9998 Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 

information no less than 10 working 

days prior to the meeting: full name; 

gender; date/place of birth; citizenship; 

visa/green card information (number, 

type, expiration date); passport 

information (number, country, 

telephone); employer/affiliation 

information (name of institution, 

address, country, telephone); title/ 

position of attendee. To expedite 

admittance, attendees with U.S. 

citizenship can provide identifying 

information 3 working days in advance 

by contacting Charlene Williams at 

(202) 358–2183, or fax: (202) 358–4336. 

Patricia D. Rausch, 

Advisory Committee Management Officer, 

National Aeronautics and Space 

Administration. 

[FR Doc. 2012–3920 Filed 2–17–12; 8:45 am] 

BILLING CODE 7510–13–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2012–0038] 

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 January 26, 

2012 to February 8, 2012. The last 

biweekly notice was published on 

February 7, 2012 (77 FR 6144). 

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–2012–0038. You 

may submit comments by the following 

methods: 

• Federal Rulemaking Web Site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0038. 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: 

Accessing Information and Submitting 

Comments 

A. Accessing Information 

Please refer to Docket ID NRC–2012– 

0038 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 NRC–2012–0038. 

• 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. 

• 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– 

0038 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 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 9999 

Commission make a final No Significant 

Hazards Consideration Determination, 

then 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 

regulations are accessible electronically 

from the NRC Library on the NRC Web 

site at 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, 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 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 ESubmittal 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 ESubmittal 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 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 

submit a request for hearing or petition 

for leave to intervene. Submissions 

should be in Portable Document Format 

(PDF) in accordance with the NRC 

mstockstill on DSK4VPTVN1PROD with NOTICES

10000 Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 

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 EFiling 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 

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’s PDR 

Reference staff at 1–(800) 397–4209, 

(301) 415–4737, or by email to 

pdr.resource@nrc.gov. 

Southern Nuclear Operating Company, 

Inc., Docket Nos. 50–348 and 50–364, 

Joseph M. Farley Nuclear Plant, Units 1 

and 2, Houston County, Alabama 

Date of amendment request: January 

12, 2012. 

Description of amendment request: 

The proposed amendments would 

extend the Reactor Coolant Pump (RCP) 

motor flywheel examination frequency 

from the currently approved 10-year 

examination frequency to an interval 

not to exceed 20 years. The changes are 

consistent with the Industry/Technical 

Specification Task Force (TSTF) 

Standard Technical Specification 

Change Traveler, TSTF–421–A, 

‘‘Revision to RCP Flywheel Inspection 

Program (WCAP–15666).’’ The 

availability of this TS improvement was 

announced in the Federal Register on 

October 22, 2003 (68 FR 60422), as part 

of the Consolidated Line Item 

Improvement Process (CLlIP). 

The NRC staff issued a notice of 

availability of a model safety evaluation 

and model no significant hazards 

consideration (NSHC) determination for 

referencing in license amendment 

applications in the Federal Register on 

June 24, 2003 (68 FR 37590). The 

licensee affirmed the applicability of the 

model NSHC determination in its 

application dated May 21, 2004. 

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—The Proposed Change Does Not 

Involve a Significant Increase in the 

Probability or Consequences of an Accident 

Previously Evaluated 

The proposed change to the RCP flywheel 

examination frequency does not change the 

response of the plant to any accidents. The 

RCP will remain highly reliable and the 

proposed change will not result in a 

significant increase in the risk of plant 

operation. Given the extremely low failure 

probabilities for the RCP motor flywheel 

during normal and accident conditions, the 

extremely low probability of a loss-of-coolant 

accident (LOCA) with loss of offsite power 

(LOOP), and assuming a conditional core 

damage probability (CCDP) of 1.0 (complete 

failure of safety systems), the core damage 

frequency (CDF) and change in risk would 

still not exceed the NRC’s acceptance 

guidelines contained in Regulatory Guide 

(RG) 1.174 (<1.0E–6 per year). Moreover, 

considering the uncertainties involved in this 

evaluation, the risk associated with the 

postulated failure of an RCP motor flywheel 

is significantly low. Even if all four RCP 

motor flywheels are considered in the 

bounding plant configuration case, the risk is 

still acceptably low. 

The proposed change does not adversely 

affect accident initiators or precursors, nor 

alter the design assumptions, conditions, or 

configuration of the facility, or the manner in 

which the plant is operated and maintained; 

alter or prevent the ability of structures, 

systems, and components (SSCs) from 

performing their intended function to 

mitigate the consequences of an initiating 

event within the assumed acceptance limits; 

or affect the source term, containment 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 10001 

isolation, or radiological release assumptions 

used in evaluating the radiological 

consequences of an accident previously 

evaluated. Further, the proposed change does 

not increase the type or amount of 

radioactive effluent that may be released 

offsite, nor significantly increase individual 

or cumulative occupational/public radiation 

exposure. The proposed change is consistent 

with the safety analysis assumptions and 

resultant consequences. 

Therefore, the proposed change does not 

involve a significant increase in the 

probability or consequences of an accident 

previously evaluated. 

Criterion 2—The Proposed Change Does Not 

Create the Possibility of a New or Different 

Kind of Accident From Any Accident 

Previously Evaluated 

The proposed change in flywheel 

inspection frequency does not involve any 

change in the design or operation of the RCP. 

Nor does the change to examination 

frequency affect any existing accident 

scenarios, or create any new or different 

accident scenarios. Further, the change does 

not involve a physical alteration of the plant 

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

will be installed) or alter the methods 

governing normal plant operation. In 

addition, the change does not impose any 

new or different requirements or eliminate 

any existing requirements, and does not alter 

any assumptions made in the safety analysis. 

The proposed change is consistent with the 

safety analysis assumptions and current plant 

operating practice. 

Therefore, the proposed change does not 

create the possibility of a new or different 

kind of accident from any accident 

previously evaluated. 

Criterion 3—The Proposed Change Does Not 

Involve a Significant Reduction in a Margin 

of Safety 

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 impacted by this 

change. The proposed change will not result 

in plant operation in a configuration outside 

of the design basis. The calculated impact on 

risk is insignificant and meets the acceptance 

criteria contained in RG 1.174. There are no 

significant mechanisms for inservice 

degradation of the RCP flywheel. 

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. 

Attorney for licensee: M. Stanford 

Blanton, Esq., Balch and Bingham, Post 

Office Box 306, 1710 Sixth Avenue 

North, Birmingham, Alabama 35201. 

NRC Branch Chief: Nancy Salgado. 

Virginia Electric and Power Company, 

Docket Nos. 50–280 and 50–281, Surry 

Power Station, Units 1 and 2, Surry 

County, Virginia and 50–338 and 50– 

339, North Anna Power Station Units 1 

and 2, Mineral, Virginia 

Date of amendment request: October 

6, 2011. 

Description of amendment request: To 

change the Emergency Action Levels 

(EALs) for North Anna Power Station 

(NAPS) and Surry Power Station (SPS). 

Several changes are proposed to 

incorporate lessons learned from the 

safety related breaker fire that occurred 

at NAPS on April 22, 2009 (Ref. NRC 

Event Notification Report 45013). The 

proposed changes are briefly 

summarized as follows: (1) Revise the 

definition of ‘‘Affecting Safe Shutdown’’ 

in the EAL Technical Basis Documents 

to specifically describe how this applies 

to NAPS and SPS; (2) revise applicable 

Hazards EALs to incorporate the intent 

of the revised definition for ‘‘Affecting 

Safe Shutdown’’; in addition, the main 

dam is added to the Initiating Condition 

(IC) for HA1 for NAPS and the low level 

intake structure is added to the IC for 

HA1 for SPS; (3) changing the IC for 

HA2 and HA3 to replace ‘‘a safe 

shutdown area’’ with ‘‘any Table H–1 

Area’’; and (4) revise applicable System 

Malfunctions EAL to include a 

15-minute threshold for RCS leaks. 

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 change involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

These changes affect the North Anna and 

Surry Power Station Emergency Action 

Levels, but 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 

consequences 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 consequence 

of an accident previously evaluated. 

2. Does the proposed change create the 

possibility of a new or different kind of 

accident from any accident previously 

evaluated? 

Response: No. 

These changes affect the North Anna and 

Surry Power Station Emergency Action 

Levels, but 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 setpoints are being modified. No new 

failure modes are introduced by the proposed 

changes. The proposed amendment, does not 

introduce any accident initiators 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. 

3. Does the proposed change involve a 

significant reduction in a margin of safety? 

Response: No. 

These changes affect the North Anna and 

Surry Power Station Emergency Action 

Levels, but 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 in operation of the facility as 

discussed 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: Lillian M. 

Cuoco, Esq., Senior Counsel, Dominion 

Resources Services, Inc., 120 Tredegar 

St., RS–2, Richmond, VA 23219. 

NRC Branch Chief: Nancy 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 

mstockstill on DSK4VPTVN1PROD with NOTICES

10002 Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 

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 

electronically 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 NRC’s PDR 

Reference staff at 1–(800) 397–4209, 

(301) 415–4737 or by email to 

pdr.resource@nrc.gov. 

Entergy Nuclear Operations, Inc., 

Docket No. 50–255, Palisades Nuclear 

Plant, Van Buren County, Michigan 

Date of application for amendment: 

January 31, 2011, supplemented by 

letter dated October 11, 2011. 

Brief description of amendment: The 

amendment modifies the Spent Fuel 

Pool (SFP) storage requirements in PNP 

Technical Specifications (TS) Section 

3.7.16 by revising a limiting condition 

for operation (LCO) for Region I fuel and 

non-fissile bearing component storage 

and by inserting tables containing spent 

fuel minimum burn-up for Regions 1B, 

1C, 1D, and 1E; and also modifies the 

Region I fuel storage criticality 

requirements, and design features in TS 

section 4.3, by describing revised 

requirements for Regions 1B and 1E and 

adding requirements for new Regions 1C 

and 1D. 

Date of issuance: January 27, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days of issuance. 

Amendment No.: 246. 

Facility Operating License No. DPR– 

20: Amendment revised the Technical 

Specifications. 

Date of initial notice in Federal 

Register: May 10, 2011 (76 FR 27096). 

The supplemental letter contained 

clarifying information and did not 

change the initial 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 January 27, 

2012. 

No significant hazards consideration 

comments received: No. 

Nebraska Public Power District, Docket 

No. 50–298, Cooper Nuclear Station, 

Nemaha County, Nebraska 

Date of amendment request: January 

5, 2011, as supplemented by letters 

dated October 6 and 18, 2011. 

Brief description of amendment: The 

amendment revised Technical 

Specification (TS) 3.4.3, ‘‘Safety/Relief 

Valves (SRVs) and Safety Valves (SVs).’’ 

The original proposed TS changes 

would have revised the required 

number of SRVs required to be operable 

for overpressure protection and 

Anticipated Transient without Scram 

from eight to five. By letter dated 

October 6, 2011, the licensee revised its 

submittal by changing the proposed 

required number of SRVs to be operable 

from eight to seven. 

Date of issuance: January 31, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days of issuance. 

Amendment No.: 240. 

Renewed Facility Operating License 

No. DPR–46: Amendment revised the 

Facility Operating License and 

Technical Specifications. 

Date of initial notice in Federal 

Register: November 1, 2011 (76 FR 

67488). 

The supplemental letters dated 

October 6 and 18, 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 amendment is contained in a 

Safety Evaluation dated January 31, 

2012. 

No significant hazards consideration 

comments received: No. 

NextEra Energy Point Beach, LLC, 

Docket Nos. 50–266 and 50–301, Point 

Beach Nuclear Plant, Units 1 and 2, 

Town of Two Creeks, Manitowoc 

County, Wisconsin 

Date of application for amendments: 

March 23, 2011. 

Brief description of amendments: The 

amendments replace non-conservative 

values for five operating limits in the 

Technical Specifications with more 

conservative values that incorporate 

measurement uncertainty. Additionally, 

one of the operating limits will replace 

a tank volume expressed in cubic feet 

with a volume expressed in percent 

level to allow plant operators to directly 

verify the technical specification limit 

based on direct instrument readings. 

Date of issuance: January 30, 2012. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days. 

Amendment Nos.: 246 (Unit 1) and 

250 (Unit 2). 

Renewed Facility Operating License 

Nos. DPR–24 and DPR–27: Amendments 

revise the Renewed Facility Operating 

License and Technical Specifications. 

Date of initial notice in Federal 

Register: May 17, 2011 (76 FR 28475). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated January 30, 

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: July 14, 

2011, as supplemented November 11, 

2011. 

Description of amendment request: 

The amendment replaces the Technical 

Specification surveillance 4.6.2.1.d 10- 

year surveillance frequency for testing 

the containment spray nozzles with an 

event-based frequency. 

Date of issuance: January 30, 2012. 

Effective date: As of its date of 

issuance and shall be implemented 

within 90 days. 

Amendment No.: 128. 

Facility Operating License No. NPF– 

86: The amendment revised the TS and 

the License. 

Date of initial notice in Federal 

Register: September 6, 2011 (76 FR 

55130). 

The supplemental letter provided 

additional information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the U.S. Nuclear 

Regulatory Commission (NRC) staff’s 

original proposed no significant hazards 

consideration determination. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated January 30, 

2012. 

No significant hazards consideration 

comments received: No. 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 77, No. 34 / Tuesday, February 21, 2012 / Notices 10003 

PSEG Nuclear LLC, Docket No. 50–354, 

Hope Creek Generating Station, Salem 

County, New Jersey 

Date of application for amendment: 

February 28, 2011, as supplemented by 

letters dated August 29, and December 

16, 2011, and January 26, 2012. 

Brief description of amendments: The 

amendment modifies the Hope Creek 

Generating Station Technical 

Specifications (TSs) to revise the 

existing TS for the control room 

emergency filtration system and to add 

a new TS for the control room air 

conditioning system. The amendment is 

based, in part, on Nuclear Regulatory 

Commission-approved Technical 

Specification Task Force (TSTF) 

Standard TS Change Traveler TSTF– 

477, Revision 3, ‘‘Adding an Action 

Statement for Two Inoperable Control 

Room Air Conditioning Subsystems.’’ 

Date of issuance: February 8, 2012. 

Effective date: As of the date of 

issuance, to be implemented within 60 

days. 

Amendment No.: 191. 

Facility Operating License No. NPF– 

57: The amendment revised the TSs and 

the Facility Operating License. 

Date of initial notice in Federal 

Register: May 3, 2011 (76 FR 24929). 

The letters dated August 29, and 

December 16, 2011, and January 26, 

2012, provided clarifying information 

that did not change the initial proposed 

no significant hazards consideration 

determination or expand the 

application. 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated February 8, 

2012. 

No significant hazards consideration 

comments received: No. 

Yankee Atomic Electric Company, 

Docket No. 50–29, Yankee Nuclear 

Power Station, Franklin County, 

Massachusetts. 

Date of application for amendment: 

August 10, 2011. 

Brief Description of Amendment: The 

amendment revises License Condition 

C(3) ‘‘Physical Protection’’. It updates 

the title of the Physical Security Plan, 

from the ‘‘Yankee Nuclear Power 

Station Defueled Security Plan’’ 

Revision 0, dated October 13, 1992, and 

‘‘Yankee Defueled Security Training and 

Qualification Plan’’ Revision 0, dated 

October 13, 1992, to the ‘‘Physical 

Security Plan for Yankee Rowe 

Independent Spent Fuel Storage 

Installation.’’ 

Amendment No.: 159. 

Facility Operating License No. DPR–3. 

The amendment revised the Facility 

Operating License. 

Date of Initial Notice in Federal 

Register. October 4, 2011 (76 FR 

61398). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated January 24, 

2012. 

No Significant Hazards Consideration 

Comments Received: No. 

Dated at Rockville, Maryland, this 10th day 

of February 2012. 

For the Nuclear Regulatory Commission. 

Michele G. Evans, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2012–3822 Filed 2–17–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Meeting of the 

ACRS Subcommittee on Reliability and 

PRA; Notice of Meeting 

The ACRS Subcommittee on 

Reliability and PRA will hold a meeting 

on March 7, 2012, Room T–2B1, 11545 

Rockville Pike, Rockville, Maryland. 

The entire meeting will be open to 

public attendance. 

The agenda for the subject meeting 

shall be as follows: 

Wednesday, March 7, 2012—8:30 a.m. 

Until 5 p.m. 

The Subcommittee will be briefed on 

the progress made for the tabletop 

exercises as part of the response to the 

SRM on SECY 10–0121, Modifying the 

Risk-Informed Regulatory Guidance For 

New Reactors. The Subcommittee will 

hear presentations by and hold 

discussions with the NRC staff and 

other interested persons regarding this 

matter. The Subcommittee will gather 

information, analyze relevant issues and 

facts, and formulate proposed positions 

and actions, as appropriate, for 

deliberation by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), John Lai 

(Telephone 301–415–5107 or Email: 

John.Lai@nrc.gov) five days prior to the 

meeting, if possible, so that appropriate 

arrangements can be made. Thirty-five 

hard copies of each presentation or 

handout should be provided to the DFO 

thirty minutes before the meeting. In 

addition, one electronic copy of each 

presentation should be emailed to the 

DFO one day before the meeting. If an 

electronic copy cannot be provided 

within this timeframe, presenters 

should provide the DFO with a CD 

containing each presentation at least 

thirty minutes before the meeting. 

Electronic recordings will be permitted 

only during those portions of the 

meeting that are open to the public. 

Detailed procedures for the conduct of 

and participation in ACRS meetings 

were published in the Federal Register 

on October 17, 2011, (76 FR 64126– 

64127). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

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

-rm/doc-collections/acrs. Information 

regarding topics to be discussed, 

changes to the agenda, whether the 

meeting has been canceled or 

rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in a major 

inconvenience. 

If attending this meeting, please enter 

through the One White Flint North 

building, 11555 Rockville Pike, 

Rockville, MD. After registering with 

security, please contact Mr. Theron 

Brown (240–888–9835) to be escorted to 

the meeting room. 

Dated: February 14, 2012. 

Antonio Dias, 

Technical Advisor, Advisory Committee on 

Reactor Safeguards. 

[FR Doc. 2012–3953 Filed 2–17–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Sunshine Act Meeting 

AGENCY HOLDING THE MEETINGS: Nuclear 

Regulatory Commission, [NRC–2012– 

0002]. 

DATE: Week of February 20, 2012. 

PLACE: Commissioners’ Conference 

Room, 11555 Rockville Pike, Rockville, 

Maryland. 

STATUS: Public and Closed. 

Additional Items To Be Considered 

Week of February 20, 2012 

Wednesday, February 22, 2012 

8:55 a.m. Affirmation Session (Public 

Meeting) (Tentative). 

a. Entergy Nuclear Generation Co. and 

Entergy Nuclear Operations, Inc. 

(Pilgrim Nuclear Power Station), 

mstockstill on DSK4VPTVN1PROD with NOTICES