Federal Register / Vol. 74, No. 126 / Thursday, July 2, 2009 / Notices 31769 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0268] 

Notice of Availability of Interim Staff 

Guidance Documents for Spent Fuel 

Storage Casks 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of Availability. 

FOR FURTHER INFORMATION CONTACT: 

Matthew Gordon, 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– 

3331; fax number: (301) 492–3342; email: matthew.gordon@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The Nuclear Regulatory Commission 

(NRC) has prepared a draft Interim Staff 

Guidance (ISG) No. 23 document, 

entitled ‘‘Application of ASTM 

Standard Practice C1671–07 when 

performing technical reviews of spent 

fuel storage and transportation 

packaging licensing actions.’’ This draft 

ISG document would provide guidance 

to the NRC staff when reviewing 

licensee integrated safety analyses, 

license or Certificate of Compliance 

applications or amendment requests, or 

other related activities for dry cask 

storage systems under 10 CFR part 71 

and 10 CFR part 72. The NRC is 

soliciting public comments on this draft 

of ISG–23, which will be considered 

before the NRC issues any 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 Document 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 

matthew.gordon@nrc.gov. 

ADAMS document ADAMS 

accession No. 

Draft of Interim Staff Guidance-23.ML090771224 

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 ISG–23 should be directed 

to Matthew Gordon, 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 August 

17, 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– 

3331; fax number: (301) 492–3331; email: matthew.gordon@nrc.gov. 

Dated at Rockville, Maryland this 25th day 

of June 2009. 

For the U.S. Nuclear Regulatory 

Commission. 

Robert E. Einziger, 

Acting Chief, Structural Mechanics and 

Materials Branch, Division of Spent Fuel 

Storage and Transportation, Office of Nuclear 

Materials Safety and Safeguards. 

[FR Doc. E9–15622 Filed 7–1–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0269] 

Notice of Availability of Interim Staff 

Guidance Documents for Spent Fuel 

Storage Casks 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of availability. 

FOR FURTHER INFORMATION CONTACT: 

Matthew Gordon, 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– 

3331; fax number: (301) 492–3342; email: matthew.gordon@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The Nuclear Regulatory Commission 

(NRC) has prepared a draft Interim Staff 

Guidance (ISG) No. 2, Revision 1, 

document, entitled ‘‘Division of Spent 

Fuel Storage and Transportation, 

Interim Staff Guidance—2, Revision 1, 

Fuel Retrievability.’’ This draft ISG 

document would provide guidance to 

the NRC staff when reviewing licensee 

integrated safety analyses, license 

applications or amendment requests, or 

other related licensing activities for dry 

cask storage systems under 10 CFR part 

72. The NRC is soliciting public 

comments on this draft of ISG–2, 

Revision 1, which will be considered 

before the NRC issues any 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 Document 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 pdr.resource@nrc.gov. 

ADAMS document ADAMS 

accession No. 

Draft of Interim Staff Guidance-2, Revision 1 ............ ML090771169 

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 ISG–2, Revision 1, should 

be directed to Matthew Gordon, 

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 August 

17, 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– 

3331; fax number: (301) 492–3331; email: matthew.gordon@nrc.gov. 

31770 Federal Register / Vol. 74, No. 126 / Thursday, July 2, 2009 / Notices 

Dated at Rockville, Maryland this 25th day 

of June 2009. 

For the U.S. Nuclear Regulatory 

Commission. 

Robert E. Einziger, 

Acting Chief, Structural Mechanics and 

Materials Branch, Division of Spent Fuel 

Storage and Transportation, Office of Nuclear 

Materials Safety and Safeguards. 

[FR Doc. E9–15620 Filed 7–1–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0272; Docket No. 03003754] 

Notice of Availability of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment to Materials License No. 

06–00217–06, for Remediation of 

Portions of a Site in Windsor, CT 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Issuance of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment. 

FOR FURTHER INFORMATION CONTACT: 

James Schmidt, (610) 337–5276; or John 

Nicholson, (610) 337–5236; Health 

Physicist, Decommissioning Branch, 

Division of Nuclear Materials Safety, 

Region I, 475 Allendale Road, King of 

Prussia, Pennsylvania 19406; fax 

number (610) 337–5269; or by e-mail: 

jim.schmidt@nrc.gov; 

john.nicholson@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is considering the 

issuance of a license amendment to 

Materials License No. 06–00217–06 

issued to ABB Inc. (ABB or the 

Licensee). ABB submitted the 

amendment request by letter dated 

December 31, 2008. The proposed 

action would authorize ABB to conduct 

remediation in place of the U.S. Army 

Corps of Engineers (USACE), at portions 

of the ABB site designated as Formally 

Utilized Sites Remedial Action Program 

(FUSRAP) areas. The ABB site, a 612- 

acre parcel located at 2000 Day Hill 

Road, in Windsor, Connecticut (the 

Facility), is currently undergoing sitewide decommissioning. The Facility’s 

FUSRAP areas will be cleaned up by the 

Licensee with NRC oversight, in 

accordance with an agreement between 

the NRC and USACE dated August 15, 

2007. Under this agreement, USACE 

will suspend its FUSRAP activities at 

the Facility after the Licensee modifies 

its previously-approved site 

decommissioning plan (DP) by bringing 

within its scope cleanup of the FUSRAP 

areas. To accomplish this, the Licensee 

submitted a revised DP for NRC review 

and approval as part of its December 31, 

2008, application. 

The NRC has prepared an 

Environmental Assessment (EA) in 

support of this proposed action in 

accordance with the requirements of 

Title 10, Code of Federal Regulations 

(CFR), Part 51 (10 CFR Part 51). Based 

on the EA, the NRC has concluded that 

a Finding of No Significant Impact 

(FONSI) is appropriate with respect to 

the proposed action. The amendment 

will be issued to the Licensee following 

the publication of this FONSI and EA in 

the Federal Register. 

II. Environmental Assessment 

Identification of Proposed Action 

The proposed action would approve 

the Licensee’s December 31, 2008, 

license amendment request. The scope 

of the DP (initially approved on June 1, 

2004) will be expanded to authorize 

ABB to conduct remediation activities 

for select FUSRAP areas at its Facility. 

Changes in the revised DP were 

generally limited to an update to reflect 

the successful remediation of the nonFUSRAP Facility areas, and a 

description of the remaining Facility 

areas to be remediated. However, the 

revised DP does include new derived 

concentration guideline levels (DCGLs) 

for uranium and cobalt-60, to be used 

for one structure: The south portion of 

Building 3, that will remain in place 

following completion of the remediation 

activities. Areas to be remediated under 

the revised DP include all FUSRAP 

areas except the Debris Pile area and 

Site Brook area. These areas are located 

in wetlands and will be the subject of 

a future DP amendment. The specific 

FUSRAP areas to be remediated 

included the removal of part of the five 

acre Building 3 Complex; removal of the 

one acre Building 6 Complex; removal 

of the industrial, waste, and sanitary 

lines associated with the Building 

Complexes; excavation of the seven acre 

Woods Area; and excavation of the one 

acre Drum Burial Pit area. Additionally, 

the revised DP provided for the 

Licensee’s remediation of a two acre 

area termed the Burning Grounds which 

is contaminated with small quantities of 

radium-226 and thorium-232. This area 

was previously remediated to existing 

NRC standards and approved for 

unrestricted use by the NRC on August 

10, 1989. 

Need for the Proposed Action 

The proposed action would allow 

ABB to complete the remaining Facility 

remediation and decommissioning 

activities, thereby reducing residual 

radioactivity at the Facility to a level 

that permits release of the entire 

property for unrestricted use and 

termination of the license. The Licensee 

has been successfully remediating and 

decommissioning the Facility since 

2004 under the previously-approved DP. 

In order to complete remediation of the 

entire Facility, the FUSRAP areas must 

be remediated. NRC is fulfilling its 

responsibilities under the Atomic 

Energy Act to make a decision on a 

proposed license amendment for 

decommissioning that ensures safety 

and protection of the public and the 

environment. 

Environmental Impacts of the Proposed 

Action 

In preparing this EA, the NRC staff 

reviewed the 2004 EA issued in 

connection with the initial DP; the 

Licensee’s Environmental Report 

submitted on February 28, 2008; and the 

revised DP submitted on December 31, 

2008. Additionally, the staff reviewed 

the performance of the 

decommissioning activities completed 

by the Licensee to date. The staff 

concluded that the bases for the findings 

of the 2004 EA remain valid, and are 

applicable to the revised DP. Regarding 

remediation of the FUSRAP areas, 

decommissioning methodologies are 

unchanged from the initial approved DP 

and are appropriate for the contaminant 

concentrations found in the FUSRAP 

area structures and soils. The same 

isotopes that were present in the 

Facility’s non-FUSRAP areas (namely, 

those associated with enriched uranium 

and cobalt-60) exist in the FUSRAP 

areas as well. The FUSRAP buildings 

and areas requiring remediation are 

similar to those already successfully 

remediated and decommissioned at the 

Facility. The amount of waste in 

FUSRAP areas which will need to be 

packaged and shipped to a licensed 

disposal facility is similar to the 

amounts evaluated in the 2004 EA, and 

this waste will be packaged and 

transported to the same disposal facility 

previously used for non-FUSRAP area 

remediation activities. 

As stated above, the revised DP 

includes a new site specific building 

DCGL, to support the unrestricted 

release of the southern portion, or High 

Bay, of Building 3. The staff’s technical 

review confirmed that the licensee’s 

requested site specific total uranium 

and cobalt-60 building DCGLs of 20,148,