Federal Register / Vol. 74, No. 192 / Tuesday, October 6, 2009 / Notices 51339 

on September 11 and 12, 2009. The 

notice provided an opportunity to 

submit comments on the NRC staff’s 

proposed NSHC determination. 

The supplemental letter dated 

September 8, 2009, provided additional 

information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the NRC staff’s 

original proposed no significant hazards 

consideration determination as 

published in The Tribune. 

The Commission’s related evaluation 

of the amendment, finding of exigent 

circumstances, consideration of public 

comments, state consultation, and final 

NSHC determination are contained in a 

safety evaluation dated September 17, 

2009. 

Attorney for licensee: Jennifer Post, 

Esq., Pacific Gas and Electric Company, 

P.O. Box 7442, San Francisco, California 

94120. 

NRC Branch Chief: Michael T. 

Markley. 

Dated at Rockville, Maryland, this 25th day 

of September 2009. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. E9–23780 Filed 10–5–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2008–0361] 

Notice of Availability for Comment of 

Draft Standard Review Plan for 

Renewal of Independent Spent Fuel 

Storage Installation Licenses and Dry 

Cask Storage System Certificates of 

Compliance 

AGENCY: U.S. Nuclear Regulatory 

Commission. 

ACTION: Notice of availability and 

opportunity to provide comments. 

DATES: Comments must be provided by 

December 21, 2009. 

FOR FURTHER INFORMATION CONTACT: Ata 

Istar, Structural Mechanics and 

Materials Branch, Division of Spent 

Fuel Storage and Transportation 

Division, Office of Nuclear Material 

Safety and Safeguards, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20005–0001. Telephone: (301) 492– 

3409; fax number: (301) 492–3342; 

e-mail: ata.istar@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The Nuclear Regulatory Commission 

(NRC) has prepared a draft Standard 

Review Plan (SRP) NUREG–1927, 

entitled ‘‘Standard Review Plan for 

Renewal of Independent Spent Fuel 

Storage Installation Licenses and Dry 

Cask Storage System Certificate of 

Compliance.’’ This draft SRP would 

provide guidance to the NRC staff when 

reviewing Safety Analyses Reports 

submitted by applicants for renewals of 

specific Independent Spent Fuel Storage 

Installation licenses or dry cask storage 

system certificates of compliance under 

10 CFR part 72. This draft SRP is related 

to the proposed rule published in the 

Federal Register on September 15, 2009 

(74 FR 47126). The NRC is soliciting 

public comments on this draft SRP, 

which will be considered before the 

NRC issues the final version. 

II. Further Information 

Documents related to this action are 

available electronically at the NRC’s 

Electronic Reading Room at http:// 

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

From this site, you can access the NRC’s 

Agencywide Documents Access and 

Management System (ADAMS), which 

provides text and image files of NRC’s 

public documents. The ADAMS 

accession numbers for the documents 

related to this notice are provided in the 

following table. If you do not have 

access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC 

Public Document Room (PDR) reference 

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

or by e-mail to ata.istar@nrc.gov. 

Interim staff guidance 

documents 

ADAMS accession 

No. 

Draft of SRP 

NUREG–1927.

ML092510340. 

These documents may also be viewed 

electronically on the public computers 

located at the NRC’s PDR, O–1 F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, MD 20852. The PDR 

reproduction contractor will copy 

documents for a fee. Comments and 

questions on this draft SRP should be 

directed to Ata Istar, Structural 

Mechanics and Materials Branch, 

Division of Spent Fuel Storage and 

Transportation, Office of Nuclear 

Materials Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20005–0001 by 

December 21, 2009. Comments received 

after this date will be considered if it is 

practical to do so, but assurance of 

consideration cannot be given to 

comments received after this date. 

Comments can also be submitted by 

telephone, fax, or e-mail to the 

following: Telephone: (301) 492–3409; 

fax number: (301) 492–3342; e-mail: 

ata.istar@nrc.gov. 

Dated at Rockville, Maryland, this 29th day 

of September 2009. 

For the U.S. Nuclear Regulatory 

Commission. 

Christopher M. Regan, 

Chief, Structural Mechanics and Materials 

Branch, Division of Spent Fuel Storage and 

Transportation, Office of Nuclear Material 

Safety and Safeguards. 

[FR Doc. E9–24051 Filed 10–5–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–361 and 50–362; NRC– 

2009–0439] 

Southern California Edison Company; 

San Onofre Nuclear Generating 

Station, Unit 2 and Unit 3; 

Environmental Assessment and 

Finding of No Significant Impact 

The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of a temporary exemption from 

Title 10 of the Code of Federal 

Regulations (10 CFR) Part 50, Section 

50.46 and 10 CFR 50, Appendix K, for 

Facility Operating License Nos. NPF–10 

and NPF–15, issued to Southern 

California Edison Company (SCE, the 

licensee), for operation of the San 

Onofre Nuclear Generating Station 

(SONGS), Unit 2 and Unit 3, 

respectively, located in San Diego 

County, California. Therefore, as 

required by 10 CFR 51.21, the NRC is 

issuing this environmental assessment 

and finding of no significant impact. 

Environmental Assessment 

Identification of the Proposed Action 

The requirements in 10 CFR 50.46 

specifically, and 10 CFR 50, Appendix 

K implicitly, refer to the use of Zircaloy 

or ZIRLO cladding. Therefore, a 

temporary exemption is required to use 

fuel rods clad with an advanced 

zirconium-based alloy that is not either 

Zircaloy or ZIRLO. Unlike the current 

fuel assemblies, the lead fuel assemblies 

(LFAs) manufactured by AREVA NP 

will contain M5 alloy cladding material. 

The licensee has requested a temporary 

exemption to allow the use of M5 alloy 

cladding. 

The temporary exemption would 

allow up to 16 LFAs manufactured by 

AREVA NP with M5 alloy cladding 

material to be inserted into the SONGS 

Unit 2 or Unit 3 reactor cores during the 


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