15814 Federal Register / Vol. 77, No. 52 / Friday, March 16, 2012 / Notices 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0065. 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. 

FOR FURTHER INFORMATION CONTACT: 

Frank Talbot, Division of Construction 

Inspection, and Operational Programs, 

Office of New Reactors, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone: 301–415– 

3146; email: Frank.Talbot@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Accessing Information and 

Submitting Comments 

A. Accessing Information 

Please refer to Docket ID NRC–2012– 

0065 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–2012–0065. 

• 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 draft 

regulatory guide is available 

electronically under ADAMS Accession 

Number ML113180379. The regulatory 

analysis may be found in ADAMS under 

Accession No. ML113180380. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

• 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– 

0065 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 

enters the comment submissions into 

ADAMS. 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. 

II. Further Information 

The NRC is issuing for public 

comment a draft guide in the NRC’s 

‘‘Regulatory Guide’’ series. This series 

was developed to describe and make 

available to the public such information 

as methods that are acceptable to the 

NRC staff for implementing specific 

parts of the NRC’s regulations, 

techniques that the staff uses in 

evaluating specific problems or 

postulated accidents, and data that the 

staff needs in its review of applications 

for permits and licenses. 

The draft regulatory guide, entitled, 

‘‘Preoperational Testing of Instrument 

and Control Air Systems,’’ is 

temporarily identified by its task 

number, DG–1268. The DG–1268 is 

proposed revision 2 of Regulatory Guide 

1.68.3, dated January 1977. 

This guide describes methods and 

procedures the staff of the NRC 

considers acceptable to implement 

preoperational testing of the instrument 

and control air systems (ICAS) in a 

commercial nuclear power plant. 

Successful demonstration of the 

operability of the ICAS is one of the 

items required by Appendix A, ‘‘General 

Design Criteria for Nuclear Power 

Plants,’’ of Title 10 of the Code of 

Federal Regulations, part 50, ‘‘Domestic 

Licensing of Production and Utilization 

Facilities’’ (10 CFR part 50). This guide 

also describes the methods that the NRC 

staff finds acceptable for the initial test 

program for ICAS systems, structures, 

and components (SSCs) in accordance 

with the regulations in 10 CFR Part 52, 

‘‘Licenses, Certifications, and Approvals 

for Nuclear Power Plants,’’ Subpart B, 

‘‘Standard Design Certifications,’’ and 

Subpart C, ‘‘Combined Licenses.’’ 

For the Nuclear Regulatory Commission. 

Dated at Rockville, Maryland, this 8th day 

of March, 2012. 

Thomas H. Boyce, 

Chief, Regulatory Guide Development Branch, 

Division of Engineering, Office of Nuclear 

Regulatory Research. 

[FR Doc. 2012–6413 Filed 3–15–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–388; NRC–2012–0063] 

PPL Susquehanna, LLC; Application 

and Amendment to Facility Operating 

License Involving: Proposed No 

Significant Hazards Consideration 

Determination 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: License amendment request, 

opportunity to comment, request a 

hearing and petition for leave to 

intervene. 

DATES: Comments must be filed by April 

16, 2012. A request for a hearing must 

be filed by May 15, 2012. 

ADDRESSES: You may access information 

and comment submissions related to 

this document by searching on http:// 

www.regulations.gov under Docket ID 

NRC–2012–0063. 

You may submit comments by the 

following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0063. 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. 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 77, No. 52 / Friday, March 16, 2012 / Notices 15815 

FOR FURTHER INFORMATION CONTACT: 

Bhalchandra K. Vaidya, Project 

Manager, Plant Licensing Branch I–1, 

Division of Operating Reactor Licensing, 

Office of Nuclear Reactor Regulation, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555. Telephone: 

301–415–3308; fax number: 301–415– 

2102; email: 

bhalchandra.vaidya@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Accessing Information and 

Submitting Comments 

A. Accessing Information 

Please refer to Docket ID NRC–2012– 

0063 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–2012–0063. 

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/reading-rm/ 

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 

application for amendment, dated 

March 8, 2012, is available 

electronically under ADAMS Accession 

No. ML12069A176. 

• 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– 

0063 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. 

II. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC or the Commission) 

is considering issuance of an 

amendment to Facility Operating 

License No. NPF–22, issued to PPL 

Susquehanna, LLC (the licensee), for 

operation of the Susquehanna Steam 

Electric Station, Unit 2 located in 

Luzerne County, Pennsylvania. 

The proposed amendment would 

allow a temporary extension of 24 hours 

to the Completion Time for Condition C 

in the Susquehanna Steam Electric 

Station (SSES) Unit 2 Technical 

Specification (TS) 3.8.7, ‘‘Distribution 

Systems—Operating,’’ to allow a Unit 1 

4160 V subsystem to be de-energized 

and removed from service for 96 hours 

to perform modifications on the bus. It 

also proposes a temporary extension of 

24 hours to the Completion Time for 

Condition A in SSES Unit 2 TS 3.7.1, 

‘‘Plant Systems—RHRSW [residual heat 

removal service water system] and UHS 

[ultimate heat sink],’’ to allow the UHS 

spray array and spray array bypass 

valves associated with applicable 

division RHRSW, and in Condition B, 

the applicable division Unit 2 RHRSW 

subsystem, to be inoperable for 96 hours 

during the Unit 1 4160 V bus breaker 

control logic modifications. 

Before issuance of the proposed 

license amendment, the Commission 

will have made findings required by the 

Atomic Energy Act of 1954, as amended 

(the Act), and the Commission’s 

regulations. 

The Commission has made a 

proposed determination that the 

amendment request involves 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. 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: 

This ‘‘No Significant Hazards 

Consideration’’ evaluates the following 

changes to the Technical Specifications: 

a. The Unit 2 TS 3.8.7, Condition C, 

Completion Time is revised to extend the 

Completion Time from 72 hours to 96 hours 

for a Unit 1 4160 V subsystem that is deenergized and removed from service. 

b. The Unit 2 TS 3.7.1, Condition A, 

Completion Time is revised to extend the 

Completion Time from 72 hours to 96 hours 

for a loop of UHS spray array and spray array 

bypass valves being inoperable due to the 

Unit 1 4160 V subsystem completion time 

being extended. 

c. The Unit 2 TS 3.7.1, Condition B, 

Completion Time is revised to extend the 

Completion Time from 72 hours to 96 hours 

for one Unit 2 RHRSW subsystem being 

inoperable due to the Unit 1 4160 V 

subsystem completion time being extended. 

1. Do the proposed changes involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

The temporary changes to the completion 

times for TS 3.8.7, Condition C and TS 3.7.1, 

Conditions A and B are necessary to 

implement plant changes which modify the 

4 kV Control Circuits on the 4.16 kV ESS 

[electronic switching system] Buses in order 

to mitigate the consequences of multiple fireinduced spurious operations. These 

modifications decrease the probability that a 

fire-induced hot short will cause equipment 

malfunctions. The current assumptions in the 

safety analysis regarding accident initiators 

and mitigation of accidents are unaffected by 

these changes. No SSC [structure, system, 

and component] failure modes or 

mechanisms are being introduced, and the 

likelihood of previously analyzed failures 

remains unchanged. 

The Completion Time to restore the Unit 

2 RHRSW subsystem has been extended to 96 

hours in order to complete the modifications 

associated with the Multiple Fire-Induced 

Spurious Operations issue. This is a 

temporary extension of the Completion Time. 

The extended Completion Times for TS 3.7.1 

Conditions A and B are only applicable when 

either the 1A 201 4.16 kV ESS Bus or the 1A 

202 4.16 kV ESS Bus is out of service in order 

to implement modifications associated with 

the Multiple Fire-Induced Spurious 

Operations issue. The affected Unit 2 

RHRSW subsystem remains functional, while 

the other subsystem of Unit 2 RHRSW will 

remain operable. 

There are no changes to any accident 

initiators or to the mitigating capability of 

safety-related equipment supported by the 

Class 1E Electrical AC system. The protection 

provided by these safety-related systems will 

continue to be provided as assumed by the 

safety analysis. 

Therefore, this proposed change does not 

involve a significant increase in the 

probability or consequences of an accident 

previously evaluated. 

2. Do the proposed changes create the 

possibility of a new or different kind of 

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15816 Federal Register / Vol. 77, No. 52 / Friday, March 16, 2012 / Notices 

accident from any accident previously 

evaluated? 

Response: No. 

The proposed changes to Technical 

Specification 3.8.7 Condition C, and to 

Technical Specification 3.7.1 Condition A 

and Condition B involve the extension of 

completion time for a Unit 1 4.16 kV Bus to 

be out of service in order to modify the 

control circuits to mitigate the consequences 

of multiple fire-induced spurious operations, 

the completion time for the UHS spray array 

and spray array bypass valves to be 

inoperable and one Unit 2 RHRSW 

subsystem being inoperable. No new 

equipment is being introduced, and installed 

equipment is not being operated in a new or 

different manner. There are no setpoints, at 

which protective or mitigative actions are 

initiated, affected by this change. These 

changes do not alter the manner in which 

equipment operation is initiated, nor will the 

function demands on credited equipment be 

changed. No alterations in the procedures 

that ensure the plant remains within 

analyzed limits are being proposed, and no 

major changes are being made to the 

procedures relied upon to respond to an offnormal event as described in the FSAR [final 

safety analysis report]. As such, no new 

failure modes are being introduced. The 

proposed change does not alter assumptions 

made in the safety analysis and licensing 

basis. 

Therefore, the proposed change does not 

create the possibility of a new or different 

kind of accident from any previously 

evaluated. 

3. Do the proposed changes involve a 

significant reduction in a margin of safety? 

Response: No. 

The margin of safety is established through 

equipment design, operating parameters, and 

the setpoints at which automatic actions are 

initiated. The proposed changes are 

acceptable because the completion time 

extensions allow modifications to the 4.16 kV 

control circuits to mitigate the consequences 

of a fire-induced short damaging equipment. 

Therefore, the plant response to analyzed 

events is affected by this modification in that 

the plant will better cope with the fireinduced shorts and will continue to provide 

the margin of safety assumed by the safety 

analysis. 

With the RHRSW Spray Pond Return 

Bypass Valves on the out of service loop 

electrically de-powered in the open position, 

a return flow path will be established. Since 

the RHRSW Pumps on Unit 2 are not 

impacted by the Unit 1—4.16 kV ESS Bus 

outages, with this return flow path 

established, the affected RHRSW Loop on 

Unit 2 will be functional. Also in this 

configuration a fire-induced circuit failures 

will not be able to affect the position of the 

valves. This configuration will continue to 

provide the margin of safety assumed by the 

safety analysis. 

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. 

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. 

III. Opportunity To Request a Hearing; 

Petition for Leave To Intervene 

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 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 

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 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. 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 77, No. 52 / Friday, March 16, 2012 / Notices 15817 

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. 

IV. Electronic Submissions (E-Filing) 

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 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 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’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 NRC guidance 

available on the NRC public Web site at 

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

complete at the time the documents are 

submitted through the NRC’s E-Filing 

system. To be timely, an electronic 

filing must be submitted to the E-Filing 

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

Time on the due date. Upon receipt of 

a transmission, the E-Filing system 

time-stamps the document and sends 

the submitter an 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 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 NRC’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/e-submittals.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 firstclass mail as of the time of deposit in 

the mail, or by courier, express mail, or 

expedited delivery service upon 

depositing the document with the 

provider of the service. A presiding 

officer, having granted an exemption 

request from using E-Filing, may require 

a participant or party to use E-Filing if 

the presiding officer subsequently 

determines that the reason for granting 

the exemption from use of E-Filing no 

longer exists. 

Documents submitted in adjudicatory 

proceedings will appear in NRC’s 

electronic hearing docket which is 

available to the public at http:// 

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 

mstockstill on DSK4VPTVN1PROD with NOTICES

15818 Federal Register / Vol. 77, No. 52 / Friday, March 16, 2012 / Notices 

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 dated March 

8, 2012, which is available for public 

inspection at the Commission’s PDR, 

located at One White Flint North, File 

Public Area 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 by telephone at 1–800– 

397–4209, 301–415–4737, or by email to 

pdr.resource@nrc.gov. 

Attorney for licensee: Bryan A. 

Snapp, Esquire, Assoc. General Counsel, 

PPL Services Corporation, 2 North 

Ninth St., GENTW3, Allentown, PA 

18101–1179. 

For the Nuclear Regulatory Commission. 

Dated at Rockville, Maryland, this 9th day 

of March 2012. 

Bhalchandra Vaidya, 

Project Manager, Plant Licensing Branch I– 

1, Division of Operating Reactor Licensing, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2012–6407 Filed 3–15–12; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2011–0191] 

License Renewal Interim Staff 

Guidance LR–ISG–2011–05: Ongoing 

Review of Operating Experience 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Interim staff guidance; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing the final 

License Renewal Interim Staff Guidance 

(LR–ISG), LR–ISG–2011–05, ‘‘Ongoing 

Review of Operating Experience.’’ This 

LR–ISG provides guidance and 

clarification concerning ongoing 

reviews of plant-specific and industrywide operating experience as an 

attribute of aging management programs 

used at nuclear power plants as 

described in NUREG–1801, Revision 2, 

‘‘Generic Aging Lessons Learned (GALL) 

Report,’’ (Agencywide Documents 

Access and Management System 

(ADAMS) Accession No. 

ML103490041), and NUREG–1800, 

Revision 2, ‘‘Standard Review Plan for 

Review of License Renewal 

Applications for Nuclear Power Plants’’ 

(SRP–LR) (ADAMS Accession No. 

ML103490036). 

ADDRESSES: Please refer to Docket ID 

NRC–2011–0191 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–2011–0191. 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 publiclyavailable documents online in the NRC 

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

select ‘‘ADAMS Public Documentsz,’’ 

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 final LR–ISG–2011–05 is available 

under ADAMS Accession No. 

ML12044A215. 

• 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: LR–ISG documents are also 

available online under the ‘‘License 

Renewal’’ heading at http:// 

www.nrc.gov/reading-rm/doccollections/#int. 

FOR FURTHER INFORMATION CONTACT: Mr. 

Matthew Homiack, Division of License 

Renewal, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001; telephone: 301–415–1683; email: 

Matthew.Homiack@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

Background Information 

The NRC issues LR–ISG to 

communicate insights and lessons 

learned and to address emergent issues 

not covered in license renewal guidance 

documents. In this way, the NRC staff 

and stakeholders may use the guidance 

in an LR–ISG document until 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 developed LR–ISG– 

2011–05 to clarify guidance on how the 

ongoing review of operating experience 

should be used to ensure the 

effectiveness of the license renewal 

aging management programs used at 

nuclear power plants to meet the 

requirements of Title 10 of the Code of 

Federal Regulations (10 CFR) Part 54, 

‘‘Requirements for Renewal of Operating 

Licenses for Nuclear Power Plants.’’ The 

final LR–ISG–2011–05 revises the NRC 

staff’s recommended aging management 

programs in the GALL Report and the 

NRC staff’s aging management review 

procedures and acceptance criteria in 

the SRP–LR. 

On August 24, 2011 (76 FR 52995), 

the NRC requested public comments on 

draft LR–ISG–2011–05. By letter dated 

August 29, 2011 (ADAMS Accession 

No. ML11242A114), the Nuclear Energy 

Institute (NEI) requested a 30-day 

extension to the comment period and a 

public meeting to discuss draft 

comments and questions concerning 

implementation of the LR–ISG. The 

NRC staff granted the NEI’s requests, as 

noticed on September 20, 2011 (76 FR 

58311). The public meeting was held on 

October 12, 2011 (ADAMS Accession 

No. ML11304A259), and the comment 

period was extended until October 23, 

2011. 

During this time, the NRC staff 

identified the need to include additional 

guidance on areas where license 

renewal applicants should ensure their 

programmatic activities for operating 

experience reviews are appropriate for 

considering operating experience 

related to aging management. The NRC 

staff identified this need through its 

ongoing reviews of license renewal 

applications and through insights 

gained on how nuclear power plant 

licensees carry out their operating 

experience review activities. The 

additional guidance covers areas where 

enhancements may need to be made for 

license renewal, such as the specific 

kind of information that should be 

considered as operating experience, the 

training of plant personnel, information 

to consider in operating experience 

evaluations, criteria for identifying and 

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