69710 Federal Register / Vol. 75, No. 219 / Monday, November 15, 2010 / Notices 

Plants,’’ and related guidance 

documents. 

Disposition: On May 13, 2010, the 

NRC staff issued the proposed Revision 

0 on SRP Section 13.6.6 on ‘‘Cyber 

Security Plan,’’ ADAMS Accession No. 

ML093560837. There were comments 

received on the proposed guidance 

(ADAMS Accession No. ML101810249). 

These comments were incorporated as 

appropriate and the details of 

disposition of the stakeholder’s 

comments are available under ADAMS 

Accession No. ML102590155. 

ADDRESSES: The NRC maintains 

ADAMS, which provides text and image 

files of NRC’s public documents. These 

documents may be accessed through the 

NRC’s Public Electronic Reading Room 

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

reading-rm/adams.html. Persons who 

do not have access to ADAMS or who 

encounter problems in accessing the 

documents located in ADAMS should 

contact the NRC Public Document Room 

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

415–4737, or by e-mail at 

pdr.resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: Mr. 

William F. Burton, Chief, Rulemaking 

and Guidance Development Branch, 

Division of New Reactor Licensing, 

Office of New Reactors, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; telephone at 301–415– 

6332 or e-mail at 

william.burton@nrc.gov. 

SUPPLEMENTARY INFORMATION: The NRC 

posts its issued staff guidance on the 

NRC external Web page (http:// 

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

Dated at Rockville, Maryland, this 3rd day 

of November 2010. 

For the Nuclear Regulatory Commission. 

William F. Burton, 

Chief, Rulemaking and Guidance 

Development Branch, Division of New Reactor 

Licensing, Office of New Reactors. 

[FR Doc. 2010–28634 Filed 11–12–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–302; NRC–2010–0105] 

Florida Power Corporation, et al.; 

Crystal River Unit 3 Nuclear 

Generating Plant Environmental 

Assessment and Finding of No 

Significant Impact 

The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of an exemption, pursuant to 

Title 10 of the Code of Federal 

Regulations (10 CFR) Section 73.5, 

‘‘Specific exemptions,’’ from the 

implementation date for certain new 

requirements of 10 CFR part 73, 

‘‘Physical protection of plants and 

materials,’’ for Facility Operating 

License No. DPR 72 issued to Florida 

Power Corporation (the licensee), for 

operation of the Crystal River Unit 3 

Nuclear Generating Plant (CR–3), 

located in Citrus County, Florida. In 

accordance with 10 CFR 51.21, the NRC 

prepared an environmental assessment 

documenting its finding. The NRC 

concluded that the proposed actions 

will have no significant environmental 

impact. 

Environmental Assessment 

Identification of the Proposed Action 

The proposed action would exempt 

the licensee from the required 

implementation date of March 31, 2010, 

for four new requirements of 10 CFR 

part 73. Specifically, CR–3 would be 

granted a second exemption, further 

extending the date for full compliance 

with four new requirements contained 

in 10 CFR 73.55, from November 15 and 

December 15 (the dates specified in a 

prior exemption granted by NRC on 

March 25, 2010), until December 15, 

2011 and March 15, 2012, respectively. 

The licensee has proposed an alternate 

full compliance implementation date of 

March 15, 2012, which is approximately 

2 years beyond the compliance date 

required by 10 CFR part 73. The 

proposed action, an extension of the 

schedule for completion of certain 

actions required by the revised 10 CFR 

part 73, does not involve any physical 

changes to the reactor, fuel, plant 

structures, support structures, water, or 

land at the CR–3 site. 

The proposed action is in accordance 

with the licensee’s application dated 

September 8, 2010. 

The Need for the Proposed Action 

The proposed second scheduler 

exemption is needed to provide the 

licensee with additional time, beyond 

the previously approved by the NRC 

letter dated March 25, 2010, to 

implement four specific elements of the 

new requirements that involve 

significant physical upgrades to the CR– 

3 security system. The schedules used 

in the original scheduler exemption 

were based on the conceptual design 

information available to the licensee at 

the time of the submittal. At this time, 

the licensee has fully developed the 

design and has completed the discovery 

phase. Therefore, due to the unforeseen 

need for design changes necessary to 

achieve full compliance with the Final 

Rule, additional time is needed to 

complete the complex revised design 

and construction and associated 

analysis. 

Environmental Impacts of the Proposed 

Action 

The NRC has completed its 

environmental assessment of the 

proposed exemption. The NRC staff has 

concluded that the proposed action to 

further extend the implementation 

deadline for two items would not 

significantly affect plant safety and 

would not have a significant adverse 

effect on the probability of an accident 

occurring. 

The proposed action would not result 

in an increased radiological hazard 

beyond those hazards previously 

analyzed in the environmental 

assessment and finding of no significant 

impact made by the Commission in 

promulgating its revisions to 10 CFR 

part 73 as discussed in a Federal 

Register notice dated March 27, 2009; 

74 FR 13926. There will be no change 

to radioactive effluents that affect 

radiation exposures to plant workers 

and members of the public. Therefore, 

no changes or different types of 

radiological impacts are expected as a 

result of the proposed exemption. 

The proposed action does not result 

in changes to land use or water use, or 

result in changes to the quality or 

quantity of nonradiological effluents. No 

changes to the National Pollution 

Discharge Elimination System permit 

are needed. No effects on the aquatic or 

terrestrial habitat in the vicinity of the 

plant, or to threatened, endangered, or 

protected species under the Endangered 

Species Act, or impacts to essential fish 

habitat covered by the MagnusonStevens Act are expected. There are no 

impacts to the air or ambient air quality. 

There are no impacts to historical and 

cultural resources. There would be no 

impact to socioeconomic resources. 

Therefore, no changes to or different 

types of nonradiological environmental 

impacts are expected as a result of the 

proposed exemption. 

Accordingly, the NRC concludes that 

there are no significant environmental 

impacts associated with the proposed 

action. In addition, in promulgating its 

revisions to 10 CFR part 73, the 

Commission prepared an environmental 

assessment and published a finding of 

no significant impact [Part 73, Power 

Reactor Security Requirements, March 

27, 2009; 74 FR 13926]. 

With its request to extend the 

implementation deadline, the licensee 

currently maintains a security system 

acceptable to the NRC and that will 

continue to provide acceptable physical 


srobinson on DSKHWCL6B1PROD with NOTICES
Federal Register / Vol. 75, No. 219 / Monday, November 15, 2010 / Notices 69711 

protection of CR–3 in lieu of the new 

requirements in 10 CFR part 73. 

Therefore, the extension of the 

implementation date for four elements 

of the new requirements of 10 CFR part 

73 to December 15, 2011, and March 15, 

2012, would not have any significant 

environmental impacts. 

The NRC staff’s safety evaluation will 

be provided in the exemption that will 

be issued as part of the letter to the 

licensee approving the exemption to the 

regulation, if granted. 

Environmental Impacts of the 

Alternatives to the Proposed Action 

As an alternative to the proposed 

actions, the NRC staff considered denial 

of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the 

exemption request would result in no 

change in current environmental 

impacts. If the proposed action was 

denied, the licensee would have to 

comply with the existing 

implementation deadline for those 

specific items of November 15, and 

December 15, 2010, as extended by the 

exemption granted on March 25, 2010. 

The environmental impacts of the 

proposed exemption and the ‘‘no-action’’ 

alternative are similar. 

Alternative Use of Resources 

The action does not involve the use of 

any different resources than those 

previously considered in the Final 

Environmental Statement for CR–3, 

dated May 1973. 

Agencies and Persons Consulted 

In accordance with its stated policy, 

on November 4, 2010, the NRC staff 

consulted with the Florida State official, 

Mr. William A. Passeti of the Florida 

Department of Health, Bureau of 

Radiation Control regarding the 

environmental impact of the proposed 

action. The State official had no 

comments. 

Finding of No Significant Impact 

On the basis of the environmental 

assessment, the NRC concludes that the 

proposed action will not have a 

significant effect on the quality of the 

human environment. Accordingly, the 

NRC has determined not to prepare an 

environmental impact statement for the 

proposed action. 

For further details with respect to the 

proposed action, see the licensee’s letter 

dated September 8, 2010. Portions of the 

September 8, 2010, submittal contains 

security-related information and, 

accordingly, a redacted version of this 

letter is available for public review in 

the Agencywide Documents Access and 

Management System (ADAMS), 

Accession No. ML102530129. This 

document may be examined, and/or 

copied for a fee, at the NRC’s Public 

Document Room (PDR), located at One 

White Flint North, Public File Area O– 

1F21, 11555 Rockville Pike (first floor), 

Rockville, Maryland 20852. Publicly 

available records will be accessible 

electronically from the ADAMS Public 

Electronic Reading Room on the Internet 

at the NRC Web site: http:// 

www.nrc.gov/reading-rm/adams.html. 

Persons who do not have access to 

ADAMS or who encounter problems in 

accessing the documents located in 

ADAMS should contact the NRC PDR 

Reference staff by telephone at 1–800– 

397–4209 or 301–415–4737, or send an 

e-mail to pdr.resource@nrc.gov. 

Dated at Rockville, Maryland, on 

November 5, 2010. 

For the Nuclear Regulatory Commission. 

Christopher Gratton, 

Senior Project Manager, Plant Licensing 

Branch II–2, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2010–28633 Filed 11–12–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 52–012 and 52–013; NRC– 

2010–0343] 

STP Nuclear Operating Company, 

South Texas Project Nuclear Power 

Plant, Units 3 and 4; Exemption 

1.0 Background 

By letters dated February 2, 2010 

(Agency wide Documents Access and 

Management System (ADAMS) 

Accession Number ML100350219), 

March 23, 2010 (ADAMS Accession 

Number ML100880055) and July 21, 

2010 (ADAMS Accession Number 

ML102070274), STP Nuclear Operating 

Company (STPNOC) submitted a 

request for an exemption from Title 10 

of the Code of Federal Regulations (10 

CFR) part 50, section 50.10: License 

required; limited work authorization. 

The U.S. Nuclear Regulatory 

Commission (NRC or the NRC staff) has 

reviewed this request for exemption, 

pursuant to 10 CFR 50.12, as it relates 

to STPNOC’s application for combined 

licenses (COLs) for South Texas Project 

(STP) Units 3 and 4, which is currently 

under review by the NRC staff. This 

exemption would authorize STPNOC to 

install two crane foundation retaining 

walls (CFRWs) prior to issuance of the 

COLs. Granting this exemption would 

not constitute a commitment by the 

NRC to issue COLs for STP Units 3 and 

4. STPNOC would install the CFRWs 

assuming the risk that its COL 

application may later be denied. 

2.0 Request/Action 

The proposed action, as described in 

STPNOC’s request for an exemption to 

10 CFR 50.10, would allow STPNOC to 

install two CFRWs (one for Unit 3 and 

one for Unit 4), prior to issuance of 

COLs. According to STPNOC, the 

CFRWs are non-safety related, and have 

no adverse interactions with any 

structures, systems, or components as 

identified in 50.10. STPNOC states that 

the CFRWs are required to facilitate 

excavation activities by retaining soil 

next to the excavations of the Reactor 

Building, Control Building and Turbine 

Building Foundations, while allowing 

the crane areas to be at grade and near 

the buildings. Installation of the CFRWs 

would include the following activities: 

• Performing a full-depth and widthslurry excavation; 

• Placing of reinforcement in the 

slurry trench; 

• Displacing the slurry with concrete 

from the bottom up; and 

• Installing tiebacks and whalers to 

stabilize the CFRWs, as excavation for 

permanent plant structures proceeds. 

As construction of the permanent 

plant structures proceeds, the CFRWs 

would be abandoned in place following 

crane use. After abandonment, the 

CFRWs would have no function during 

operation of STP Units 3 and 4. 

In its exemption request, STPNOC 

stated that the proposed exemption is 

needed because installation of the 

CFRWs must occur before excavation for 

permanent plant structures, and 

compliance with the requirements for a 

limited work authorization as indicated 

in 10 CFR 50.10 would result in undue 

hardship or other costs that are 

significantly in excess of those 

contemplated during the development 

of 10 CFR 50.10. According to the 

exemption request, installation of the 

CFRWs is needed to allow STPNOC to 

complete certain on-site activities in 

parallel with the licensing process, so 

that it can begin construction promptly 

upon issuance of COLs. 

3.0 Discussion 

Pursuant to 10 CFR 50.12(a) the 

Commission may, upon application by 

any interested person or upon its own 

initiative, grant exemptions from the 

requirements of 10 CFR 50.10 when (1) 

the exemption authorized by law, will 

not present an undue risk to public 

health or safety, and are consistent with 

the common defense and security; and 

(2) when special circumstances are 

present. 


srobinson on DSKHWCL6B1PROD with NOTICES