Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 16271 

see ‘‘Accessing Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: Mr. 

James Medoff, Division of License 

Renewal, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001; telephone: 301–415–2715; email: 

James.Medoff@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

Accessing Information and Submitting 

Comments 

A. Accessing Information 

Please refer to Docket ID NRC–2012– 

0070 when contacting the NRC about 

the availability of information regarding 

this document. You may access 

information related to this document by 

the following methods: 

• Federal Rulemaking Web Site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0070. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may access publiclyavailable documents online in the NRC 

Library at http://www.nrc.gov/readingrm/adams.html. To begin the search, 

select ‘‘ADAMS Public Documents’’ and 

then select ‘‘Begin Web-based ADAMS 

Search.’’ For problems with ADAMS, 

please contact the NRC’s Public 

Document Room (PDR) reference staff at 

1–800–397–4209, 301–415–4737, or by 

email to pdr.resource@nrc.gov. Draft 

LR–ISG–2011–04 is available 

electronically under ADAMS Accession 

No. ML12004A149. The GALL Report 

and SRP–LR are available under 

ADAMS Accession Nos. ML103490041 

and ML103490036, respectively. 

• NRC’s PDR: You may examine and 

purchase copies of public documents at 

the NRC’s PDR, Room O1–F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, Maryland 20852. 

• NRC’s Interim Staff Guidance Web 

Site: The LR–ISG documents are also 

available online under http://

www.nrc.gov/reading-rm/doccollections/isg/license-renewal.html. 

B. Submitting Comments 

Please include Docket ID NRC–2012– 

0070 in the subject line of your 

comment submission, in order to ensure 

that the NRC is able to make your 

comment submission available to the 

public in this docket. 

The NRC cautions you not to include 

identifying or contact information in 

comment submissions that you do not 

want to be publicly disclosed. The NRC 

posts all comment submissions at http://

www.regulations.gov as well as entering 

the comment submissions into ADAMS, 

and the NRC does not edit comment 

submissions to remove identifying or 

contact information. 

If you are requesting or aggregating 

comments from other persons for 

submission to the NRC, then you should 

inform those persons not to include 

identifying or contact information in 

their comment submissions that they do 

not want to be publicly disclosed. Your 

request should state that the NRC will 

not edit comment submissions to 

remove such information before making 

the comment submissions available to 

the public or entering the comment 

submissions into ADAMS. 

Background 

The NRC issues LR–ISGs to 

communicate insights and lessons 

learned and to address emergent issues 

not covered in license renewal guidance 

documents, such as the GALL Report 

and SRP–LR. In this way, the NRC staff 

and stakeholders may use the guidance 

in an LR–ISG document before it is 

incorporated into a formal license 

renewal guidance document revision. 

The NRC staff issues LR–ISG in 

accordance with the LR–ISG Process, 

Revision 2 (ADAMS Accession No. 

ML100920158); for which a notice of 

availability was published in the 

Federal Register on June 22, 2010 (75 

FR 35510). 

The NRC staff has determined that 

existing guidance in the SRP–LR and 

GALL Report needs to be revised for 

PWR reactor vessel internal 

components. The guidance document 

changes that are proposed in draft LR– 

ISG–2011–04 are based on the 

conclusions of the NRC’s revised safety 

evaluation (ADAMS Accession No. 

ML11308A770). 

Proposed Action 

By this action, the NRC is requesting 

public comments on draft LR–ISG– 

2011–04. This LR–ISG proposes certain 

revisions to NRC guidance in the SRP– 

LR and GALL Report. The NRC staff will 

make a final determination regarding 

issuance of the LR–ISG after it considers 

any public comments received in 

response to this request. 

Dated at Rockville, Maryland, this 13th day 

of March, 2012. 

For the Nuclear Regulatory Commission. 

Melanie A. Galloway, 

Acting Director, Division of License Renewal, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2012–6694 Filed 3–19–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2012–0061] 

Biweekly Notice: Applications and 

Amendments to Facility Operating 

Licenses Involving No Significant 

Hazards Considerations 

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 February 23 

to March 7, 2012. The last biweekly 

notice was published on March 6, 2012 

(77 FR 13369). 

ADDRESSES: You may access information 

and comment submissions related to 

this document, which the NRC 

possesses and is publicly available, by 

searching on http://www.regulations.gov 

under Docket ID NRC–2012–0061. 

You may submit comments by the 

following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0061. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–492–3668; 

email: Carol.Gallagher@nrc.gov. 

• Mail comments to: Cindy Bladey, 

Chief, Rules, Announcements, and 

Directives Branch (RADB), Office of 

Administration, Mail Stop: TWB–05– 

B01M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

• Fax comments to: RADB at 301– 

492–3446. 

For additional direction on accessing 

information and submitting comments, 

see ‘‘Accessing Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

SUPPLEMENTARY INFORMATION: 


srobinson on DSK4SPTVN1PROD with NOTICES
16272 Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 

I. Accessing Information and 

Submitting Comments 

A. Accessing Information 

Please refer to Docket ID NRC–2012– 

0061 when contacting the NRC about 

the availability of information regarding 

this document. You may access 

information related to this document, 

which the NRC possesses and is 

publicly available, by the following 

methods: 

• Federal Rulemaking Web Site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0061. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may access publicly 

available documents online in the NRC 

Library at http://www.nrc.gov/readingrm/adams.html. To begin the search, 

select ‘‘ADAMS Public Documents’’ and 

then select ‘‘Begin Web-based ADAMS 

Search.’’ For problems with ADAMS, 

please contact the NRC’s Public 

Document Room (PDR) reference staff at 

1–800–397–4209, 301–415–4737, or by 

email to pdr.resource@nrc.gov. 

Documents may be viewed in ADAMS 

by performing a search on the document 

date and docket number. 

• NRC’s PDR: You may examine and 

purchase copies of public documents at 

the NRC’s PDR, Room O1–F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, Maryland 20852. 

B. Submitting Comments 

Please include Docket ID NRC–2012– 

0061 in the subject line of your 

comment submission, in order to ensure 

that the NRC is able to make your 

comment submission available to the 

public in this docket. 

The NRC cautions you not to include 

identifying or contact information in 

comment submissions that you do not 

want to be publicly disclosed. The NRC 

posts all comment submissions at 

http://www.regulations.gov as well as 

entering the comment submissions into 

ADAMS, and the NRC does not edit 

comment submissions to remove 

identifying or contact information. 

If you are requesting or aggregating 

comments from other persons for 

submission to the NRC, then you should 

inform those persons not to include 

identifying or contact information in 

their comment submissions that they do 

not want to be publicly disclosed. Your 

request should state that the NRC will 

not edit comment submissions to 

remove such information before making 

the comment submissions available to 

the public or entering the comment 

submissions into ADAMS. 

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) 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; (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. 

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 NRC’s PDR, located at 

One White Flint North, Room O1–F21, 

11555 Rockville Pike (first floor), 

Rockville, Maryland 20852. The NRC’s 

regulations are accessible online at the 

NRC Library on the NRC’s Web site at 

http://www.nrc.gov/reading-rm/doccollections/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 


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Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 16273 

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, then 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’s E-Filing rule 

(72 FR 49139, August 28, 2007). The EFiling 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 10 

days prior to the filing deadline, the 

participant should contact the Office of 

the Secretary by email at 

hearing.docket@nrc.gov, or by telephone 

at 301–415–1677, to request (1) a digital 

identification (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 the 

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 the 

NRC’s ‘‘Guidance for Electronic 

Submission,’’ which is available on the 

agency’s public Web site at http:// 

www.nrc.gov/site-help/esubmittals.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 the Electronic 

Information Exchange System, users 

will be required to install a Web 

browser plug-in from the NRC’s Web 

site. Further information on the Webbased 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 

submit a request for hearing or petition 

for leave to intervene. Submissions 

should be in Portable Document Format 

(PDF) in accordance with the NRC’s 

guidance available on the NRC’s public 

Web site at http://www.nrc.gov/sitehelp/e-submittals.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 

email notice confirming receipt of the 

document. The E-Filing system also 

distributes an email notice that provides 

access to the document to the NRC’s 

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’s Web site at http:// 

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

MSHD.Resource@nrc.gov, or by a tollfree call at 1–866–672–7640. 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 first-class 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 the NRC’s 

electronic hearing docket which is 

available to the public at http:// 

ehd1.nrc.gov/ehd/, unless excluded 


srobinson on DSK4SPTVN1PROD with NOTICES
16274 Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 

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 the 

date of publication of this notice. Nontimely 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 

NRC’s PDR, located at One White Flint 

North, Room O1–F21, 11555 Rockville 

Pike (first floor), Rockville, Maryland 

20852. Publicly available documents 

created or received at the NRC are 

accessible electronically through 

ADAMS in the NRC Library 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 PDR 

Reference staff at 1–800–397–4209, 301– 

415–4737, or by email to 

pdr.resource@nrc.gov. 

Duke Energy Carolinas, LLC, et al., 

Docket Nos. 50–413 and 50–414, 

Catawba Nuclear Station, Units 1 and 2, 

York County, South Carolina 

Date of amendment request: July 21, 

2011. 

Description of amendment request: 

The amendments would revise 

Technical Specifications (TSs) 3.3.2, 

‘‘Engineered Safety Feature Actuation 

System (ESFAS) Instrumentation,’’ 

3.5.4, ‘‘Refueling Water Storage Tank 

(RWST),’’ and 3.6.6, ‘‘Containment 

Spray System.’’ 

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 changes delete superseded 

TS requirements following the 

implementation of NRC approved 

modifications. As such, they do not adversely 

affect accident initiators or precursors nor do 

they alter the design assumptions, 

conditions, or configurations of the facility. 

The proposed changes do not alter or prevent 

the ability of Structures, Systems, and 

Components (SSCs) to perform their intended 

function to mitigate the consequences of an 

initiating event within the assumed 

acceptance limits. In review of the discussion 

above, it can be concluded that the 

probability or consequences of any accident 

previously evaluated will not be affected. 

2. Does the proposed amendment create 

the possibility of a new or different kind of 

accident from any accident previously 

evaluated? 

Response: No. 

This amendment request will not impact 

the accident analyses. The proposed changes 

delete superseded TS requirements following 

the implementation of NRC approved 

modifications. As such, they will not alter 

the requirements of any of the subject SSCs 

or their function during accident conditions. 

No new or different accidents will result 

from the proposed changes. The changes do 

not involve a physical alteration of the plant 

(i.e., no new or different type of equipment 

will be installed) or any changes in methods 

governing normal plant operation. The 

changes do not alter assumptions made in the 

safety analyses. The proposed changes are 

consistent with the safety analyses 

assumptions. In review of the discussion 

above, it can be concluded that these changes 

will not create the possibility of a new or 

different kind of accident from any accident 

previously evaluated. 

3. Does the proposed amendment involve 

a significant reduction in a margin of safety? 

Response: No. 

The proposed changes delete superseded 

TS requirements following the 

implementation of NRC approved 

modifications. As such, they do not alter the 

manner in which safety limits, limiting safety 

system settings, or limiting conditions for 

operation are determined. The safety 

analyses acceptance criteria are not affected 

by these changes. The proposed changes will 

not result in plant operation in a 

configuration outside the design basis. The 

proposed changes do not adversely affect 

systems that respond to safely shut down the 

plant and to maintain the plant in a safe 

shutdown condition. In review of the 

discussion above, it can be concluded that 

the proposed changes will not involve a 

significant reduction in a margin of safety. 

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 

amendments requested involve no 

significant hazards consideration. 

Attorney for licensee: Lara S. Nichols, 

Associate General Counsel, Duke Energy 

Corporation, 526 South Church Street— 

EC07H, Charlotte, NC 28202. 

NRC Branch Chief: Nancy Salgado. 

Entergy Gulf States Louisiana, LLC, 

and Entergy Operations, Inc., Docket 

No. 50–458, River Bend Station, Unit 1, 

West Feliciana Parish, Louisiana 

Entergy Nuclear Operations, Inc., 

Docket Nos. 50–155 and 72–043 (ISFSI), 

Big Rock Point Plant, Charlevoix 

County, Michigan 

Entergy Nuclear Operations, Inc., 

Docket Nos. 50–003, 50–247 and 50– 

286, Indian Point Nuclear Generating 

Units 1, 2 and 3, Westchester County, 

New York 

Entergy Nuclear Operations, Inc., 

Docket No. 50–333, James A. FitzPatrick 

Nuclear Power Plant, Oswego County, 

New York 

Entergy Nuclear Operations, Inc., 

Docket No. 50–255, Palisades Nuclear 

Plant, Van Buren County, Michigan 

Entergy Nuclear Operations, Inc., 

Docket No. 50–293, Pilgrim Nuclear 

Power Station, Plymouth County, 

Massachusetts 

Entergy Nuclear Vermont Yankee, LLC 

and Entergy Nuclear Operations, Inc., 

Docket No. 50–271, Vermont Yankee 

Nuclear Power Station, Vernon, 

Vermont 

Entergy Operations, Inc., Docket Nos. 

50–313 and 50–368, Arkansas Nuclear 

One, Units 1 and 2, Pope County, 

Arkansas 

Entergy Operations, Inc., System Energy 

Resources, Inc., South Mississippi 

Electric Power Association, and 

Entergy Mississippi, Inc., Docket No. 

50–416, Grand Gulf Nuclear Station, 

Unit 1, Claiborne County, Mississippi 

Entergy Operations, Inc., Docket No. 50– 

382, Waterford Steam Electric Station, 

Unit 3, St. Charles Parish, Louisiana 

Date of amendment request: 

December 13, 2011. 

Description of amendment request: 

The amendments would approve 

changes to the Quality Assurance 

Program Manual (QAPM) and Technical 

Specifications (TSs) for the above 

specified plants. The proposed changes 

standardize unit staff qualification 

requirements for the Entergy fleet. 

Certain changes to the QAPM are a 

reduction in commitment and, in 

accordance with 10 CFR 50.54(a)(4), 

NRC approval is required prior to 

implementation. The related TS changes 

for unit staff qualifications are requested 

in accordance with 10 CFR 50.90. 

Basis for proposed no significant 

hazards consideration determination: 

As required by 10 CFR 50.91(a), the 

licensee has provided its analysis of the 


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Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 16275 

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 changes involve the revision 

or relocation of administrative requirements 

associated with unit staff qualifications and 

will not impact the design, operation, testing, 

performance, or reliability of any plant 

system or component. The TS changes will 

require plants currently required to be 

qualified per ANSI [American National 

Standards Institute] N18.1–1971 to be 

qualified to the later standard of ANSI/ANS 

[American Nuclear Society] 3.1–1978. The 

changes do not affect licensed operator 

qualifications or training, which will 

continue to comply with applicable 

regulations. Qualification requirements for 

the Shift Technical Advisor (STA) are revised 

to comply with a later standard that provides 

more prescriptive qualifications and ensures 

that the STA maintains an active status. The 

changes do not affect operating procedures or 

operator response to any accidents 

previously evaluated in the Updated Final 

Safety Analysis Report (UFSAR). 

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? 

Response: No. 

The proposed amendment is 

administrative in nature and does not 

introduce any credible new failure 

mechanisms, malfunctions, or accident 

initiators. The changes will not alter the 

plant configuration, require new plant 

equipment to be installed, alter accident 

analysis assumptions, introduce any new 

accident initiators, or affect the function of 

plant systems or the manner in which 

systems are operated, maintained, modified, 

tested, or inspected. 

Therefore, the proposed change does not 

create the possibility of a new or different 

kind of accident from any accident 

previously evaluated. 

(3) Does the proposed amendment involve 

a significant reduction in a margin of safety? 

Response: No. 

The proposed amendment involves the 

revision or relocation of administrative 

requirements associated with unit staff 

qualifications. The proposed change is 

administrative in nature and does not involve 

any physical changes to the plant or alter the 

manner in which plant systems are operated, 

maintained, modified, tested, or inspected. 

The proposed change does not alter the 

manner in which safety limits, limiting safety 

system settings or limiting conditions for 

operation are determined. The safety analysis 

acceptance criteria are not affected by this 

change. The proposed change will not result 

in plant operation in a configuration outside 

the design basis. The proposed change does 

not adversely affect systems that respond to 

safely shutdown the plant and to maintain 

the plant in a safe shutdown condition. 

Therefore, the proposed change does not 

involve a significant reduction in a margin of 

safety. 

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. 

Attorneys for licensee: Joseph A. 

Aluise, Associate General Counsel— 

Nuclear, Entergy Services, Inc., 639 

Loyola Avenue, New Orleans, LA 70113 

(for River Bend Station, Unit 1, 

Arkansas Nuclear One, Units 1 and 2, 

Grand Gulf Nuclear Station, Unit 1, and 

Waterford Steam Electric Station, Unit 

3); and William C. Dennis, Assistant 

General Counsel, Entergy Nuclear 

Operations, Inc., 440 Hamilton Avenue, 

White Plains, NY 10601 (for Big Rock 

Point Plant (ISFSI), James A. Fitzpatrick 

Nuclear Power Plant, Indian Point 

Nuclear Generating Units 1, 2, and 3, 

Palisades Nuclear Plant, Pilgrim Nuclear 

Power Station, and Vermont Yankee 

Nuclear Power Station). 

NRC Branch Chief: Michael T. 

Markley. 

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. 

A 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 NRC’s Public Document Room 

(PDR), located at One White Flint North, 

Room O1–F21, 11555 Rockville Pike 

(first floor), Rockville, Maryland 20852. 

Publicly available documents created or 

received at the NRC are accessible 

online through the Agencywide 

Documents Access and Management 

System (ADAMS) in the NRC Library at 

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’s Reference 

staff at 1–800–397–4209, 301–415–4737 

or by email to pdr.resource@nrc.gov. 

Detroit Edison Company, Docket No. 

50–341, Fermi 2, Monroe County, 

Michigan 

Date of application for amendment: 

August 12, 2011, supplemented by letter 

dated October 20, 2011. 

Brief description of amendment: The 

amendment revised TS 3.8.3, ‘‘Diesel 

Fuel Oil and Starting Air,’’ by relocating 

the current stored diesel fuel oil 

numerical volume requirements from 

the Technical Specification to the TS 

Bases consistent with Technical 

Specification Task Force TSTF–501. 

Date of issuance: February 24, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days. 

Amendment No.: 188. 

Facility Operating License No. NPF– 

43: Amendment revised the Technical 

Specifications and License. 

Date of initial notice in Federal 

Register: October 4, 2011 (76 FR 

61394). 

The supplemental letter dated 

October 20, 2011 did not change staff’s 

original proposed no significant hazards 

consideration determination as 

published in the initial Federal 

Register. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated February 24, 

2012. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket Nos. 50–373, LaSalle County 

Station, Unit 1, LaSalle County, 

Illinois 


srobinson on DSK4SPTVN1PROD with NOTICES
16276 Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 

Date of application for amendment: 

October 12, 2011, as supplemented by 

letter(s) dated January 30, 2012, and 

February 13, 2012. 

Brief description of amendment: The 

amendment request proposed changes 

to the Technical Specifications (TSs) to 

revise Section 2.1.1, ‘‘Reactor Core SLs’’ 

minimum critical power ratio safety 

limit (MCPR SL) from ≥ 1.11 to ≥ 1.13 

for two-loop recirculation operation and 

from ≥ 1.12 to ≥ 1.15 for a single-loop 

recirculation operation. 

Date of issuance: March 1, 2012. 

Effective date: As of the date of 

issuance and shall be implemented after 

Cycle 14 is completed and prior to the 

operation of Cycle 15. 

Amendment No.: 205. 

Facility Operating License Nos. NPF– 

11: The amendment revised the 

Technical Specifications and License. 

Date of initial notice in Federal 

Register: January 3, 2012 (77 FR 139). 

The January 30, 2012, and February 

13, 2012, supplements contained 

clarifying information, did not expand 

the scope of the application as originally 

noticed, and did not change the staff’s 

original proposed no significant hazards 

consideration (NSHC) determination. 

The Commission’s related evaluation 

of the amendment and final NSHC 

determination is contained in a Safety 

Evaluation dated March 1, 2012. 

No significant hazards consideration 

comments received: No. 

Florida Power and Light Company, 

Docket Nos. 50–250 and 50–251, 

Turkey Point Plant, Units 3 and 4, 

Miami-Dade County, Florida 

Date of application for amendment: 

February 21, 2011, as supplemented by 

letter dated July 21, 2011. 

Brief description of amendment: 

Selected figures and values from the 

technical specifications (TSs) are being 

relocated to the Core Operating Limits 

Report (COLR), including TS Figure 

2.1–1 cited in TS 2.1.1, selected 

portions of Note 1 on Overtemperature 

D T and Note 3 on Overpower D T cited 

in TS Table 2.2–1, TS Figure 3.1–1 cited 

in TS 3/4.1.1.1, Shutdown Margin value 

cited in TS 3/4.1.1.2, Moderator 

Temperature Coefficient values cited in 

TS 3/4.1.1.3, and Departure from 

Nucleate Boiling values cited in TS 

3.2.5. The description of the COLR in 

TS 6.9.1.7 is also revised to reflect these 

changes. The affected TS figures and 

technical limits cited above are only 

being relocated to the COLR and are not 

being changed under this license 

amendment. 

Date of issuance: February 23, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days of issuance. 

Amendment Nos.: Unit 3—247 and 

Unit 4—243. 

Renewed Facility Operating License 

Nos. DPR–31 and DPR–41: Amendments 

revised the Technical Specifications and 

Surveillance Requirements. 

Date of initial notice in Federal 

Register: May 31, 2011 (76 FR 31374). 

The supplement dated July 21, 2011, 

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 as 

published in the Federal Register. 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated February 23, 

2012. 

No significant hazards consideration 

comments received: No. 

NextEra Energy Duane Arnold, LLC, 

Docket No. 50–331, Duane Arnold 

Energy Center, Linn County, Iowa 

Date of application for amendment: 

February 23, 2011, as supplemented by 

letters dated April 20, August 15, 

November 1, 2011, and February 3, 

2012. 

Brief description of amendment: The 

amendment revised the Technical 

Specifications (TSs) by relocating 

specific surveillance frequencies to a 

licensee-controlled program with the 

guidance of Nuclear Energy Institute 

(NEI) 04–10, ‘‘Risk-Informed Technical 

Specifications Initiative 5b, RiskInformed Method for Control of 

Surveillance Frequencies.’’ The 

amendment adopted NRC-approved 

Technical Specification Task Force 

(TSTF)–425, Revision 3, ‘‘Relocate 

Surveillance Frequencies to Licensee 

Control—RITSTF [Risk-Informed TSTF] 

Initiative 5b.’’ When implemented, 

TSTF–425 relocates most periodic 

frequencies of TS surveillances to a 

licensee-controlled program, the 

Surveillance Frequency Control 

Program, and provides requirements for 

the new program in the Administrative 

Controls section of the TSs. 

Date of issuance: February 24, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days. 

Amendment No.: 280. 

Renewed Facility Operating License 

No. DPR–49: The amendment revised 

the Renewed Facility Operating License 

and Technical Specifications. 

Date of initial notice in Federal 

Register: May 17, 2011 (76 FR 28474). 

The supplemental letters dated April 

20, August 15, November 1, 2011 and 

February 3, 2012, 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 as 

published in the Federal Register. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated February 24, 

2012. 

No significant hazards consideration 

comments received: No. 

NextEra Energy Seabrook, LLC, Docket 

No. 50–443, Seabrook Station, Unit 1, 

Rockingham County, New Hampshire 

Date of amendment request: April 21, 

2011. 

Description of amendment request: 

The amendment revised operability 

requirements for the leakage detection 

systems, eliminated redundant 

Technical Specification (TS) 

requirements, and revised the TS 

actions to include conditions and 

required actions for inoperable leakage 

detection systems similar to those in 

NUREG 1431, ‘‘Standard Technical 

Specifications—Westinghouse Plants.’’ 

The amendment also incorporated the 

requirements of TSTF–513, Revision 3, 

‘‘Revise [Pressurized Water Reactor] 

Operability Requirements and Actions 

for [Reactor Coolant System] Leakage 

Instrumentation.’’ 

Date of issuance: February 23, 2012. 

Effective date: As of its date of 

issuance and shall be implemented 

within 90 days. 

Amendment No.: 129. 

Facility Operating License No. NPF– 

86: The amendment revised the TS and 

the License. 

Date of initial notice in Federal 

Register: August 9, 2011 (76 FR 48913). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated February 23, 

2012. 

No significant hazards consideration 

comments received: No. 

NextEra Energy Seabrook, LLC, Docket 

No. 50–443, Seabrook Station, Unit 1, 

Rockingham County, New Hampshire 

Date of amendment request: 

November 17, 2011. 

Description of amendment request: 

The proposed change revises Technical 

Specification 3.3.3.5, ‘‘Remote 

Shutdown System Table 3.3–9,’’ by 

removing the location information of 

transfer switches, control circuits, and 

instruments. 

Date of issuance: February 28, 2012. 

Effective date: As of its date of 

issuance and shall be implemented 

within 30 days. 

Amendment No.: 130. 


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Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 16277 

Facility Operating License No. NPF– 

86: The amendment revised the TS and 

the License. 

Date of initial notice in Federal 

Register: December 27, 2011 (76 FR 

80976). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated February 28, 

2012. 

No significant hazards consideration 

comments received: No. 

South Carolina Electric & Gas Company, 

South Carolina Public Service 

Authority, Docket No. 50–395, Virgil 

C. Summer Nuclear Station, Unit 1, 

Fairfield County, South Carolina 

Date of application for amendment: 

May 2, 2011. 

Brief description of amendment: This 

license amendment revised the 

Technical Specifications (TSs) 3.4.6.1, 

‘‘RCS [Reactor Coolant System] Leakage 

Detection Systems,’’ to define a new 

time limit for restoring inoperable RCS 

leakage detection instrumentation to 

operable status, establish alternate 

methods of monitoring RCS leakage 

when monitors are inoperable, and to 

reflect the requested changes and more 

accurately reflect the contents of the 

facility design bases related to the 

operability of the RCS leakage detection 

instrumentation. 

Date of issuance: February 22, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 120 days. 

Amendment No.: 186. 

Renewed Facility Operating License 

No. NPF–12: Amendment revises the 

License and TSs. 

Date of initial notice in Federal 

Register: July 12, 2011 (76 FR 40941). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated February 22, 

2012. 

No significant hazards consideration 

comments received: No. 

South Carolina Electric & Gas Company, 

Docket No. 50–395, Virgil C. Summer, 

Nuclear Station Unit 1, Jenkinsville, 

South Carolina 

Date of application for amendment: 

April 18, 2011, and supplemented by 

letter dated September 26, 2011. 

Brief description of amendment: This 

amendment revised the VCSNS 

Technical Specification Table 4.3–2 for 

the ‘‘Engineered Safety Feature 

Actuation System Instrumentation’’ to 

allow the surveillance frequency to be 

expanded from quarterly to every 18 

months or refueling for the specific 

Westinghouse type AR relays used as 

Solid State Protection System slave 

relays or auxiliary relays. 

Date of Issuance: March 6, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 120 days. 

Amendment No: 187. 

Renewed Facility Operating License 

No. NPF–12: Amendment revised the 

Licenses and Technical Specifications. 

Date of initial notice in Federal 

Register: August 16, 2011 (76 FR 

50763). 

The licensee’s supplemental letter 

contained clarifying information, did 

not change the scope of the original 

license amendment request, did not 

change the NRC staff’s initial proposed 

finding of no significant hazards 

consideration determination, and did 

not expand the scope of the original 

Federal Register notice. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated March 6, 2012. 

No significant hazards consideration 

comments received: No. 

Southern Nuclear Operating Company, 

Inc., Docket Nos. 50–424 and 50–425, 

Vogtle Electric Generating Plant, 

Units 1 and 2, Burke County, Georgia 

Date of application for amendment: 

March 3, 2011. 

Brief description of amendment: The 

amendments revised the Technical 

Specifications (TS) 3.3.1 Reactor Trip 

System Instrumentation Table 3.3.1–1 

and TS 3.3.2 Emergency System Feature 

Actuation System Table 3.3.2–1. 

Specifically, the change incorporates the 

Technical Specification Task Force 

Traveler TSTF–493–A, ‘‘Clarify 

Application of Setpoint Methodology 

for LSSS [limiting safety system setting] 

Function. The setpoint methodology 

incorporates revised (more conservative) 

calculations associated with the P–14, 

Steam Generator Water Level High-High 

instrument setpoint and associated 

allowable value. Also, the amendments 

contain administrative changes. 

Specifically, the amendment correct a 

typographical error on TS Table 3.3.1– 

1, page 9 of 9, and deletes an expired 

allowance provided by TS Table 3.3.2– 

1, Note J. 

Date of issuance: February 27, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days from the date of 

issuance. 

Amendment Nos.: Unit 1—165 and 

Unit 2—147. 

Facility Operating License Nos. NPF– 

68 and NPF–81: Amendments revised 

the licenses and the technical 

specifications. 

Date of initial notice in Federal 

Register: May 24, 2011 (re-noticed on 

July 12, 2011). 

The supplements dated August 12, 

2011, and December 9, 2011, 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 the amendments is contained in 

Safety Evaluation dated February 27, 

2012. 

No significant hazards consideration 

comments received: No. 

Virginia Electric and Power Company, 

Docket Nos. 50–338 and 50–339, 

North Anna Power Station, Units 1 

and 2, Louisa County, Virginia 

Date of application for amendment: 

July 19, 2010, and supplemented by 

additional information dated September 

9, 2010, January 26, 2011, and May 16, 

2011, contained clarifying information 

only and did not change the initial no 

significant hazards determination or 

expand the scope of the initial 

application. 

Brief description of amendment: The 

proposed amendments revise Technical 

Specification 5.6.5.b, ‘‘Core Operating 

Limits Report (COLR),’’ to include 

Appendix C, ‘‘Qualification of the 

Westinghouse WRB–2M CHF 

Correlation in the Dominion VIPRE–D 

Computer Code.’’ This would allow 

NAPS to use the VIPRE–D/WRB–2M 

and VIPRE–D/W–3 correlation pairs to 

perform licensing calculations with 

Westinghouse RFA–2 fuel in the cores. 

Date of issuance: February 29, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days. 

Amendment Nos.: Unit 1—266 and 

Unit 2—247. 

Renewed Facility Operating License 

Nos. NPF–4 and NPF–7: Amendments 

changed the licenses and the technical 

specifications. 

Date of initial notice in Federal 

Register: July 26, 2011 (76 FR 44618). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated February 29, 

2012. 

No significant hazards consideration 

comments received: No. 

Virginia Electric and Power Company, 

Docket Nos. 50–338 and 50–339, 

North Anna Power Station, Units 1 

and 2, Louisa County, Virginia 

Date of application for amendment: 

October 21, 2010, as supplemented by 

letter dated June 23, 2011, and August 

22, 2011, contained clarifying 

information only and did not change the 

initial no significant hazards 

determination or expand the scope of 

the initial application. 


srobinson on DSK4SPTVN1PROD with NOTICES
16278 Federal Register / Vol. 77, No. 54 / Tuesday, March 20, 2012 / Notices 

Brief description of amendment: The 

proposed amendments revised 

Technical Specification 5.6.5.b, ‘‘Core 

Operating Limits Report (COLR),’’ to 

permit the use of the ‘‘Westinghouse 

Best Estimate—Large Break Loss-ofCoolant Accident (BE–LBLOCA) 

Evaluation Methodology using the 

Automated Statistical Treatment of 

Uncertainty Method (ASTRUM)’’ for the 

analysis of LBLOCA. 

Date of issuance: February 29, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days. 

Amendment Nos.: Unit 1—267 and 

Unit 2—248. 

Renewed Facility Operating License 

Nos. NPF–4 and NPF–7: Amendments 

changed the licenses and the technical 

specifications. 

Date of initial notice in Federal 

Register: November 30, 2010 (75 FR 

74097). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated February 29, 

2012. 

No significant hazards consideration 

comments received: No. 

For the Nuclear Regulatory Commission. 

Dated at Rockville, Maryland, this 8th day 

of March 2012. 

Michele G. Evans, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2012–6261 Filed 3–19–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–247 and 50–286; NRC– 

2008–0672] 

License Renewal Application for Indian 

Point Nuclear Generating Units 2 and 

3; Entergy Nuclear Operations, Inc. 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: License renewal application; 

intent to prepare supplement to final 

SEIS. 

SUMMARY: On April 23, 2007, Entergy 

Operations, Inc. (Entergy), submitted to 

the U.S. Nuclear Regulatory 

Commission (NRC) an application for 

renewal of Facility Operating Licenses 

DPR–26 and DPR–64 for an additional 

20 years of operation at Indian Point 

Nuclear Generating Units 2 and 3 (IP2 

and IP3). The current operating licenses 

for IP2 and IP3 expire on September 28, 

2013, and December 12, 2015, 

respectively. The purpose of this 

document is to inform the public that 

the NRC will be preparing a supplement 

to the final Supplemental 

Environmental Impact Statement (SEIS) 

to address information on aquatic 

impacts in accordance with the NRC’s 

regulations. 

ADDRESSES: Please refer to Docket ID 

NRC–2008–0672, when contacting the 

NRC about the availability of 

information regarding this document. 

You may access information related to 

this document, which the NRC 

possesses and is publicly available, 

using the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2008–0672. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–492–3668; 

email: Carol.Gallagher@nrc.gov. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may access publicly 

available documents online in the NRC 

Library at http://www.nrc.gov/readingrm/adams.html. To begin the search, 

select ‘‘ADAMS Public Documents’’ and 

then select ‘‘Begin Web-based ADAMS 

Search.’’ For problems with ADAMS, 

please contact the NRC’s Public 

Document Room (PDR) reference staff at 

1–800–397–4209, 301–415–4737, or by 

email to pdr.resource@nrc.gov. The 

ADAMS accession number for each 

document referenced in this notice (if 

that document is available in ADAMS) 

is provided the first time that a 

document is referenced. 

• NRC’s PDR: You may examine and 

purchase copies of public documents at 

the NRC’s PDR, Room O1–F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, Maryland 20852. 

FOR FURTHER INFORMATION CONTACT: Ms. 

Kimberly Green, Division of License 

Renewal, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001; telephone: 301–415–1627; email: 

Kimberly.Green@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

Discussion 

Entergy submitted an application for 

renewal of Facility Operating Licenses 

DPR–26 and DPR–64 for an additional 

20 years of operation at IP2 and IP3. 

Approximately 24 miles north of New 

York City, IP2 and IP3 are located in 

Westchester County in the Village of 

Buchanan, New York. 

The current operating licenses for IP2 

and IP3 expire on September 28, 2013, 

and December 12, 2015, respectively. 

The application for renewal, dated April 

23, 2007, was submitted pursuant to 

Title 10 of the Code of Federal 

Regulations (10 CFR) Part 54, which 

included an environmental report (ER). 

On December 3, 2010, the NRC staff 

issued its final SEIS, documenting its 

final analysis and recommendation on 

the proposed action—renewal of the 

operating licenses for IP2 and IP3. The 

final SEIS is available in ADAMS under 

package Accession No. ML103360205. 

This document is being published in 

accordance with the National 

Environmental Policy Act and the 

NRC’s regulations found at 10 CFR Part 

51. The purpose of this document is to 

inform the public that the NRC will be 

preparing a supplement to the final SEIS 

to address information on aquatic 

impacts in accordance with the NRC’s 

regulations found at 10 CFR 51.92. 

Subsequent to the issuance of the 

final SEIS, the NRC staff identified three 

types of new information regarding 

aquatic impacts that necessitate changes 

to the staff’s findings in the final SEIS. 

The new information consists of (1) 

entrainment and impingement field data 

units of measure; (2) a new thermal 

study that characterizes the thermal 

plume of cooling water discharges from 

IP2 and IP3; and (3) new developments 

concerning the staff’s section 7 

consultation under the Endangered 

Species Act of 1973, as amended, with 

the National Marine Fisheries Service 

regarding endangered species. 

In accordance with 10 CFR 51.53(c) 

and 10 CFR 54.23, Entergy submitted 

the ER as part of the application. The ER 

was prepared pursuant to 10 CFR Part 

51 and is available in ADAMS under 

Accession No. ML071210530. In 

addition, the ER is available for public 

inspection at the White Plains Public 

Library located at 100 Martine Avenue, 

White Plains, NY 10601; the Hendrick 

Hudson Free Library located at 185 

Kings Ferry Road, Montrose, NY 10548; 

and the Field Library located at 4 

Neslon Avenue, Peekskill, NY 10566. 

Dated at Rockville, Maryland, this 13th day 

of March, 2012. 

For the Nuclear Regulatory Commission. 

David J. Wrona, 

Chief, Projects Branch 2, Division of License 

Renewal, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2012–6666 Filed 3–19–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards: Notice of Meeting 

In accordance with the purposes of 

Sections 29 and 182b of the Atomic 

Energy Act (42 U.S.C. 2039, 2232b), the 


srobinson on DSK4SPTVN1PROD with NOTICES