alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
[Federal Register Volume 69, Number 204 (Friday, October 22, 2004)]
[Notices]
[Pages 62116-62117]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 04-23770]


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DEPARTMENT OF TRANSPORTATION

Surface Transportation Board

[STB Finance Docket No. 34533]


Southwestern Railroad Company, Inc.--Lease and Operation 
Exemption--The Burlington Northern and Santa Fe Railway Company

    Southwestern Railroad Company, Inc. (SWRR), a Class III rail 
carrier, has filed a verified notice of exemption under 49 CFR 1150.41 
et seq. to lease and operate from The Burlington Northern and Santa Fe 
Railway Company the following 227.6 miles of rail line located: (1) On 
the Carlsbad Subdivision between milepost 0.5, at Clovis, NM, and 
milepost 183.0, at Carlsbad, NM; (2) in the Carlsbad Yard;\1\ (3) on 
the Carlsbad Industrial Spur between milepost 0.0 and milepost 20.0, at 
Carlsbad, NM; and (4) on the Loving Industrial Spur between milepost 
0.0, at Carlsbad, NM, and milepost 20.0, at Loving, NM.
---------------------------------------------------------------------------

    \1\ SWRR states that there are no milepost designations 
associated with this 5.1-mile line of railroad located in the 
Carlsbad Yard.
---------------------------------------------------------------------------

    Because SWRR's projected annual revenues will exceed $5 million, 
SWRR certified to the Board on August 4, 2004, that, on July 29, 2004, 
it had posted the required 60-day notice of intent to undertake the 
proposed transaction at the workplace of the employees on the affected 
line and that, on August 4, 2004, it had served a copy of the notice of 
intent on the national offices of all labor unions with employees on 
the rail line. See 49 CFR 1150.42(e).
    SWRR states that it intended to consummate the transaction on or 
after the October 3, 2004 effective date of the exemption (60 days 
after its certification to the Board under 49 CFR 1150.42(e)).
    If the notice contains false or misleading information, the 
exemption is void ab initio. Petitions to revoke the exemption under 49 
U.S.C. 10502(d) may be filed at any time. The filing of a petition to 
revoke will not automatically stay the transaction.
    An original and 10 copies of all pleadings, referring to STB 
Finance Docket No. 34533, must be filed with the Surface Transportation 
Board, 1925

[[Page 62117]]

K Street NW., Washington, DC 20423-0001. In addition, one copy of each 
pleading must be served on Karl Morell, Of Counsel, Ball Janik LLP, 
Suite 225, 1455 F Street, NW., Washington, DC 20005.
    Board decisions and notices are available on our Web site at http://www.stb.dot.gov.

    Decided: October 19, 2004.

    By the Board, David M. Konschnik, Director, Office of 
Proceedings.
Vernon A. Williams,
Secretary.
[FR Doc. 04-23770 Filed 10-21-04; 8:45 am]
BILLING CODE 4915-01-P
NRC NEWS

 U.S. NUCLEAR REGULATORY COMMISSION 

 Office of Public Affairs Telephone: 301/415-8200

 Washington, DC 20555-001 E-mail: opa@nrc.gov 

 Web Site: http://www.nrc.gov/OPA

No. 01-082 July 6, 2001

 NRC TO BEGIN ONE-YEAR EVALUATION OF A REVISED PROGRAM

TO ASSESS PHYSICAL SECURITY AT NUCLEAR POWER PLANTS

The Nuclear Regulatory Commission is beginning a one-year pilot of the Safeguards Performance

Assessment (SPA) program, a process by which a power-reactor licensee tests the effectiveness of key

elements of its physical security program. 

 The pilot program will also allow NRC to evaluate concepts being considered for proposed

revisions to NRC regulations. It will also be used to determine if the SPA has merit as a possible

replacement for the Operational Safeguards Response Evaluation (OSRE), the current NRC program to

assess physical security at nuclear power plants.

The SPA program provides for:

ï development of "target sets," equipment essential for safe operations of a reactor, as the

basis for a licenseeís physical security measures;

ï participation by each security shift in a minimum of one annual licensee-evaluated drill to

demonstrate proficiency for key security personnel;

ï quarterly drills; and

ï participation in an NRC-evaluated exercise every 3 years to test the licenseeís ability to

protect target sets from mock acts of sabotage.

On a case-by-case basis, licensees who volunteer to participate in the SPA pilot may be exempt from

an OSRE. However, NRC baseline inspections under the reactor oversight program will continue to assess

licenseesí ability to protect themselves from malevolent acts. NRC will continue to conduct OSREs at sites

not participating in the SPA pilot program until its evaluation of SPA is completed and the Commission

determines whether it is an acceptable alternative to OSRE.

Under the SPA program, full-scale force-on-force exercises would be conducted at each nuclear

power plant every three years, exceeding the frequency of the OSRE program, which provides for an NRC

assessment of each plantís security programs every eight years. Like OSRE, the SPA program includes
provisions to address deficiencies identified through drills and exercises within the licenseeís corrective

action program.

 NRC will choose eight volunteers from those plants that have agreed to participate in the pilot

program. This evaluation is part of an ongoing effort by NRC to identify more efficient and effective ways

to assess security at nuclear power plants.

###
IIB 

108TH CONGRESS 

2D SESSION H. R. 1385

IN THE SENATE OF THE UNITED STATES 

JANUARY 28, 2004

Received; read twice and referred to the Committee on Governmental Affairs 

AN ACT

To extend the provision of title 39, United States Code, 

under which the United States Postal Service is authorized to issue a special postage stamp to benefit breast 

cancer research.

1 Be it enacted by the Senate and House of Representa2 tives of the United States of America in Congress assembled,
2

HR 1385 RFS 

1 SECTION 1. BREAST CANCER STAMP EXTENSION. 

2 Section 414(h) of title 39, United States Code, is 

3 amended by striking ‘‘2005’’ and inserting ‘‘2006’’.

Passed the House of Representatives January 27, 

2004. 

Attest: JEFF TRANDAHL, 

Clerk.
NASA LogoNTRSNTRS - NASA Technical Reports ServerSearchmore_vertCollectionsAboutNewsHelpLogin Back to ResultsPhysical vapor transport of mercurous chloride under a nonlinear thermal profileOur study investigates numerically the flow field characteristics during the growth of mercurous chloride (Hg2Cl2) crystals in a rectangular ampoule under terrestrial and microgravity conditions for a nonlinear thermal gradient. With a residual gas lighter than the nutrient, the solutal Grashof number is dominant. We observe that in tilted configurations, when solutal convection is dominant, the maximum transport rate occurs at approximately 40 percent. For the vertical configurations, we were able to obtain solutions only for the cases either below the critical Rayleigh numbers or the stabilized configurations. The total mass flux decreases exponentially with an increase of pressure of residual gas, but it increases following a power law with the temperature difference driving the transport. The nonlinear thermal gradient appears to destabilize the flow field when thermal convection is dominant for both vertical top-heated and bottom-heated configurations. However, when the solutal Grashof number is dominant, the density gradient resulting from the solutal gradient appears to stabilize the flow for the bottom-heated configuration. The flow field for the top-heated configuration is destabilized for high Grashof numbers. The microgravity environment provides a means for lowering convection. For gravity levels of 10(exp -3) g(0) or less, the Stefan wind drives the flow, and no recirculating cell is predicted.Document ID19930007423Acquisition SourceLegacy CDMSDocument TypeTechnical Memorandum (TM)AuthorsMennetrier, Christophe*(NASA Lewis Research Center Cleveland, OH, United States)*Duval, Walter M. B.*(NASA Lewis Research Center Cleveland, OH, United States)*Singh, Narsingh B.*(Westinghouse Science and Technology Center Pittsburgh, PA., United States)*Date AcquiredSeptember 6, 2013Publication DateNovember 1, 1992Subject CategoryFluid Mechanics And Heat TransferReport/Patent NumberNASA-TM-105920E-7413NAS 1.15:105920Accession Number93N16612Funding Number(s)PROJECT: RTOP 674-21-05Distribution LimitsPublicCopyrightWork of the US Gov. Public Use Permitted.Available DownloadsNameType19930007423.pdfSTIcloud_downloadcontent_copyvisibilityRelated RecordsThere are no records associated with this record.visibility_offNo Preview Available
 No Fear Act | Freedom of Information Act | Office of the Inspector General | Agency Financial ReportsNASA Web Privacy Policy and Important Notices | NASA Guidelines for Quality of InformationDisclaimers, Copyright, Terms of Use | Accessibility | NASA OCIO | USA.gov | NASA.govContact Us | Site MapSTI LogoNASA Official: JoAnne R. Calhoun Site Curator: STI Compliance and Distribution Services Last Modified: September 12, 2024
NRC NEWS

U.S. NUCLEAR REGULATORY COMMISSION

Office of Public Affairs Telephone: 301/415-8200

Washington, DC 20555-001 E-mail: opa@nrc.gov

Web Site: http://www.nrc.gov/OPA

No. 00-085 May 24, 2000

NRC ISSUES ANNUAL ASSESSMENTS FOR 13 NUCLEAR PLANTS THAT

PARTICIPATED IN PILOT EVALUATION OF REVISED REACTOR OVERSIGHT

PROCESS

The U.S. Nuclear Regulatory Commission has issued annual assessments for 13 nuclear power

plants that participated in a six month pilot evaluation of the revised reactor oversight process. This is

the first annual assessment of nuclear power plants under the new program.

No significant performance problems were identified at any of the 13 plants. They are:

ˇ Salem 1 and 2, near Wilmington, Delaware, operated by Public Service Electric & Gas;

ˇ Hope Creek near Wilmington, Delaware, operated by Public Service Electric & Gas;

ˇ Fitzpatrick, near Oswego, New York, operated by the Power Authority of the State of New

York;

ˇ Shearon Harris, near Raleigh, North Carolina, operated by Carolina Power & Light Co.;

ˇ Sequoyah 1 and 2, near Chattanooga, Tennessee, operated by the Tennessee Valley Authority;

ˇ Prairie Island 1 and 2, near Minneapolis, Minnesota, operated by Northern States Power Co.;

ˇ Quad Cities 1 and 2, near Moline, Illinois, operated by Commonwealth Edison Co.;

ˇ Ft. Calhoun, near Omaha, Nebraska, operated by the Omaha Public Power District;

ˇ Cooper, near Nebraska City, Nebraska, operated by the Nebraska Public Power District.

Results of these reviews and copies of letters sent to each licensee will be available from the

NRC Office of Public Affairs, at: http://www.nrc.gov/OPA/ppr on the NRC web site, and ADAMS,

the Agencywide Documents Access and Management System.

All commercial nuclear power plants (with the exception of the two D.C. Cook plants, due to

their extended shutdown) are now being evaluated under the revised reactor oversight process initiated

on April 2. The NRC expects to make additional refinements to the program during its first year of

implementation.

The revised reactor oversight process reflects several important themes for all of NRC's
activities - an even greater focus on safety, an effort to improve objectivity and timeliness, a

commitment to stakeholder involvement, and improved transparency of agency activities for both

licensees and the general public.

As part of the new program, each plant will receive an assessment letter every six months

which will include a 12-month inspection plan that may be updated periodically to reflect changes in

nuclear power plant performance and NRC resource allocations. Updated information on plant

performance is being posted to the NRC web site every quarter.

Public meetings at each of the 13 plants are being planned. Details of the meetings, which will

be open to the public, will be announced as they are scheduled.

A full description of the reactor oversight process is available at:

http://www.nrc.gov/OPA/primer.htm on the NRC web site. Details about plant performance can be

found at: http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index/html on the NRC web site.

##
U.S. NUCLEAR REGULATORY COMMISSION

Region III Office of Public Affairs

801 Warrenville Road, Lisle, IL 60532-4351

NEWS ANNOUNCEMENT: RIII-98-26 April 13, 1998

CONTACT: Jan Strasma 630/829-9663

Angela Greenman 630/829-9662

E-mail: opa3@nrc.gov

NOTE TO EDITORS:

CHANGE IN DATE FOR ABB COMBUSTION ENGINEERING MEETING

The Nuclear Regulatory Commission staff will meet with

officials of the ABB Combustion Engineering, Inc., commercial

nuclear fuel facility in Hematite, Missouri, on Thursday,

April 30, to discuss the plant’s regulatory performance.

(This is a change in the meeting date. Press Release RIII98-23 issued on April 3, announced the meeting as April 14)

The meeting will be at 1 p.m., at the company’s Hematite

Nuclear Manufacturing Facility Building 110, 3300 State Road P.

It is open for public observation. NRC officials will be

available at its conclusion to answer questions from the news

media and other interested observers.

NRC officials will discuss a Licensee Performance Review in

which the agency evaluated performance in five areas -- safety

operations, safeguards, radiological controls, facility support,

and licensing activities -- in order to form a basis for

establishing the NRC’s inspection program at the facility for the

next year.

The assessment covers the period from January 1, 1996,

through January 31 of this year.

The NRC review concludes that the facility’s performance in

radiological controls was “very good” and the remaining four

areas -- safety operations, safeguards, facility support, and

licensing activities -- were evaluated as “generally adequate.”

####

Note: A copy of the full report and press release RIII-98-23 are

available for review on the NRC’s internet web site at

http://www.nrc.gov/OPA/reports.
NRC NEWS

U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF PUBLIC AFFAIRS, REGION I

475 Allendale Road

King of Prussia, PA 19406

No. I-01-010 February 27, 2001

CONTACT: Diane Screnci, (610) 337-5330/e-mail: dps@nrc.gov

Neil A. Sheehan, (610) 337-5331/e-mail: nas@nrc.gov

NRC TO DISCUSS APPARENT VIOLATION AT WASHINGTON, D.C., HOSPITAL

Nuclear Regulatory Commission staff will meet with representatives of a Washington, D.C.,

medical facility on Monday, March 5, to discuss an apparent violation of agency requirements involving

the hospital’s radiation oncology program.

The predecisional enforcement conference with George Washington University Hospital is

scheduled to begin at 1 p.m. in the Public Meeting Room at the NRC Region I office, 475 Allendale

Road, King of Prussia, Pa. The meeting will be open to the public.

Last July, the NRC conducted a safety inspection at the hospital, located on 23rd Street, N.W., to

review a medical misadministration to one patient that occurred on June 15, 2000. During that event, a

patient underwent a cancer treatment that utilized radioactive cesium-137 brachytherapy sources.

However, because the sources being used shifted during treatment, the patient received a lesser dose

than prescribed to the cancerous tissue and a higher dose than prescribed to surrounding tissues. A

medical consultant contracted by the NRC to review the incident indicated the patient was experiencing

medical complications that may be attributable to the misadministration.

Based on the inspection, the NRC has preliminarily determined that the hospital’s quality

management program failed to include a written procedure to meet the objective that each

administration of nuclear medicine be in accordance with a written directive.

The decision to hold a predecisional enforcement conference does not mean that the NRC has

determined a violation has occurred or that enforcement action will be taken. Rather, the purpose is to

discuss the apparent violation, its causes and safety significance; to provide the licensee with an

opportunity to point out any errors that may have been made in the NRC inspection report; and to

enable the licensee to outline its proposed corrective action.

No decision on the apparent violation will be made at this conference. That decision will be

made by NRC officials at a later time.

###
### §§853 to 859. Repealed. Pub. L. 97–300, title I, §184(a)(1), Oct. 13, 1982, 96 Stat. 1357

Section 853, Pub. L. 93–203, title II, §231, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1957, set out the Congressional statement of purpose for transitional employment opportunities for the economically disadvantaged.

Section 854, Pub. L. 93–203, title II, §232, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1958, related to financial assistance to prime sponsors for transitional public service employment for economically disadvantaged persons who are unemployed.

Section 855, Pub. L. 93–203, title II, §233, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1958; amended Pub. L. 96–583, §3(b), Dec. 23, 1980, 94 Stat. 3376, related to allocation of funds for carrying out of transitional employment opportunities for the economically disadvantaged.

Section 856, Pub. L. 93–203, title II, §234, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1959, related to expenditure of funds by prime sponsors for purposes of transitional employment opportunities for economically disadvantaged.

Section 857, Pub. L. 93–203, title II, §235, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1959, related to applicability of section 966 of this title to transitional employment opportunities for economically disadvantaged.

Section 858, Pub. L. 93–203, title II, §236, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1959, related to eligibility for transitional employment opportunities for economically disadvantaged.

Section 859, Pub. L. 93–203, title II, §237, as added Pub. L. 95–524, §2, Oct. 27, 1978, 92 Stat. 1960, related to payment of wages to economically disadvantaged individuals employed in transitional public service employment.
###### Editorial Note on Part 151

#### Editorial Note:

Nomenclature changes to part 151 appear by CBP Dec. No. 16-26, 81 FR 93021, Dec. 20, 2016.

#### § 151.81 Definition of staple length.

For the purposes of this subpart, “staple length” means the length of the fibers in a particular quantity of cotton designated in terms expressing the measurement by the millimeter or fraction thereof of a representative portion of the quantity in accordance with the Official Cotton Standards of the United States for length of staple, as established by the Secretary of Agriculture.

[T.D. 73-175, 38 FR 17470, July 2, 1973, as amended by T.D. 89-1, 53 FR 51269, Dec. 21, 1988]
_______________________________________ __ Michigan Supreme Court 

# Order

Lansing, Michigan

August 29, 2006 Clifford W. Taylor, Chief Justice

Michael F. Cavanagh
Elizabeth A. Weaver 131549 & (27) Marilyn Kelly Maura D. Corrigan Robert P. Young, Jr. Stephen J. Markman, RICHARD DELENE a nd NANCY DELENE, Justices Plaintiffs-Appellees,

v SC: 131549 COA: 267209 Baraga CC: 05-005461-CH D. HAYWOOD & ASSOCIATES, P.C., now known as HAYWOOD HARRISON, P.C., Defendant-Appellant.

________________ _______________ __________/

On order of the Court, the motion for immediate consideration is GRANTED. The application for leave to appeal the May 18 , 2006 judgment of the Court of Appeals is considered, and it is DENIED, because we are not persuaded that th e questions presented
should be reviewed by this Court.

d0821 I, Corbin R. Davis, Clerk of the Mi chigan Supreme Cour t, certify that the foregoing is a true and complete copy of the order entered at the direction of the Court.

August 29, 2006

Clerk
NRC NEWS

UNITED STATES NUCLEAR REGULATORY COMMISSION

OFFICE OF PUBLIC AFFAIRS, REGION II

61 Forsyth Street SW, Atlanta GA 30303

Web Site: www.nrc.gov

No. II-03-016 March 21, 2003

CONTACT: Ken Clark (404)562-4416 E-mail: OPA2@nrc.gov

Roger Hannah (404)562-4417

Note: Change in location from previous news release issued March 19

 

NRC TO MEET WITH PROGRESS ENERGY OFFICIALS TO DISCUSS SAFETY

PERFORMANCE AT HARRIS NUCLEAR POWER PLANT

The U.S. Nuclear Regulatory Commission staff will meet with Progress Energy officials on

Tuesday, March 25, to discuss the results of NRC’s annual assessment of safety performance at the

Shearon Harris nuclear power plant southwest of Raleigh, North Carolina.

The meeting will be held at 1:00 p.m. in the Summit Room of the Apex Community Center,

53 Hunter Street in Apex (The meeting was previously scheduled at the Harris Energy and

Environmental Center Board Room, 3932 New Hill-Holleman Road near the plant). The public is

invited to observe the meeting, and NRC officials will be available before the conclusion of the

meeting to answer any questions.

A letter from the NRC to Progress Energy addresses plant safety performance during the

previous year and forms the basis for the meeting discussions. The letter states that, overall, Harris

operated in a manner that preserved public health and safety and that the plant fully met all objectives.

The letter, which is available from Region II Public Affairs and on the NRC web site at

www.nrc.gov/NRR/OVERSIGHT/ASSESS/LETTERS/har_2002q4.pdf , says the NRC staff is

considering some unresolved items identified during NRC fire protection inspections. If the NRC

determines that any of these items are greater than very low safety significance, additional inspections

in the fire protection area may be conducted. The letter also mentions two inspections planned for the

coming year beyond the baseline, or routine, NRC inspections. Those inspections involve a review of

the plant’s implementation of measures required by an NRC Security Order, dated February 25, 2002,

and a review of the plant staff’s activities in response to an NRC Bulletin on reactor vessel heads and

vessel head penetrations.

Current performance indicators for the Harris plant are available at 

www.nrc.gov/NRR/OVERSIGHT/ASSESS/HAR1/har1_chart.html

###
[Federal Register Volume 69, Number 205 (Monday, October 25, 2004)]
[Notices]
[Pages 62316-62317]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 04-23847]


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DEPARTMENT OF STATE

[Public Notice 4865]


Shipping Coordinating Committee; Notice of Meeting

    The Shipping Coordinating Committee will conduct an open meeting at 
9:30 a.m. on Tuesday, November 16, 2004, in Room 2415, at U.S. Coast 
Guard Headquarters, 2100 2nd Street, SW., Washington, DC 20593-0001. 
The purpose of this meeting will be to finalize preparations for the 
79th Session of the Maritime Safety Committee, and associated bodies of 
the International Maritime Organization (IMO), which is scheduled for 
December 1-10, 2004, at IMO Headquarters in London. At this meeting, 
papers received and the draft U.S. positions for the Maritime Safety 
Committee will be discussed. Among other things, the items of 
particular interest are:

--Adoption of amendments to SOLAS for voyage data recorders, bulk 
carrier safety, the International Code for Carrying Dangerous Chemicals 
in Bulk, company and owner identification numbers and fire safety.
--Large passenger ship safety.
--Measures to enhance maritime security.
--Goal-based new ship construction standards.
--Implementation of the revised STCW Convention.
--Reports of five subcommittees: Ship design and equipment, Flag State 
implementation, Safety of navigation, Stability, load lines and fishing 
vessel safety, Dangerous goods, solid cargoes and containers.


[[Page 62317]]


    Members of the public may attend this meeting up to the seating 
capacity of the room. Interested persons may seek information by 
writing to Mr. Joseph J. Angelo, Commandant (G-MS), U.S. Coast Guard 
Headquarters, 2100 2nd Street, SW., Room 1218, Washington, DC 20593-
0001 or by calling (202) 267-2970.

    Dated: October 19, 2004.
Clay Diamond,
Executive Secretary, Shipping Coordinating Committee, Department of 
State.
[FR Doc. 04-23847 Filed 10-22-04; 8:45 am]
BILLING CODE 4710-07-P