alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
No: 19-010 March 7, 2019

CONTACT: Scott Burnell, 301-415-8200

NRC Issues Annual Assessments for Nation’s Nuclear Plants

The Nuclear Regulatory Commission has issued annual letters to the nation’s 98 commercial 

nuclear power plants operating in 2018 regarding their performance throughout the year. All were in 

the two highest performance categories.

Ninety-three of 98 fully met all safety and security performance objectives and were 

inspected by the NRC using the normal “baseline” inspection program.

Four reactors were assessed as needing to resolve one or two items of low safety 

significance. For this performance level, regulatory oversight includes additional inspection and 

follow-up of corrective actions. Plants in this level are: Grand Gulf (Mississippi); Peach Bottom 2 

& 3 (Pennsylvania); and Watts Bar 2 (Tennessee). Watts Bar 2 resolved its issues since the 

reporting period ended and has transitioned to the highest performing level.

There were no reactors in the third performance category with a degraded level of 

performance. 

One reactor has transitioned out of the fourth performance category. Pilgrim 

(Massachusetts) was in that category because of now-resolved issues of low-to-moderate safety 

significance. Reactors that reach this category receive additional inspections to confirm the 

performance issues are being addressed, and Pilgrim’s latest additional inspection concluded the 

plant can return to the highest performance level.

Later this spring and summer, the NRC will host a public meeting or other event in the 

vicinity of each plant to discuss the details of the annual assessment results. A separate 

announcement will be issued for each public assessment meeting. In addition to the annual 

assessment letters, plants also receive an NRC inspection plan for the coming year.

Information on the NRC’s oversight of commercial nuclear power plants is available 

through the NRC’s webpage on the Reactor Oversight Process. The NRC routinely updates 

information on each plant’s current performance and posts the latest information as it becomes 

available to the action matrix summary. Assessment letters are posted here; click on “2018q4” for 

each plant for the 2018 annual assessment. Annual construction oversight assessments for new 

reactors at the Vogtle units 3 and 4 sites are also on the NRC website.
```

[Congressional Bills 115th Congress]
[From the U.S. Government Publishing Office]
[H.R. 1442 Introduced in House (IH)]

<DOC>

115th CONGRESS
  1st Session
                                H. R. 1442

To extend the period of eligibility for non-competitive appointment of 
 Peace Corps and VISTA volunteers and certain overseas employees, and 
                          for other purposes.

_______________________________________________________________________

                    IN THE HOUSE OF REPRESENTATIVES

                             March 9, 2017

  Mr. Lynch (for himself, Mr. Katko, Mr. Kennedy, and Mr. Garamendi) 
 introduced the following bill; which was referred to the Committee on 
Foreign Affairs, and in addition to the Committee on Education and the 
 Workforce, for a period to be subsequently determined by the Speaker, 
 in each case for consideration of such provisions as fall within the 
                jurisdiction of the committee concerned

_______________________________________________________________________

                                 A BILL

 
To extend the period of eligibility for non-competitive appointment of 
 Peace Corps and VISTA volunteers and certain overseas employees, and 
                          for other purposes.

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

SECTION 1. SHORT TITLE.

    This Act may be cited as the ``Public Service Federal Eligibility 
Protection Act of 2017''.

SEC. 2. EXTENSION OF ELIGIBILITY FOR NON-COMPETITIVE APPOINTMENT OF 
              PEACE CORPS AND VISTA VOLUNTEERS AND CERTAIN OVERSEAS 
              EMPLOYEES.

    (a) In General.--Notwithstanding any other law, rule, or 
regulation, the eligibility for non-competitive appointment of any 
individual provided under Executive Order 11103 (relating to non-
competitive appointment of eligible Peace Corps volunteers) or 
Executive Order 12721 (relating to non-competitive appointment of 
certain overseas employees) or a VISTA volunteer under title I of the 
Domestic Volunteer Service Act of 1973 (42 U.S.C. 4951 et seq.) shall 
be extended by an amount of days (if any) equal to the number of days 
that such eligibility coincides with any Federal hiring freeze.
    (b) Definition of Federal Hiring Freeze.--In this section, the term 
``Federal hiring freeze'' means the memorandum titled ``Presidential 
Memorandum Regarding the Hiring Freeze'' published on January 23, 2017, 
or any other substantially similar memorandum, Executive order, or 
other action by the President to prevent a department or agency of the 
Federal Government from filling vacant Federal civilian employee 
positions or creating new such positions.
                                 <all>
```
Attachment 1 

DVMT Inventory 

(Available upon request)
```

[Federal Register Volume 89, Number 230 (Friday, November 29, 2024)]
[Notices]
[Page 94774]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-27918]

-----------------------------------------------------------------------

POSTAL SERVICE

Product Change--Priority Mail Express, Priority Mail, and USPS 
Ground Advantage[supreg] Negotiated Service Agreement

AGENCY: Postal ServiceTM.

ACTION: Notice.

-----------------------------------------------------------------------

SUMMARY: The Postal Service gives notice of filing a request with the 
Postal Regulatory Commission to add a domestic shipping services 
contract to the list of Negotiated Service Agreements in the Mail 
Classification Schedule's Competitive Products List.

DATES: Date of required notice: November 29, 2024.

FOR FURTHER INFORMATION CONTACT: Sean C. Robinson, 202-268-8405.

SUPPLEMENTARY INFORMATION: The United States Postal Service[supreg] 
hereby gives notice that, pursuant to 39 U.S.C. 3642 and 3632(b)(3), on 
November 19, 2024, it filed with the Postal Regulatory Commission a 
USPS Request to Add Priority Mail Express, Priority Mail & USPS Ground 
Advantage[supreg] Contract 760 to Competitive Product List. Documents 
are available at www.prc.gov, Docket Nos. MC2025-451, K2025-448.

Sean C. Robinson,
Attorney, Corporate and Postal Business Law.
[FR Doc. 2024-27918 Filed 11-27-24; 8:45 am]
BILLING CODE 7710-12-P
```
Form of Series 8 Preferred Stock Certificate


 Exhibit 4.1 

 

					
	Number P8-        	  	CELL THERAPEUTICS, INC.	  	*            * Shares
		  	A Washington Corporation	  	Series 8 Preferred Stock

 THIS CERTIFIES THAT
*                                        
                        * is the record holder of
*                                        
                        
(                                )* shares of Series 8 Preferred
Stock of Cell Therapeutics, Inc. (the “Corporation”) transferable only on the share register of the Corporation by the holder, in person or by such holder’s duly authorized attorney, upon surrender of this certificate
properly endorsed or assigned. 
 This certificate and the shares represented hereby shall be held subject to all of the
provisions of the Amended and Restated Articles of Incorporation and the Second Amended and Restated Bylaws of the Corporation and any amendments thereto, a copy of each of which is on file at the office of the Corporation and made a part hereof as
fully as though the provisions of said Amended and Restated Articles of Incorporation and Second Amended and Restated Bylaws were imprinted in full on this Certificate, to all of which the holder of this Certificate, by acceptance hereof, assents
and agrees to be bound. 
 The shares represented by this Certificate are convertible into shares of Common Stock as set forth
in the Amended and Restated Articles of Incorporation of the Corporation. 
 The Corporation will furnish without charge to each
shareholder who so requests, the powers, designations, preferences and relative, participating, optional or other special rights of each class of stock or series thereof and the qualifications, limitations or restrictions of such preferences or
rights. 
 IN WITNESS WHEREOF, the Corporation has caused this Certificate to be signed by its duly authorized officers this
     day of January, 2011. 
  
  

					
	  
 James A. Bianco, Chief Executive Officer
	 		  	  
 Louis A. Bianco,
Executive Vice President, Finance and Administration








 FOR VALUE RECEIVED, THE UNDERSIGNED HEREBY SELLS, ASSIGNS AND TRANSFERS UNTO
                                         
       
                                         
        SHARES REPRESENTED BY THE WITHIN CERTIFICATE AND DOES HEREBY IRREVOCABLY CONSTITUTE AND APPOINT
                             ATTORNEY TO TRANSFER THE SAID SHARES ON THE SHARE REGISTER OF THE WITHIN
NAMED CORPORATION WITH FULL POWER OF SUBSTITUTION IN THE PREMISES. 

DATED                     

 
  

	
	  
 (Signature)



 NOTICE: THE SIGNATURE ON THIS ASSIGNMENT MUST CORRESPOND WITH
THE NAME AS WRITTEN UPON THE FACE OF THIS CERTIFICATE, IN EVERY PARTICULAR, WITHOUT ALTERATION OR ENLARGEMENT, OR ANY CHANGE WHATEVER.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# US Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 (NUREG/CR-7227, ORNL/TM-2015/619)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7227 (PDF – 4.90 MB)

## Publication Information

**Manuscript Completed:** June 2016**Date Published:** September 2016

**Prepared by:** Jianwei Hu, Ian C. Gauld, Joshua L. Peterson, and Stephen M. Bowman

Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6170

Mourad Aissa, NRC Project Manager

NRC Job Code Number V6449

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

Availability Notice

## Abstract

Activities related to management of spent nuclear fuel (SNF) are increasing in the US and many other countries. Over 240,000 SNF assemblies have been discharged from US commercial reactors since the late 1960s. The enrichment and burnup of SNF have changed significantly over the past 40 years, and fuel assembly designs have also evolved. Understanding the general characteristics of SNF helps regulators and other stakeholders form overall strategies towards the final disposal of US SNF. This report documents a survey of all US commercial SNF assemblies in the GC-859 database and provides reference SNF source terms (e.g., nuclide inventories, decay heat, and neutron/photon emission) at various cooling times up to 200 years after fuel discharge. This study reviews the distribution and evolution of fuel parameters of all SNF assemblies discharged over the past 40 years. Assemblies were categorized into three groups based on discharge year, and the median burnups and enrichments of each group were used to establish representative cases. An extended burnup case was created for boiling water reactor (BWR) fuels, and another was created for the pressurized water reactor (PWR) fuels. Two additional cases were developed to represent the eight mixed oxide (MOX) fuel assemblies in the database. Burnup calculations were performed for each representative case. Realistic parameters for fuel design and operations were used to model the SNF and to provide reference fuel characteristics representative of the current inventory. Burnup calculations were performed using the ORIGEN code, which is part of the SCALE nuclear modeling and simulation code system. Results include total activity, decay heat, photon emission, neutron flux, gamma heat, and plutonium content, as well as concentrations for 115 significant nuclides. These quantities are important in the design, regulation, and operations of SNF storage, transportation, and disposal systems.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Structural Seismic Fragility Analysis of the Surry Containment (NUREG/CR-6783)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6783 (PDF - 4.41 MB)

## Publication Information

**Manuscript Completed:** June 2002**Date Published:** October 2002

**Prepared by:** Eric W. Klamerus

Sandia National Laboratories Albuquerque, NM 87185-0744

J. Davis, NRC Project Manager

**Prepared for:** Division of Engineering Technology Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission****Washington, DC 20555-0001

NRC Job Code W6487 

Availability Notice

## Abstract

In a collaborative program between the United States Nuclear Regulatory Commission and the Nuclear Power Engineering Corporation (NUPEC) of Japan, the seismic behavior of a Reinforced Concrete Containment Vessel (RCCV) model was investigated. A 1:8 scale RCCV model was constructed by NUPEC and subjected to seismic simulation tests. Dynamic 3D finite element analyses were performed before and after the seismic tests.

Utilizing the same material models developed for the RCCV analysis, a detailed finite element model was developed for the Surry Nuclear Power plant containment structure and seismic analyses were performed. Material models that were validated by previous scaled model seismic tests and analyses were used. The Surry model was then subjected to 30 different earthquake time-history accelerations. In addition, Latin Hypercube Sampling was used to vary all the material and modeling parameters of the input to get a realistic distribution for this limited set of runs.

Fragilities were generated based on the limiting concrete shear strains. In general, the results show the Surry reinforced containment is highly resistant to seismic structural failure when it is modeled on a rigid rock foundation. The most significant variable in the response is the variability in the input earthquakes. Modeling on a rock site, rather than on a soil site, will produce higher concrete stresses and strains than for a less rigid site model, resulting in a conservative estimate of the structural capacity of a reinforced concrete containment. These predictions may be non-conservative for other failure modes (such as pipes breaking), however, because a containment on a soil site would probably see larger displacements than a containment attached to rock.

Page Last Reviewed/Updated Wednesday, March 24, 2021
**NRC INSPECTION MANUAL**	IRIB

INSPECTION MANUAL CHAPTER 2515 APPENDIX C

# SPECIAL AND INFREQUENTLY PERFORMED INSPECTIONS

Effective Date: 06/26/2023

This appendix lists inspection procedures that are implemented infrequently for special situations. These inspections may be implemented in response to events, infrequent major activities at nuclear power plants, to evaluate emergent technical issues not related to licensee performance, to fulfill NRC’s obligations under domestic interagency memoranda of understanding, or to implement the requirements of 10 CFR Part 75 for treaties between the United States and the International Atomic Energy Agency.

These inspections are not part of the baseline or supplemental inspection program elements and Regional Administrator authorization is required to charge inspection hours to any of the listed inspection procedures below. To provide for adequate documentation of agency business consistent with 36 CFR 1222.22, the Regional Administrator’s authorization shall be annotated in an Official Agency Record that either approves or documents any inspection implemented using this appendix.

Non-baseline inspection used to address deficient licensee performance is supplemental inspection and shall be addressed under Inspection Manual Chapter (IMC) 2515, Appendix B, “Supplemental Inspection Program.”

Each inspection procedure in the table below will be reviewed in accordance with the periodicity and process specified in IMC 0040, “Preparation, Revision, Issuance, and Ongoing Oversight of NRC Inspection Manual Documents.” IMC 0307, Appendix A, “Reactor Oversight Process SelfAssessment Metrics and Data Trending,” is used to assess the conduct of this review. [C1]

Issue Date: XX/XX/XX	C-2	2515 Appendix C

Issue Date: 06/26/23	1	2515 App C

Attachment 1: Revision History for IMC 2515, Appendix C

Issue Date: 06/26/23	Att1-4	2515 App C
## •--c ! OPERATION S ^^^Oeci- i AW : 2 2 

## Cumfaedan

b Count ? Hegieilatib e delegatio n iSortl ) Carolin a(Genera

l lasficmbl p 3&alctg(j , Mottl ) Carolin a2760 1 109 6 ^epresfeiitatib e ^ic h iSla^ier , ^ou^ e 4 5 ^epredentotib e Clme r jno^b
. i^ousc e 4 3 3&epre£(entatib

p iRarbi n HurnS , J^ousf

c 4 2 3ftcpref(enfatiti e ^^tUia m?@rif(s(on , J^outf p 2 2 i^cprcsfcntatib e 3Bian

e ^arfitt , ^Dust e 4 4 Senato r Harr p Sidabs , Senat e 2 1 Senato r ifWatgaret

?^igl)£(mitf

t ©itfetfon , Senat e 1 9
Augus t 18,201 0 Th e Honorabl e Ra

y LaHoo d Secretary , U.S
. Department o f Transportatio n 120 0 New Jerse y Avenue , S E Washington , D C 2059 0 Th e Cumberlan d Count

y Legislativ e Delegatio n write s t o expres s stron g suppor t fo r th e grant applicatio n submitte d b

y Nort h Carolina' s Fayettevill e Regiona l Airpor t (FAY ) under

th e Smal l Communit

y Ai r Servic e Development

Program
. Ne w non-sto p ai r servic e betwee n Fayettevill e and th e Washington , D C are aha s been identifie d b

y ou r loca l communit

y a s ahigh-priorit

y transportatio n requirement
. A financial grant would hel p secur

e th e commitment

o f acommercia

l airlin e t o provid e thi s important service
. Demand fo

r Washington , D C ai r

servic e i s bein g driven b

y missio n growt

h a t For t Brag g relate d t o th e Bas e Realignment

and Closure (BRAC ) process . Unde r BRAC , For

t Brag g will ad d thousand s o f militar y personne l i

n th e nex t fe w years . O f

particula r note , th e U.S
. Arm

y Force s Comman d (FORSCOM ) an d Arm y Reserv e Comman d (USARC ) wil l transfe r fromFor t McPherso n i

n Atlant at o For

t Brag g b y Septembe r 2011
. Th e additio n o f

thes e unit s wil l substantiall y increas e th e number o f trip s between For

t Brag g an d Washington , D C bot

h b y th e tnilitary an d companie s doin g busines s wit h th e Department

o f Defense
. Locate d jus t

13. 6 mile s fromFor

t Bragg' s mai n gat e and withi n eas y acces s o f surroundin g communities , Fayettevill e Regiona

l Airpor t i s ideall y positione d t o accommodate th e region' s Washington , DC n-avelers
. Currently , th e Fayettevill e Regiona l Airpor t serve s a12-count

y are ai n th e Sandhill s o f

souther n Nort h Carolin aand traveler s i

n thi s marke t

ar e force d t o either

driv e 6 hour s eac h wa

y o r fly vi aalternativ e airports
. Thes e option s ar

e neithe r efficien t no r economical and presen t

substantial obstacle s t o maximizin g th e economi c potential o f th e BRA C proces s i n th e Fayettevill e region
. Th e Delegatio n rcspectfiilly ask s tha t th e highes t

consideratio n i s given t o th e Fayettevill e Regiona l Airport' s grant

appUcation i

n orde r t o improv e acces s t o Washington , D C fo r th e benefit

o f military , busines s an d leisure traveler s alike
. Sincerely , Representativ e Ric

k Glazier , Chair Representativ e Elmer

Floyd , Vic e Chair Representativ e Marvin Luca s Representativ e Dian e Parfit t Senato r Margaret H
. Dickson Representativ e Willia

mBrisson Senato r Larr y Sha w
Statement of the Air and Radiat ion Management Administration Department of the Environment for the Public Hearing Relating to Proposed Amendments to Regulation .13 Drum and Pail Coating under COMAR 26.11.19 Control of Volatile Organic Compounds from Specific Processes held on February 15, 2011 Baltimore, MD

My name is Husain Waheed. I am a Senior Regulatory and Compliance Engineer with the Regulation Development Division of the Ai r and Radiation Management Administration, Department of the Environment.

This public hearing is being held pursuant to the requirements of 40 CFR Section 51.102

and Sections 2-301 et.seq. of the Environment Artic le, Annotated Code of Maryland. It is also being held in conformance with the State Administrative Procedures Act under the State Government Article, beginning at Section 10-101.

Notice of this hearing appeared in the:

Maryland Register on January 14, 2011; MDE's website from January 11, 2011 through February 16, 2011; Baltimore Sun on January 14, 2011; Washington Post on January 13, 2011; and the St. Mary’s Enterprise on January 14, 2011. Copies of these notices were submitted for the record.

Copies of the proposed action and supporting documents were submitted for review to the State Clearinghouse and are also submitted at this time into the hearing record. Copies were also made available for public inspection at th e Air and Radiation Management Administration offices in Baltimore, Cumberland, and Salisbury, and at all local health departments or local air quality control offices.

The purpose of today's hearing is to give the public an opportunity to comment on the proposed amendments to Regulation .13 under COMAR 26.11.19.

Summary

COMAR 26.11.19.13 amendments are proposed to set VOC coating standards for exterior and interior coatings for new and reconditioned drums and pails in the range of 2.8 to 4.2 lbs/gal and require higher efficiency application methods.

Maryland’s State Implementation Plan (SIP)

These amendments will be submitted to the EPA for approval as part of the SIP.

Consideration of Comments

The Department will consider all comments before making a decision to adopt these

1amendments.

2