hours to 72 hours. The proposed amendment 

does not involve any change to plant 

equipment or system design functions. This 

proposed TS amendment does not change the 

design function of the SLC system and does 

not affect the system’s ability to perform its 

design function. The SLC system provides a 

method to bring the reactor, at any time in 

a fuel cycle, from full power and minimum 

control rod inventory to a subcritical 

condition with the reactor in the most 

reactive xenon free state without taking 

credit for control rod movement. Required 

actions and surveillance requirements are 

sufficient to ensure that the SLC system 

functions are maintained. No new accident 

initiators are introduced by this amendment. 

Therefore, the proposed amendment does not 

create the possibility of a new or different 

kind of accident from any previously 

evaluated. 

3. Does the proposed amendment involve 

a significant reduction in a margin of safety? 

Response: No. 

The proposed amendment revises TS 3.1.7 

to extend the CT for Condition B from eight 

hours to 72 hours. The proposed amendment 

does not involve any change to plant 

equipment or system design functions. The 

margin of safety is established through the 

design of the plant structures, systems, and 

components, the parameters within which 

the plant is operated, and the setpoints for 

the actuation of equipment relied upon to 

respond to an event. 

Safety margins applicable to the SLC 

system include pump capacity, boron 

concentration, boron enrichment, and system 

response timing. The proposed amendment 

does not modify these safety margins or the 

setpoints at which SLC is initiated, nor does 

it affect the system’s ability to perform its 

design function. In addition, the proposed 

change complies with the intent of the 

defense-in-depth philosophy and the 

principle that sufficient safety margins are 

maintained, consistent with RG 1.177 

requirements (i.e., Section C, ‘‘Regulatory 

Position,’’ paragraph 2.2, ‘‘Traditional 

Engineering Considerations’’). 

The NRC staff has reviewed the 

licensee’s analysis and, based on this 

review, it appears that the three 

standards of 10 CFR 50.92(c) are 

satisfied. Therefore, the NRC staff 

proposes to determine that the 

amendment request involves no 

significant hazards consideration. 

Attorney for licensee: Mr. Bradley J. 

Fewell, Associate General Counsel, 

Exelon Nuclear, 4300 Winfield Road, 

Warrenville, IL 60555. 

NRC Branch Chief: Stephen J. 

Campbell. 

R.E. Ginna Nuclear Power Plant, LLC, 

Docket No. 50–244, R.E. Ginna Nuclear 

Power Plant, Wayne County, New York 

Date of amendment request: 

November 30, 2009. 

Description of amendment request: 

The proposed changes would use the 

guidance in Nuclear Regulatory 

Commission (NRC) Regulatory Issue 

Summary 2003–18 Supplement 2, ‘‘Use 

of Nuclear Energy Institute (NEI) 99–01, 

Methodology for Development of 

Emergency Action Levels,’’ to modify 

several Ginna Emergency Action Levels 

based on NEI 99–01. NRC approval, 

prior to implementation of the proposed 

change, is being requested pursuant to 

10 CFR 50.54(q). 

Basis for proposed no significant 

hazards consideration determination: 

As required by 10 CFR 50.91(a), the 

licensee has provided its analysis of the 

issue of no significant hazards 

consideration, which is presented 

below: 

Criterion 1: Does the proposed amendment 

involve a significant increase in the 

probability or consequences of an accident 

previously evaluated? 

Response: No. 

These changes affect the R.E. Ginna 

Nuclear Power Plant Emergency Plan and do 

not alter any of the requirements of the 

Operating License or the Technical 

Specifications. The proposed changes do not 

modify any plant equipment and do not 

impact any failure modes that could lead to 

an accident. Additionally, the proposed 

changes have no effect on the consequence of 

any analyzed accident since the changes do 

not affect any equipment related to accident 

mitigation. Based on this discussion, the 

proposed amendment does not increase the 

probability or consequences of an accident 

previously evaluated. 

Criterion 2: Does the proposed amendment 

create the possibility of a new or different 

kind of accident from any accident 

previously evaluated? 

Response: No. 

These changes affect the R.E. Ginna 

Nuclear Power Plant Emergency Plan and do 

not alter any of the requirements of the 

Operating License or the Technical 

Specifications. They do not modify any plant 

equipment and there is no impact on the 

capability of the existing equipment to 

perform their intended functions. No system 

set points are being modified and no changes 

are being made to the method in which plant 

operations are conducted. No new failure 

modes are introduced by the proposed 

changes. The proposed amendment does not 

introduce accident initiator or malfunctions 

that would cause a new or different kind of 

accident. Therefore, the proposed 

amendment does not create the possibility of 

a new or different kind of accident from any 

accident previously evaluated. 

Criterion 3: Does the proposed amendment 

involve a significant reduction in a margin of 

safety? 

Response: No. 

These changes affect the R.E. Ginna 

Nuclear Power Plant Emergency Plan and do 

not alter any of the requirements of the 

Operating License or the Technical 

Specifications. The proposed changes do not 

affect any of the assumptions used in the 

accident analysis, nor do they affect any 

operability requirements for equipment 

important to plant safety. Therefore, the 

proposed changes will not result in a 

significant reduction in the margin of safety 

as defined in the bases for technical 

specifications covered in this license 

amendment request. 

The NRC staff has reviewed the 

licensee’s analysis and, based on this 

review, it appears that the three 

standards of 10 CFR 50.92(c) are 

satisfied. Therefore, the NRC staff 

proposes to determine that the 

amendment request involves no 

significant hazards consideration. 

Attorney for licensee: Carey Fleming, 

Sr. Counsel—Nuclear Generation, 

Constellation Group, LLC, 750 East Pratt 

Street, 17th Floor, Baltimore, MD 21202. 

NRC Branch Chief: Nancy L. Salgado. 

Notice of Issuance of Amendments to 

Facility Operating Licenses 

During the period since publication of 

the last biweekly notice, the 

Commission has issued the following 

amendments. The Commission has 

determined for each of these 

amendments that the application 

complies with the standards and 

requirements of the Atomic Energy Act 

of 1954, as amended (the Act), and the 

Commission’s rules and regulations. 

The Commission has made appropriate 

findings as required by the Act and the 

Commission’s rules and regulations in 

10 CFR Chapter I, which are set forth in 

the license amendment. 

Notice of Consideration of Issuance of 

Amendment to Facility Operating 

License, Proposed No Significant 

Hazards Consideration Determination, 

and Opportunity for a Hearing in 

connection with these actions was 

published in the Federal Register as 

indicated. 

Unless otherwise indicated, the 

Commission has determined that these 

amendments satisfy the criteria for 

categorical exclusion in accordance 

with 10 CFR 51.22. Therefore, pursuant 

to 10 CFR 51.22(b), no environmental 

impact statement or environmental 

assessment need be prepared for these 

amendments. If the Commission has 

prepared an environmental assessment 

under the special circumstances 

provision in 10 CFR 51.22(b) and has 

made a determination based on that 

assessment, it is so indicated. 

For further details with respect to the 

action see (1) The applications for 

amendment, (2) the amendment, and (3) 

the Commission’s related letter, Safety 

Evaluation and/or Environmental 

Assessment as indicated. All of these 

items are available for public inspection 

at the Commission’s Public Document 


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Room (PDR), located at One White Flint 

North, Public File Area 01F21, 11555 

Rockville Pike (first floor), Rockville, 

Maryland. Publicly available records 

will be accessible from the Agencywide 

Documents Access and Management 

System (ADAMS) Public Electronic 

Reading Room on the internet at the 

NRC Web site, http://www.nrc.gov/ 

reading-rm/adams.html. If you do not 

have access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the PDR 

Reference staff at 1 (800) 397–4209, 

(301) 415–4737 or by e-mail to 

pdr.resource@nrc.gov. 

Entergy Nuclear Vermont Yankee, LLC 

and Entergy Nuclear Operations, Inc., 

Docket No. 50–271, Vermont Yankee 

Nuclear Power Station, Vernon, 

Vermont 

Date of amendment request: 

September 16, 2009, as supplemented 

by letter dated November 16, 2009. 

Description of amendment request: 

The proposed amendment revised 

Technical Specification (TS) Section 

3.7.D.2 to allow reactor operation to 

continue, in the event any containment 

isolation valve becomes inoperable, 

provided the affected penetration flow 

path is isolated by the use of at least one 

closed and de-activated automatic valve, 

closed manual valve, or blind flange. 

The corresponding change to TS Section 

4.7.D.2 is consistent with NUREG–1433 

actions and completion times. 

Date of Issuance: January 26, 2010. 

Effective date: As of the date of 

issuance, and shall be implemented 

within 60 days. 

Amendment No.: 242. 

Facility Operating License No. DPR– 

28: Amendment revised the License and 

Technical Specifications. 

Date of initial notice in Federal 

Register: November 3, 2009 (74 FR 

56886). The supplement letter dated 

November 16, 2009, provided additional 

information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the staff’s original 

proposed no significant hazards 

consideration determination. The 

Commission’s related evaluation of this 

amendment is contained in a Safety 

Evaluation dated January 26, 2010. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket No. 50–461, Clinton Power 

Station, Unit No. 1, DeWitt County, 

Illinois 

Date of application for amendment: 

June 26, 2009, as supplemented by 

letters dated November 4, November 17, 

November 20, December 9, December 

14, December 17, December 28, 2009, 

and January 11, 2010. 

Brief description of amendment: The 

amendment modifies CPS License 

Condition 2.B.(6) and create new 

License Conditions 1.J, 2.B.(7), and 

2.C.(25) as part of a pilot program to 

irradiate Cobalt (Co)-59 target to 

produce Co-60. In addition to the 

proposed license condition changes, the 

amendment would modify Technical 

Specification 4.2.1, ‘‘Fuel Assemblies,’’ 

to describe the Isotope Test Assemblies 

being used. 

Date of issuance: January 15, 2010. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days. 

Amendment No.: 190. 

Facility Operating License No. NPF– 

62: The amendment revised the 

Technical Specifications and License. 

Date of initial notice in Federal 

Register: December 14, 2009 (74 FR 

66159–66163). 

The November 20, December 9, 

December 14, December 17, December 

28, 2009, and January 11, 2010 

supplements, contained clarifying 

information and did not change the NRC 

staff’s initial proposed finding of no 

significant hazards consideration. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated January 15, 

2010. 

No significant hazards consideration 

comments 

Nine Mile Point Nuclear Station, LLC, 

Docket No. 50–220, Nine Mile Point 

Nuclear Station, Unit No. 1 (NMP 1), 

Oswego County, New York 

Date of application for amendment: 

March 3, 2009, as supplemented on 

December 17, 2009. 

Brief description of amendments: The 

amendment modifies Technical 

Specification (TS) Section 3.2.1, 

‘‘Reactor Vessel Heatup and Cooldown 

Rates,’’ and Section 3.2.2, ‘‘Minimum 

Reactor Vessel Temperature for 

Pressurization,’’ by replacing the 

existing reactor vessel heatup and 

cooldown rate limits and the pressure 

and temperature limit curves with 

references to the Pressure and 

Temperature Limits Report (PTLR). In 

addition, the amendment adds a new 

definition for PTLR to TS Section 1.0, 

‘‘Definitions,’’ and a new section 

addressing administrative requirements 

for the PTLR to TS Section 6.0, 

‘‘Administrative Controls.’’ 

Date of issuance: January 21, 2010. 

Effective date: As of the date of 

issuance to be implemented within 30 

days of the date of issuance. 

Amendment No.: 204. 

Renewed Facility Operating License 

No. DPR–063: The amendment revises 

the License and TSs. 

Date of initial notice in Federal 

Register: May 19, 2009 (74 FR 23447). 

The supplemental letter dated December 

17, 2009, provided additional 

information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the Nuclear 

Regulatory Commission staff’s initial 

proposed no significant hazards 

consideration determination. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated January 21, 

2010. 

No significant hazards consideration 

comments received: No. 

Tennessee Valley Authority, Docket No. 

50–390, Watts Bar Nuclear Plant (WBN), 

Unit 1, Rhea County, Tennessee 

Date of application for amendment: 

October 20, 2009. 

Brief description of amendment: The 

amendment deletes paragraph d of 

Technical Specification (TS) 5.2.2, ‘‘Unit 

Staff,’’ to eliminate working-hour 

restrictions in the TS, as similar 

requirements are sufficiently imposed 

by Title 10 of the Code of Federal 

Regulations Part 26, Subpart I. 

Date of issuance: January 20, 2010. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days. 

Amendment No.: 83. 

Facility Operating License No. NPF– 

90: Amendment revised the License and 

TSs. 

Date of initial notice in Federal 

Register: November 17, 2009 (74 FR 

59264). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated January 20, 

2010. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 29th day 

of January 2010. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2010–2554 Filed 2–8–10; 8:45 am] 

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