78050 Federal Register / Vol. 69, No. 249 / Wednesday, December 29, 2004 / Notices 

Interlayers and Patterns in Polyimide 

Films.

Dated: December 10, 2004. 

Keith T. Sefton, 

Deputy General Counsel, Administration and 

Management.

[FR Doc. 04–28516 Filed 12–28–04; 8:45 am] 

BILLING CODE 7510–13–P

NATIONAL AERONAUTICS AND 

SPACE ADMINISTRATION 

[Notice 04–156] 

Government-Owned Inventions, 

Available for Licensing

AGENCY: National Aeronautics and 

Space Administration.

ACTION: Notice of availability of 

inventions for licensing. 

SUMMARY: The inventions listed below 

are assigned to the National Aeronautics 

and Space Administration, have been 

filed in the United States Patent and 

Trademark office, and are available for 

licensing.

DATES: December 29, 2004.

FOR FURTHER INFORMATION CONTACT: Jerry 

L. Seemann, Patent Counsel, Marshall 

Space Flight Center, Mail Code LS01, 

Huntsville, AL 35812; telephone (256) 

544–6580; fax (256) 544–0258. 

NASA Case No. MFS–31303–1–CO: 

Generalized Fluid System Simulation 

Program (GFSSP); 

NASA Case No. MFS–31529–1: Motor 

Controller System For Large Dynamic 

Range Of Motor Operation; 

NASA Case No. MFS–31595–1: Light 

Weight Precision Reflective Optics 

Manufacturing Process, Apparatus And 

Product Thereby; 

NASA Case No. MFS–31838–1: 

Pressure Vessel With Improved Impact 

Resistance And Method Of Making The 

Same; 

NASA Case No. MFS–31852–1: 

Achromatic Shearing Phase Sensor For 

Generating Images Indicative Of 

Measure(s) Of Alignment Between 

Segments Of A Segmented Telescope’s 

Mirrors; 

NASA Case No. MFS–32024–1: Fuel 

Tank For Liquefied Natural Gas; 

NASA Case No. MFS–31648–1: 

Counter-Rotating Shoulder Mechanism 

For Friction Stir Welding; 

NASA Case No. MFS–31823–1–DIV: 

Radio-Frequency Driven Dielectric 

Heaters For Non-Nuclear Testing In 

Nuclear Core Development; 

NASA Case No. MFS–31918–1: 

Friction Stir Weld Tools; 

NASA Case No. MFS–31924–1: 

Friction Stir Apparatus For Solid State 

Welding; 

NASA Case No. MFS–32105–1: 

Ultrasonic Stir Welding Process And 

Apparatus.

Dated: December 10, 2004. 

Keith T. Sefton, 

Deputy General Counsel, Administration and 

Management.

[FR Doc. 04–28517 Filed 12–28–04; 8:45 am] 

BILLING CODE 7510–13–P

NATIONAL AERONAUTICS AND 

SPACE ADMINISTRATION 

[Notice 04–157] 

Notice of Prospective Patent License

AGENCY: National Aeronautics and 

Space Administration.

ACTION: Notice of prospective patent 

license. 

SUMMARY: NASA hereby gives notice 

that Intaka Corporation, of Sunnyvale, 

California, has applied for a partially 

exclusive license to practice the 

invention, NASA case MFS–31549–1, 

‘‘Ultra Thin Substrate Integral Memory 

and Radio Frequency Identification 

Devices’’, U.S. patent application no. 

09/962,704 and assigned to the United 

States of America as represented by the 

Administrator of the National 

Aeronautics and Space Administration. 

Written objections to the prospective 

grant of a license should be sent to Mr. 

Jerry L. Seemann, Chief Patent Counsel/

LS01, Marshall Space Flight Center, 

Huntsville, AL 35812. NASA has not yet 

made a determination to grant the 

requested license and may deny the 

requested license even if no objections 

are submitted within the comment 

period.

DATES: Responses to this notice must be 

received by January 13, 2005.

FOR FURTHER INFORMATION CONTACT:

Sammy A. Nabors, Technology Transfer 

Department/CD30, Marshall Space 

Flight Center, Huntsville, AL 35812, 

(256) 544–5226.

Dated: December 8, 2004. 

Keith T. Sefton, 

Deputy General Counsel, Administration and 

Management.

[FR Doc. 04–28518 Filed 12–28–04; 8:45 am] 

BILLING CODE 7510–13–P

NUCLEAR REGULATORY 

COMMISSION 

Agency Information Collection 

Activities: Proposed Collection; 

Comment Request

AGENCY: Nuclear Regulatory 

Commission (NRC).

ACTION: Notice of pending NRC action to 

submit an information collection 

request to OMB and solicitation of 

public comment. 

SUMMARY: The NRC is preparing a 

submittal to OMB for review of 

continued approval of information 

collections under the provisions of the 

Paperwork Reduction Act of 1995 (44 

U.S.C. Chapter 35). 

Information pertaining to the 

requirement to be submitted: 

1. The title of the information 

collection: 10 CFR Part 73—Physical 

Protection of Plants and Materials. 

2. Current OMB Approval Number:

3150–0002. 

3. How often the collection is 

required: On occasion. Required reports 

are submitted and evaluated as events 

occur. 

4. Who is required or asked to report:

Persons who possess, use, import, 

export, transport, or deliver to a carrier 

for transport, special nuclear material. 

5. The number of annual respondents:

384. 

6. The number of hours needed 

annually to complete the requirement or 

request: 523,106 hours annually (50,207 

hours for reporting (0.64 hours per 

response) and 472,899 hours for 

recordkeeping (1,041 hours per 

recordkeeper)). 

7. Abstract: NRC regulations in 10 

CFR Part 73 prescribe requirements for 

establishment and maintenance of a 

physical protection system with 

capabilities for protection of special 

nuclear material at fixed sites and in 

transit and of plants in which special 

nuclear material is used. The 

information in the reports and records is 

used by the NRC staff to ensure that the 

health and safety of the public is 

protected and that licensee possession 

and use of special nuclear material is in 

compliance with license and regulatory 

requirements. 

Submit, by February 28, 2005, 

comments that address the following 

questions: 

1. Is the proposed collection of 

information necessary for the NRC to 

properly perform its functions? Does the 

information have practical utility? 

2. Is the burden estimate accurate? 

3. Is there a way to enhance the 

quality, utility, and clarity of the 

information to be collected? 

4. How can the burden of the 

information collection be minimized, 

including the use of automated 

collection techniques or other forms of 

information technology? 

A copy of the draft supporting 

statement may be viewed free of charge 

at the NRC Public Document Room, One

Federal Register / Vol. 69, No. 249 / Wednesday, December 29, 2004 / Notices 78051

White Flint North, 11555 Rockville 

Pike, Room O–1 F21, Rockville, MD 

20852. OMB clearance requests are 

available at the NRC worldwide Web 

site: http://www.nrc.gov/public-involve/

doc-comment/omb/index.html. The 

document will be available on the NRC 

home page site for 60 days after the 

signature date of this notice. 

Comments and questions about the 

information collection requirements 

may be directed to the NRC Clearance 

Officer, Brenda Jo. Shelton (T–5-F52), 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001, by 

telephone at 301–415–7233, or by 

Internet electronic mail to 

INFOCOLLECTS@NRC.GOV.

Dated at Rockville, Maryland, this 22nd 

day of December, 2004.

For the Nuclear Regulatory Commission. 

Brenda Jo. Shelton, 

NRC Clearance Officer, Office of the Chief 

Information Officer.

[FR Doc. 04–28453 Filed 12–28–04; 8:45 am] 

BILLING CODE 7590–01–P

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–461] 

Amergen Energy Company, LLC.; 

Notice of Consideration of Issuance of 

Amendment to Facility Operating 

License, Proposed No Significant 

Hazards Consideration Determination, 

and Opportunity for a Hearing 

The U.S. Nuclear Regulatory 

Commission (the Commission) is 

considering issuance of an amendment 

to Facility Operating License No. NPF–

62, issued to AmerGen Energy 

Company, LLC, for operation of the 

Clinton Power Station, Unit 1 (CPS) 

located in DeWitt County, Illinois. 

The proposed amendment would 

change Technical Specification (TS) 4.3, 

‘‘Fuel Storage,’’ to reflect the addition of 

fuel storage capacity in the fuel cask 

storage pool and increased fuel storage 

capacity in the spent fuel pool. 

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), Section 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; or (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:

1. Does the proposed amendment involve 

a significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

The proposed change involves revising 

CPS TS 4.3, ‘‘Fuel Storage,’’ to reflect the 

increased storage capacity of the spent fuel 

pool due to the installation of higher density 

storage racks and the addition of fuel storage 

capacity in the fuel cask storage pool. 

The method of handling fuel is not 

significantly changed since the same 

equipment and procedures will be used. 

During spent fuel rack removal and 

installation, all work in the spent fuel pool 

and cask storage pool area will be controlled 

and performed in strict accordance with 

specific written guidance. Any movement of 

fuel assemblies required to be performed to 

support the modification (e.g., removal and 

installation of racks) will be performed in the 

same manner as during normal refueling 

operations. Shipping cask movements will 

not be performed during the modification 

period. There is no change to the methods or 

equipment to be used in moving fuel casks. 

Expanding the spent fuel storage capacity 

does not have a significant impact on the 

frequency of occurrence for any accident 

previously evaluated. Therefore, this change 

will not significantly increase the probability 

of occurrence of any event previously 

analyzed. 

The consequences of the dropped spent 

fuel assembly in the spent fuel pool have 

been evaluated for the proposed change. The 

results show that the postulated drop of a 

spent fuel assembly striking the top of the 

spent fuel storage racks will not distort the 

racks sufficiently to impair their 

functionality. The minimum subcriticality 

margin (i.e., neutron multiplication factor 

(Keff) less than or equal to 0.95) will be 

maintained. The structural damage to the 

Fuel Building, spent fuel pool liner, and any 

fuel assembly resulting from a dropped fuel 

assembly striking the pool floor or another 

assembly located in the racks is primarily 

dependent on the mass of the falling object 

and drop height. Since these two parameters 

are not changed by the proposed 

modification, the postulated structural 

damage to these items remains unchanged. 

The radiological dose at the exclusion area 

boundary will not be increased since no 

changes are being made to in-core hold time 

or burn-up as a result of the proposed 

amendment. 

The consequences of a loss of spent fuel 

pool cooling were evaluated and found to not 

involve a significant increase as a result of 

the proposed changes. The concern with this 

event is a reduction of spent fuel pool water 

inventory from bulk boiling resulting in 

uncovering fuel assemblies. This situation 

could lead to fuel failure and subsequent 

significant increase in offsite dose. Loss of 

spent fuel pool cooling at CPS is mitigated 

by ensuring that a sufficient time lapse exists 

between the loss of forced cooling and 

uncovering fuel. This period of time is 

compared against a reasonable period to 

reestablish cooling or supply an alternative 

water source. Evaluation of this event 

includes determination of the time to boil. 

This time period is much less than the onset 

of any significant increase in offsite dose, 

since once boiling begins it would have to 

continue unchecked until the pool surface 

was lowered to the point of exposing active 

fuel. The time to boil represents the onset of 

loss of pool water inventory and is 

commonly used as a gage for establishing the 

comparison of consequences before and after 

a reracking project. The heatup rate in the 

spent fuel pool is a nearly linear function of 

the fuel decay heat load. The fuel decay heat 

load will increase subsequent to the 

proposed changes because of the increase in 

the number of assemblies. The thermalhydraulic analysis determined that the 

minimum time to boil is more than three 

hours subsequent to complete loss of forced 

cooling and a minimum of 24 hours between 

loss of forced cooling and a drop of water 

level to within 10 feet of the top of the racks. 

In the unlikely event that all pool cooling is 

lost, sufficient time will still be available 

subsequent to the proposed changes for the 

operators to provide alternate means of 

cooling before the water shielding above the 

top of the racks falls below 10 feet. The 

supporting analyses have been confirmed to 

be bounding for all spent fuel pool loading 

configurations. 

The consequences of a design basis seismic 

event are not increased. The consequences of 

this event were evaluated on the basis of 

subsequent fuel damage or compromise of 

the fuel storage or building configurations 

leading to radiological or criticality concerns. 

The new racks have been analyzed in their 

new configuration and were found to be safe 

during seismic motion. Fuel has been 

determined to remain intact and the storage 

racks maintain the fuel and fixed poison 

configurations subsequent to a seismic event. 

The structural capability of the pool and liner 

will not be exceeded under the appropriate 

combinations of dead weight, thermal, and 

seismic loads. The Fuel Building structure 

will remain intact during a seismic event and 

will continue to adequately support and 

protect the spent fuel storage racks, storage 

array, and pool moderator/coolant. 

A fuel cask drop accident was previously 

evaluated as described in the CPS Updated 

Safety Analysis Report (USAR) Section 

15.7.5. Administrative controls will be 

implemented to ensure that fuel will be 

removed from storage racks located within 

the cask storage pool prior to any fuel cask 

being moved in this area. The presence of 

any empty racks in this area will not 

adversely affect the previously evaluated 

cask drop scenarios, since any impacted 

empty racks will tend to absorb the kinetic