alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Issues License to Portland General Electric for Storage of Trojan Fuel in Independent Storage Installation

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No. 99-64 April 1, 1999

**NRC ISSUES LICENSE TO PORTLAND GENERAL ELECTRIC FOR STORAGE OF TROJAN FUEL IN INDEPENDENT STORAGE INSTALLATION**

The Nuclear Regulatory Commission has issued a license to Portland General Electric Company to permit spent nuclear fuel from the Trojan Nuclear Plant to be placed in dry storage at an independent spent fuel storage facility on the plant site near Ranier, Oregon, about 40 miles northwest of Portland on the Columbia River.

The spent fuel is currently at Trojan in the spent fuel pool.

The Trojan nuclear power plant has been shut down since November 1992. It had operated for 17 years.

The independent spent fuel storage installation is designed to provide temporary dry storage for all of the plant's spent fuel, so that decommissioning of the plant can proceed. During decommissioning, spent fuel assemblies, damaged fuel assemblies, and fuel debris currently located in the spent fuel pool will be loaded into dry shielded baskets in the plant's fuel building.

A transfer cask will be used to place the baskets in one of 34 heavily reinforced concrete vertical storage casks, which will be welded shut. The casks will then be moved to the storage installation, where all casks will be placed on a common reinforced concrete foundation slab.

Following decommissioning, the casks containing the fuel will remain on the slab as a stand-alone facility at the site. Operations thereafter will consist of daily inspections and recordkeeping.

The independent spent fuel storage installation license is for 20 years. NRC regulations permit Portland General Electric to request renewal.

Copies of the NRC's "Safety Evaluation Report for the Trojan Spent Fuel Storage Installation," as well as the recently issued license and the NRC's environmental assessment, are available for review and copying for a fee at the NRC Public Document Room, 2120 L Street, NW, Washington, DC 20555-0001, and the Local Public Document Room at the Portland State University, Branford Price Millar Library, 934 SW Harrison, Portland, Oregon 97207.

Page Last Reviewed/Updated Thursday, March 25, 2021
#### Simon, Respondent, vs. de Gersdorff, imp., Appellant.

*October 4*

October *23, 1917.*

*Simon v. de Gersdorff, ante,*p. 170, followed.

Appeal from an order of the circuit court for Milwaukee county: W. J. Turner, Circuit Judge.

*Affirmed.*

The appeal is from an order denying defendant’s motions to set aside service of summons and to suppress a proposed examination.

For the appellant there was a brief by *Upham, Black, Russell £ Richardson,*attorneys, and *Hoyt & Goff,*of counsel, all of Milwaukee, and oral argument by *Frank M. Hoyt*and *Wm. E. Black.*

For the respondent there was a brief by *Glicksman, Gold & Corri-gan*of Milwaukee, and oral argument by *W. L. Gold.*

Eschweileb, J.

The appeal in this case presents the identical situation and questions that are involved in the case of *Simon v. de Gersdorff, ante,*p. 170, 164 N. W. 818, and therefore the same judgment must follow.

*By the Court.*— The order of the circuit court is affirmed, and the cause remanded for further proceedings.

Rosenberby and Siebeoker, JJ., dissent. '
In the

Court of Appeals

Second Appellate District of Texas

at Fort Worth

No. 02-21-00273-CV

IN THE INTEREST OF S.B., A CHILD §

§

§

§

On Appeal from the 393rd District Court

of Denton County (21-0938-393)

October 21, 2021

Memorandum Opinion by Justice Walker

JUDGMENT

This court has considered the record on appeal in this case and holds that the 

appeal should be dismissed. It is ordered that the appeal is dismissed for want of 

jurisdiction.

SECOND DISTRICT COURT OF APPEALS 

By /s/ Brian Walker

 Justice Brian Walker
# L_2016300DE.01002901.xml

| 8.11.2016 | DE | Amtsblatt der Europäischen Union | L 300/29 |
| --- | --- | --- | --- |

8.11.2016

DE

Amtsblatt der Europäischen Union

L 300/29

---

Berichtigung der Delegierten Verordnung (EU) Nr. 1322/2014 der Kommission vom 19. September 2014 zur Ergänzung und Änderung der Verordnung (EU) Nr. 167/2013 des Europäischen Parlaments und des Rates hinsichtlich der Anforderungen an die Bauweise von Fahrzeugen und der allgemeinen Anforderungen im Zusammenhang mit der Typgenehmigung von land- und forstwirtschaftlichen Fahrzeugen

(
  Amtsblatt der Europäischen Union L 364 vom 18. Dezember 2014
  )

Seite 214, Anhang XI, Teil A Nummer 2:

Anstatt:

„Fahrzeuge der Klassen R und C“

muss es heißen:

„Fahrzeuge der Klassen T und C“.

Seite 267, Anhang XV, Nummer 3.4.1 erster Satz:

Anstatt:

„Handläufe oder Haltegriffe sind so anzubringen und zu gestalten, dass sich die Bedienungsperson, wenn sie sich an ihren Platz begibt oder ihn verlässt, an drei Stellen gleichzeitig halten kann.“

muss es heißen:

„Handläufe oder Haltegriffe sind so anzubringen und zu gestalten, dass die Bedienungsperson, wenn sie sich an ihren Platz begibt oder ihn verlässt, jederzeit einen Dreipunktkontakt aufrecht erhalten kann.“

Seite 267, Anhang XV, Nummer 4.1 dritter Satz:

Anstatt:

„Handläufe oder Haltegriffe sind so anzubringen und zu gestalten, dass sich die Bedienungsperson jederzeit an drei Stellen gleichzeitig halten bzw. aufstützen kann.“

muss es heißen:

„Handläufe oder Haltegriffe sind so anzubringen und zu gestalten, dass die Bedienungsperson jederzeit einen Dreipunktkontakt aufrecht erhalten kann.“

---
Exhibit 13.2

ChipMOS TECHNOLOGIES (Bermuda) LTD.

CERTIFICATION

Pursuant to 18 U.S.C. §1350, the undersigned, Shou-Kang Chen, Chief Financial Officer of ChipMOS TECHNOLOGIES (Bermuda) LTD. (the
Company), hereby certifies, to his knowledge, that the Companys Annual Report on Form 20-F for the year ended December 31, 2011 (the Report) fully complies with the requirements of Section13(a) or 15(d), as
applicable, of the Securities Exchange Act of 1934, and that the information contained in the Report fairly presents, in all material respects, the financial condition and results of operations of the Company, as of, and for, the periods presented
in the Report.

The foregoing certification is being furnished pursuant to 18 U.S.C. §1350 solely for purposes of
complying with the provisions of Section 906 of the Sarbanes-Oxley Act of 2002, is not intended to be used or relied upon for any other purpose and is not being filed as part of the Report or as a separate disclosure document.

Date: April 26, 2012



/s/ Shou-Kang ChenName:

Shou-Kang ChenTitle:

Chief Financial Officer
#### St. Joseph’s Hospital of the Sisters of St. Francis, Respondent, vs. Town of Withee, Appellant.

*October 12*

November *9, 1932.*

*H. G. Haight*of Neillsville, for the appellant.

For the respondent there was a brief by *W. H. Stafford*and *Harold E. Stafford,*both of Chippewa Falls, and oral argument by *Harold'E. Stafford.*

Fairchild, J.

The indigent person had a lawful settlement in the town of Withee. In 1928 this person was placed in respondent’s hospital by members of her family under a private arrangement and charges were paid out of her own funds until they were exhausted. This condition was reached prior to March 27, 1930, at which time there was an unpaid *425balance due respondent of $148.50. The situation of the indigent person and the respondent hospital at this time was presented to the authorities of the town of Withee, who, on behalf of the town, paid the amount then due and made an agreement for future care and maintenance, not, however, for any fixed period of time. The town continued to pay such charges up to and including March 26, 1931. At that time, according to the findings of the trial court, the town “refused to pay further charges for the hospital care and attention of said indigent, . . . and refused to support and maintain the plaintiff pursuant to the contract previously entered into; . . . ” Reasons were assigned for this action of the town at the time, but these reasons do not affect the definiteness of the détermination on the part of the town to be no longer bound to the respondent.

No bill of exceptions was settled in this case, and in its absence the sole inquiry is as to whether or not the findings support the judgment. The liability of the town to the respondent in this case ended when the contract ended. If the person remained indigent the town sustained under the law a liability to provide her with care and maintenance, but it was not obliged to continue her at the hospital of the respondent. There were ways in which respondent might have protected itself against further expense arising out of the maintenance of this particular person by bringing the matter to the attention of the proper authorities and proceeding as provided in sec. 49.03, Stats.

The law, as pointed out in *Patrick v. Baldwin,*109 Wis. 342, 85 N. W. 274, does not permit a private party, at the expense of the town, to aid or relieve an indigent person without a contract to that effect existing between him and the town. The officers of appellant town duly terminated the arrangement theretofore existing between the town and the hospital under which the town was liable for the maintenance. This termination occurred March 26, 1931. The services *426rendered thereafter by respondent were not so rendered under any contract or promise to pay therefor on the part of the town. This leaves the respondent without remedy against the town for the services rendered after that date.

*By the Court.*— Judgment of the county court reversed, and the cause remanded with directions to dismiss plaintiff’s complaint.
No. 90-5846.

#### Barnes *v.*United States.

C. A. 11th Cir. Certiorari denied.
Tetra Tech, Inc.

10306 Eaton Place, Suite 340 Fairfax, VA 22030 phone 703 - 385 - 6000 fax 703 - 385 - 6007 TO : Record FROM : Kelly

Meadows DATE: February 24 , 20 SUBJECT: Organism densities The following document present waterbod y t ypes. Attachment A shows that impingement and entrainment (on a volumetric basis) is present in all waterbod y typ es in similar concentrations. 

### MEMORANDUM
10306 Eaton Place, Suite 340

Kelly Meadows , 20 11 Organism densities by

waterbody

t ype present s information on the density of organisms in various Attachment A shows that impingement and entrainment (on a volumetric basis) is present in all waterbod y typ es in similar concentrations.

1 information on the density of organisms in various Attachment A shows that impingement and entrainment (on a
UNITED STATES ENVIRONMENTAL PROTECTION AGENCY REGION III______ 1650 Arch Street%Ic’ Philadelphia, Pennsylvania 19103-2029 COPY FOR YOUR

I FORMATION NOV 13

George Aburn, Jr., Director Air and Radiation Management Administration Maryland Department of the Environment 1800 Washington Boulevard Baltimore, Maryland 21230 Dear Mr. Abum: This letter is in.reference to two StateImplernentation Plan (SIP) revisions that

the State of Maryland submitted to the EnvirOnmentalProtection Agency (EPA) on June

4, 2007. The SIP revisions are entitled (1) “Baltimore Nonattainment Area 8-Hour Ozone State Implementation Plan and Base Year Inventory (SIP # 07-04)” and (2) “Cecil County, Maryland 8Hour Ozone State Implementation Plan and Base Year Inventory
(SIP #07-05).” These SIP revision submittals are dated June 15,2007. The June 4, 2007 sübrnittals consist of SIP revisions addressing four elements required by Sections 172(c) and 182 of the Clean Air Act as implemented by Subpart X

of 40 CFR part 51 fór moderate and above 8-hour ozOne nonattainment areas. These elements are (1) the 2002 base year emissions inventory, (2). the 15 percent reasonable further progress plan (RFP plan), (3) the attainment demonstration, and (4) contingency measures.... EPA requests that by. December 5,2008, Maryland identify which sections of its

SIP subrñittals address the RFP plan and related elements, including the2002 base year

•

emissions inventory. We ask that you identify each component of each of these four elements by its associated sectiOns, subsections, or if warranted, paragraph of the relevant subrnittal,.including any related appendices.or relevant.cbiments/responses. We are •requestingthât you provideus this very specific inforrñatioii sothat we can propose rulemaking on any elements of these submittäls that we may determine to be severable from the attainment demonstrations themselves. Should you have any questions regarding this request, please do not hesitate to contact me, or have your staff person contact Maria Pino of my staff at

(2 5)8 14-2 18 1. Sz4rely, j Ju h M. Katz, Dir tor Air Protection Division
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Simulation of the F2.1 Experiment at PKL Facility Using RELAP5/MOD3 (NUREG/IA-0250)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0250 (PDF - 6.39 MB)

## Publication Information

**Date Published:**February 2011

**Prepared by:** S. Carlos, J.F. Villanueva, S. Martorell, V. Serradell

Universidad Politécnica de Valencia Cami de Vera s/n 46022 Valencia, SPAIN

A. Calvo, NRC Project Manager

Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP) 

**Published by:** U.S. Nuclear Regulatory Commission

Availability Notice

## Abstract

When a nuclear power plant is in shutdown conditions for refuelling, the reactor coolant system water level is reduced. This situation is known as mid-loop operation, and the residual heat removal (RHR) system is used to remove the decay power heat generated in the reactor core.

In mid-loop conditions, some accidental situations may occur with not a negligible contribution to the plant risk, and all involve the loss of the RHR system. Thus, to better understand the thermalhydraulic processes following the loss of the RHR during shutdown, transients of this kind have been simulated using best-estimate codes, comparing their results against experimental data taken from different integral test facilities. This paper focuses on the simulation, using the best estimate code RELAP5/Mod 3.3, of the experiment F2.1 conducted at the PKL facility, within the OECD/PKL project. This experiment consists of the loss of the RHR system when the plant is in mid-loop conditions for refuelling and with the primary circuit closed. In the experimental series F2.1the physical phenomena to investigate are the mechanisms of heat removal in presence of nitrogen and the deboration in critical parts of the primary system.

Two experiments belonging to this experimental series have been performed. The simulations present differences in the initial plant coolant inventory and temperature in the pressurizer, F2.1RUN1 and F2.1RUN2, to asses the influence of these differences in the transient evolution.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC ContractorsRadioactive Effluents from Nuclear Power Plants (NUREG/CR-2907)

# Radioactive Effluents from Nuclear Power Plants: Annual Report 2017 (NUREG/CR-2907, Volume 23)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-2907, Volume 23 (PDF – 1.59 MB)

## Publication Information

**Manuscript Completed:** November 2019**Date Published:** November 2019

**Prepared by:** J. Davis

Oak Ridge Associated Universities 1299 Bethel Valley Road, SC-200, MS-21 Oak Ridge, TN 37830

Steven Garry and Micheal Smith, NRC Project Managers

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

In 2017, there were 99 commercial nuclear power plants (NPPs) licensed to operate on 60 sites in the United States (U.S.) regulated by the Nuclear Regulatory Commission (NRC). Each year, each power reactor sends a report to the NRC that identifies the radioactive gaseous and liquid effluents discharged from the facility. In 2017, these effluent reports comprised about 10,000 pages of information, which described the radioactive materials discharged, as well as the resulting radiation doses to the general public. This report summarizes that information and presents the information in a format intended for both nuclear professionals and the general public.

The reader can use this report to quickly characterize the radioactive discharges from any U.S. NPP in 2017. The radioactive effluents from one reactor can be compared with other reactors. The results can also be compared with typical (or median) effluents for the industry, including short-term trends and long-term trends.

Reference information is included so the reader can compare the doses from NPP effluents with the doses that the general public receives from other sources of radiation, such as medical procedures, industrial devices, and naturally occurring radioactive materials in the environment.

Although all operating NPPs released some radioactive materials in 2017, all effluents discharged were within the NRC's and the Environmental Protection Agency's (EPA’s) public dose limits, and NRC's "as low as is reasonably achievable" (ALARA) criteria. Additionally, the doses from radioactive effluents were much less than the doses from other sources of natural radiation that are commonly considered safe. This indicates radioactive effluents from NPPs in 2017 had no significant impact on the health and safety of the public or the environment.

Page Last Reviewed/Updated Wednesday, March 24, 2021
December 7, 2015

U.S. Department of Transportation

Docket Management System

1200 New Jersey Ave., SE Washington, DC 20590

Amendment to Exemption No. 12074 Regulatory Docket No. FAA–2015–1369 under Section

333 of the FAA Modernization and Reform Act of 2012 and 14 C.F.R. Part 11 regarding sUAS

use.

Dear Sir or Madam:

Regarding: Exemption No. 12074 Regulatory Docket No. FAA–2015–1369 approved on July 17,

2015.

Zugunruhe Geo, LLC seeks to amend this exemption as follows:

1) Additional aircraft.

There has been no change in the conditions and reasons relative to public interest and safety that were the basis for 

granting the original exemption.

The current exemption is for the following:

1) Aircraft

a. 3D Robotics Aero-M and Y6, ZetaScience FX-79, and the DJI S1000+

We request that the current exemption include the following aircraft. Many of these aircraft have been granted 333 

exemptions by the FAA to other companies. All aircraft are under 55 lbs.

Additional aircraft to be added to the existing exemption and COA

DJI Phantom 3, DJI Inspire, Roboflight RF70, Precision Hawk Lancaster, Freefly Alta

Please contact the undersigned should you have any question concerning this request for an

amendment to the Exemption.

Sincerely yours,

Joseph P. Busalacchi

1320 Nancy Drive

Tallahassee, Florida 32301
No: II-19-005 March 1, 2019

Contact: Roger Hannah, 404-997-4417

 Joey Ledford, 404-997-4416

NRC Names Senior Resident Inspector at Farley Nuclear Plant 

Nuclear Regulatory Commission officials in Atlanta have selected Peter 

Meier as the agency’s senior resident inspector at Southern Nuclear Operating 

Co.’s Farley nuclear power plant, located near Columbia, Ala., about 20 miles 

east of Dothan. 

Meier joins NRC Resident Inspector Ken Miller at the two-unit site. 

Meier joined the NRC in May 2015 in the Region I (King of Prussia, 

Pa.) Office as a project engineer. Before accepting the Farley position, Meier 

was the NRC resident inspector at the Seabrook nuclear plant in New 

Hampshire.

Prior to joining the agency, Meier was a licensed senior reactor operator and system engineer at 

the Turkey Point nuclear plant in Homestead, Fla. He also previously held various engineering 

positions with Maersk Lines, Red River Shipping, and Drew Marine Chemical. 

He earned a bachelor’s degree in marine engineering from the United States Merchant Marine 

Academy and later earned a U. S. Coast Guard chief engineer’s license, unlimited horsepower. 

Each operating U.S. commercial nuclear power plant site has at least two NRC resident 

inspectors. They serve as the agency’s eyes and ears at the facility, conducting regular inspections,

monitoring significant work projects, and interacting with plant workers and the public. Inspectors can 

serve for up to seven years at any one site. 

The NRC resident inspectors at the Farley plant can be reached at 404-997-5140.
I 

115TH CONGRESS 

1ST SESSION H. R. 1362 

To name the Department of Veterans Affairs community-based outpatient 

clinic in Pago Pago, American Samoa, the Faleomavaega Eni Fa’aua’a 

Hunkin VA Clinic. 

IN THE HOUSE OF REPRESENTATIVES 

MARCH 6, 2017 

Mrs. RADEWAGEN introduced the following bill; which was referred to the 

Committee on Veterans’ Affairs 

A BILL 

To name the Department of Veterans Affairs communitybased outpatient clinic in Pago Pago, American Samoa, 

the Faleomavaega Eni Fa’aua’a Hunkin VA Clinic. 

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

3 SECTION 1. NAME OF DEPARTMENT OF VETERANS AFFAIRS 

4 COMMUNITY-BASED OUTPATIENT CLINIC, 

5 PAGO PAGO, AMERICAN SAMOA. 

6 The Department of Veterans Affairs community7 based outpatient clinic in Pago Pago, American Samoa, 

8 shall after the date of the enactment of this Act be known 

9 and designated as the ‘‘Faleomavaega Eni Fa’aua’a 


sradovich on DSK3GMQ082PROD with BILLS
2 

•HR 1362 IH

1 Hunkin VA Clinic’’. Any reference to such community2 based outpatient clinic in any law, regulation, map, docu3 ment, record, or other paper of the United States shall 

4 be considered to be a reference to the Faleomavaega Eni 

5 Fa’aua’a Hunkin VA Clinic. 

Æ 


sradovich on DSK3GMQ082PROD with BILLS
Final Listing of Questionnaire Files for Steam Electric Rulemaking Record

Plant ID 06980

Removed 

from Public 

(Non-CBI) 

Docket1

Copyright 

Flag2

File Name Description

x 06980\06980_Checklist.xls

06980\06980_Completeness_Checklist.xls

06980\06980_HardcopyLog.doc

x 06980\06980_PartA.xls

06980\Certification Statement Plant ID 06980.pdf

1

 Final reviewed survey responses are located in the Steam Electric Technical Questionnaire Database . 

2

 Copyright documents are available from the docket.