and i-ces eco pyri sections figurE a-ppendices.gI

Ls refere~ncesec

.g.

A~. .4

IS.I or e

)ssarihap . t

:ables figures .titk

bibliographieso4

* S . g *

, i~

'f;

.4 ,

Ir - ,. , , tr-,,,,
: -. AVAILABILITY NOTICE

Availability of Reference Materials Cited in NRC Publications

NRC publications in the NUREG series, NRC regulations, and Title 10, Energy, of the Code of Federal

Regulations, may be purchased from one of the following sources:

1. The Superintendent of Documents

U.S. Government Printing Office

PO. Box 37082

Washington, DC 20402-9328

<http://www.access.gpo.gov/su docs>

202-512-1800

2. The National Technical Information Service

Springfield, VA 22161-0002

<http://www.ntis.gov/ordernow>

703-487-4650

The NUREG series comprises (1) brochures

(NUREG/BR-)000q, (2) proceedings of conferences (NUREG/CP-xXXX), (3) reports resulting

from international agreements (NUREG/IA-)0000,

(4) technical and administrative reports and books

[(NUREG-)0000 or (NUREG/CR-X)J0C)], and (5)

compilations of legal decisions and orders of the

Commission and Atomic and Safety Licensing

Boards and of Office Directors' decisions under

Section 2.206 of NRC's regulations (NUREGX000 .

A single copy of each NRC draft report is available

free, to the extent of supply, upon written request

as follows:

Address: Office of the Chief Information Officer

Reproduction and Distribution

Services Section

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

E-mail: <DISTRIBUTION@nrc.gov>

Facsimile: 301-415-2289

A portion of NRC regulatory and technical information is available at NRC's World Wide Web site:

<http://www.nrc.gov>

All NRC documents released to the public are available for inspection or copying for a fee, in paper,

microfiche, or, in some cases, diskette, from the

Public Document Room (PDR):

NRC Public Document Room

2120 L Street, N.W., Lower Level

Washington, DC 20555-0001

<http://www.nrc.gov/NRC/PDR/pdrl.htm>

1-800-397-4209 or locally 202-634-3273

Microfiche of most NRC documents made publicly

available since January 1981 may be found in the

Local Public Document Rooms (LPDRs) located in

the vicinity of nuclear power plants. The locations

of the LPDRs may be obtained from the PDR (see

previous paragraph) or through:

<http://www.nrc.gov/NRCfNUREGS/

SR 1350NV9/lpdr/html>

Publicly released documents include, to name a

few, NUREG-series reports; Federal Register notices; applicant, licensee, and vendor documents

and correspondence; NRC correspondence and

internal memoranda; bulletins and information no:

tices; inspection and investigation reports; licensee event reports; and Commission papers and

their attachments.

Documents available from public and special technical libraries include all open literature items, such

as books, journal articles, and transactions, Federal Register notices, Federal and State legislation,

and congressional reports. Such documents as

theses, dissertations, foreign reports and transla-.

tions, and non-NRC conference proceedings may

be purchased from their sponsoring organization.

Copies of industry codes and standards used in a

substantive manner in the NRC regulatory process

are maintained at the NRC Library, Two White Flint

North, 11545 Rockville Pike, Rockville, MD

20852-2738. These standards are available in the

library for reference use by the public. Codes and

standards are usually copyrighted and may be

purchased from the originating organization or, if

they are American National Standards, fromAmerican National Standards Institute

11 West 42nd Street

New York, NY 10036-8002

<http://www.ansi.org>

212-642-4900
Preparing NUREG-Series

Publications

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Office of the Chief information Officer

Information Management Division

January 1999

I .

1 .0

NUREG-0650, Revision 2
ABSTRACT

The guidance in this publication is for the

staff and contractors who prepare

manuscripts to be published in the

NUREG series for .the U.S. Nuclear

'Regulatory Commission (NRC). This

Revision 2 to NUREG-0650, "Publishing

Documents in the NUREG Series," is

retitled "Preparing NUREG-Series

Publications." It gives more concise and

up-to-date guidance, including certain

-Internet and World Wide Web addresses.

It. describes how to cite references to

electronic information and, in addition,

refers the NRC staff tobonline 'style

guidance for Web site publishing.

Hii NUREG-0650, Rev. 2
Content of a NUREG-Series Publication

Before you decide to draft a NUREG-series publication, consider whether

your information is appropriate to be published in the NUREG series. Does

the information give-

* support for a regulatory decision;

* results of licensing studies preliminary to licensing actions;

* results of generic regulatory or technical analyses;

* managerial, programmatic, or administrative analyses of interest to the

staff, the industry, and the public;

* research about, or resolution of, a problem of interest to the nuclear

industry at large;

* action plans and guidance for meeting NRC requirements;

* a team report on a specific topic; or

* proceedings of a conference or workshop?

Legally binding regulatory requirements are stated only in laws; NRC

regulations; licenses, including technical specifications; or orders. Although

the NRC staff may suggest a course of action in a NUREG-series publication,

these suggestions are not legally binding and the regulated community may

use other approaches to satisfy regulatory requirements. Only unclassified

information is published in this series.
CONTENTS

Page

ABSTRACT ...................................... iii

1 INTRODUCTION . 1

1.1 Objectives of These Guidelines .....................................-. 1

1.2 Publishing Policy .................................... - 1

1.3 Publishing Services. 1

2 TYPES OF PUBLICATIONS . .......................--. 3

2.1 Reports................. .3.......- 3

2.2 Brochures .................... '. 3

2.3 Conference Proceedings .. .................... . 3

2.4 International Agreement Re'ports ........................................ :. 3

2.5 Books ................. ;.-.-. 3

2.6 Report Designators 3................. 3

3 PLANNING YOUR DOCUMENT.. ......... 5

3.1 Electronic Submission of Manuscripts. . . 5

3.2 Metrication. . . 5

3.3 Consistency. . . 5

3.4 Page Format.. 6

3.5 Visual Material. . . 6

3.5.1 Selecting and Preparing Visuals .. 6

3.5.2 Style.. 6

3.5.3 Color .. 7

3.6 Guidelines for Figures ....................... .. 7

3.7 Guidelines for Tables. . . 8

3.8 Copyright Clearance. . . 8

3.9 Patent Clearance. . . 9

3.10 Security Clearance. . . 9

4 GENERAL FORMAT AND CONTENT .... 17

4.1 Front Matter 17

4.1.1 Cover ...... 17

4.1.2 AvailabilityNotice . ........................ 18

4.1.3 Title Page ....................... 18

4.1.4 Previous Reports in Series .............................. ;.;.. 18

4.1.5 Abstract .. ' i8...... 

v NUREG-0650, Rev. 2
4.1.6 Contents ............................................ 19

4.1.6.1 Figures ............................................ 19

4.1.6.2 Tables ............................................ 19

4.1.7 Executive Summary .......................................... 19

4.1.8 Preface ............................................ 19

4.1.9 Foreword ............................................ 19

4.1.10Acknowledgments ............................................ 20

4.1.11 Abbreviations ........................................... 20

4.1.12 Symbols ........................................... 20

4.2 Body of the Report ............................................ 20

4.2.1 First Section ........................................... 20

4.2.2 Subsequent Sections .......................................... 20

4.2.3 Findings, Conclusions, and Recommendations ........ ............ 20

4.2.4 References ............................. 21

4.2.4.1 Generic Information for Reference Citations ...... ......... 21

4.2.4.2 Reference Citations for Electronic Information ..... ........ 22

4.2.4.3 Identifying References in Text .......... ................. 22

4.2.4.3.1 Printed Documents .......... ................... 22

4.2.4.3.2 Electronic Documents ........... ................ 23

4.3 Back Matter .................... ....................... 23

4.3.1 Bibliography ........................................... 23

4.3.2 Glossary .............................. 23

4.3.3 Appendix .............................. 24

4.3.4 Index ............................... 24

5 PUBLISHING FORMS ............... 35

Appendix

SAMPLE REPORT .42

Figures

3.1 Sample Style Sheet .10

3.2 Sample Photograph .11

3.3 Sample Map .12

3.4 Sample Figure Denoting Size of Object .13

3.5 Sample Figure with Legend .14

3.6 Sample Table .15

NUREG-0650, Rev. 2 vi
3.7 Sample Copyright Permission Letter ............ ................. 16

4.1 Sample Contents ........................ 26

4.2 Sample List of Abbreviations ........................ 27

4.3 Sample List of Symbols ........................ 28

4.4 Sample List of References: Listed Alphabetically by Author or

Corporate Author ........... 29

4.5 Sample List of References: Listed Numerically as Referred to in Text ........... 31

4.6 Sample Bibliography . .................................................. 32

4.7 Sample Glossary ....................................................... 33

5.1 NRC Form 335, "Bibliographic Data Sheet" ............. ..................... 36

5.2 Sample Completed NRC Form 335 ........... ............................ 37

5.3 NRC Form 426, 'Authorization To Publish a NUREG-Series Document

Prepared by the NRC Staff" ... ............................................ 38

5.4 Sample Completed NRC Form 426 ........... ............................ 39

5.5 NRC Form 426A, 'Authorization To Publish a NUREG-Series Document

Prepared by a Contractor for the NRC Staff" ............ ..................... 40

5.6 Sample Completed NRC Form 426A .............. ......................... 41

Tables

4.1 Organization and Pagination for a NUREG-Series Report ...... ............. 34

Vil NUREG-0650, Rev. 2
1 INTRODUCTION

1.1 Objectives of These Guidelines

This style guide is for the staff and -

contractors who prepare manuscripts to be

published in the NUREG series for the

U.S. Nuclear Regulatory Commission

(NRC). The objectives of these guidelines

are to-

* improve readability;

* standardize format;

* ensure consistency,

* facilitate information retrieval;

* ensure accuracy of references;

* ensure public availability of

references; and

* ensure that the format is Webcompatible, as necessary.

The guide describes appropriate content

and the scope of information published by the NRC in its NUREG-series publica- tions: technical reports, including those

prepared for international agreements; conference proceedings; books; and a

variety of brochures. Next, it provides essential background information for

planning a publication, such as considering the use of graphics and taking into account

patent clearance, security reviews, and the

need for permission to use copyrighted material. Then, it describes in detail the

common components in agency technical

reports. Finally, it describes the forms

necessary for authorizing publication. The

appendix is a sample manuscript for a

NUREG-series publication.

The NRC staff may access online guidance for preparing manuscripts that will be

coded with hypertext markup language (HTML) for posting to the NRC World

Wide Web (WWW) site at

<http://wwSv.intemal.nrc.gov/NRC

PLAIN/STYLE/WP/index.htm > .

For additional information about

abbreviations, see "NRC Collection of

Abbreviations" (NUREG-0544, Rev. 4).

For NRC editorial style for (1) capital

letters, (2) hyphenation, (3) numbers, (4)

equations, and (5) punctuation, see "NRC

Editorial Style Guide" (NUREG-1379).

1.2 Publishing Policy

The policy governing these publications is

found in the following NRC Management

Directives:

* 3.7 Staff Publications in the NUREG

Series

* 3.8 Contractor-Prepared Publications

in the NUREG Series

* 3.11 Conferences and Conference

Proceedings

If you are not an NRC employee, order

these directives and final NUREG-series

publications by calling the Government

Printing Office (GPO) at 202-512-1800

or sending your order to the WWW

address <http://www.access.gpo.gov/

su docs>. If you are an NRC employee,

call 415-2070 or send your electronic mail

(e-mail) request to <DISTRIBUTION>.

1.3 Publishing Services

For the NRC staff to coordinate the

following services for a NUREG-series

publication, send a message to the

Publishing Services Branch at e-mail

address <pubs>. These services include-

* obtaining a publication designator,

* editing,

* coordinating graphics and

composition,

* approval for use of color,

* manuscript review,

1 NUREG-0650, Rev. 2
Introduction

* publishing and reprinting, and

* distribution.

For the NRC staff to discuss posting a

publication to the WWW site, send a

request by e-mail to <nrcweb>, and check

WWW in Block 5 of NRC Form 426, the

authorization to publish (see Section 5 of

this publication).

The Publishing Services Branch is part of

the Information Management Division in

NRC's Office of the Chief Information

Officer.

NUREG-0650, Rev. 2 2
:2 TYPES OF PUBLICATIONS

The NRC prepares the following types of

publications in its NUREG series:

* reports, including those prepared for

international agreements;

* brochures;

* conference proceedings; and

* books.

2.1 Reports

NRC reports cover a variety of regulatory

and technical subjects of interest to the

staff and the nuclear industry. They include

licensing, research, investigative, and

administrative topics related to the

agency's mission.

2.2 Brochures

Brochures include pamphlets, directories,

handbooks, manuals, procedural guides,

and periodicals, such as newsletters. Some

are intended principally for NRC staff use.

2.3 Conference Proceedings

Conference proceedings are compilations

of formal papers, presentations, and

transcripts from technical conferences,

seminars, or workshops.

2.4 International Agreement

Reports

NRC international agreement reports

result from international information

exchange agreements between the NRC

and foreign governments and

organizations. In these agreements, foreign

participants agree to submit unclassified

nuclear safety information to the NRC for

publication.

2.5 Books

The NRC publishes books to serve a

unique technical purpose or to meet an

industry-wide need. An NRC book is

considered a permanent reference, a

textbook, or a major critical review of a

technical or regulatory topic. Its contents

must be broadly valid and applicable for at

least 5 years after publication. Each book

undergoes stringent peer review.

2.6 Report Designators

Each NRC publication is identified by a

unique alphanumeric designator, for

example, NUREG-1555 or

NUREG/CR-1666. The alpha designation

"NUREG" identifies the publication as an

NRC publication (Nuclear Regulatory); it

is followed by a four-digit number, or it is

followed by two letters further identifying

the type of report and a four-digit number

to form the complete designator.

Publications that the staff prepare bear the

following designators:

NUREG-XXXX for a report or

book;

NUREG/BR-XXXX for a brochure;

NUREG/CP-XXXX for a conference

proceedings;

NUREG/IA-XXXX for a report

resulting from an international

agreement.

Publications that contractors prepare for

the staff bear the NRC designator and

usually bear the contractor's designator

under it as follows:

NUREG/CR--XXXX

ORNL-XXXX

Request the publication designator as close

to the publication date as possible to avoid

3 NUREG-0650, Rev. 2
cumulation of unused designators in our

publications tracking system (see Block 1

on NRC Form 426 or 426A-Figures 5.3

and 5.5 in this guide).

NUREG-0650, Rev. 2 4
3 PLANNING YOUR DOCUMENT

Legally binding regulatory requirements are stated only in laws; NRC regulations;

licenses, including technical specifications; or orders. Although the NRC staff may suggest

a course of action in a NUREG-series publication, these suggestions are not legally

binding and the regulated community may use other approaches to satisfy regulatory

requirements. Only unclassified information is published in this series.

Following guidance .ii this and subsequent

sections, you will ultimately prepare a

camera-ready copy of your.manuscript for

publication.

3.1 Electronic Submission of

Manuscripts

As the age of technology demands

multimedia publishing and electronic

access to publications, we are planning for

submission of manuscripts in both

electronic and hardcopy media. The NRC

prefers that manuscripts for NUREGseries publications be created in

WordPerfect 6.1 or a later version. Our

current agency standard is WordPerfect

8.0. To the extent possible, all visual

material except photographs should be

importable into the WordPerfect file.

These files may be submitted on compact

disk (CD ROM), in a variety of magnetic

media, and over the internet along with

camera-ready copy..

NRC is also beginning to publish its

documents on compact disks (CDs) and

will accept CDs for publication in addition

to camera-ready copy. NRC is still required

by law to publish hardcopy. .

3.2 Metrication,

The NRC Policy Stafement titled

"Conversion to' the Metric System" (57 FR

46202, 10/07/92) states, in part:'

...the NRC will publish...in dual units...

'NUREG-series documents.... In

dual-unit documents, the first unit

presented will be in the International

System of Units with the English unit

shown in brackets.

It goes on to except licensee-specific

documents from the dual-unit system by

stating:

Documents specific to a licensee, such

as inspection reports...will be in the

system of units employed by the

licensee. This protocol reflects a

general approach that only documents applicable to all licensees, or to

all licensees of a given type in which a

licensee may operate in the metric

systemnwill contain dual units,

otherwise English or metric units alone

are permissible.

3.3 Consistency'

If a document is written by multiple

authors, a lead author should review the

entire document to ensure that it is

consistent throughout. The lead author is

the sole contact with the'editor or with

'others involved in producing the

document. The lead auhthor aidbthe editor

should create a one- or two-page document

style sheet (Figure 3.1) for contributing

authors before they begin to write. The

style sheet may include an outline of how

to treat the recurrent features of a-

'!document, such as abbreviations, capital

letters, numbers, hyphens, and reference

citations. Consult NUREG-1379 and

NUREG-0544, Rev. 4, for additional

information. The style sheet may contain

5s NUREG-0650, Rev. 2
Planning Your Document

the following kinds of guidance and is

usually amended as work progresses:

* how to format and identify sections;

* the preferred way to identify licensees,

contractors, and subcontractors;

* the preferred term or terms for

equipment, measurements, personnel

(i.e., job titles), and the like;

* when to use "shall," "must," "should,"

"may," or "may not";

* when to use the present and past verb

tenses;

* how to identify and abbreviate'

procedures referred to in the text; and

* how to cite references.

The sheet may also include any special

instructions to text processing operators

about formatting, version control, coordinating drafts, and handling computer files.

Ensure also that report terminology in the

document is consistent throughout. For

example, do'not refer to the same

phenomenon as a "percentage" in the text

and as a "proportion" in a table or figure.

3.4 Page Format

Single-space the manuscript, leaving

one-inch margins on all sides. Publications

other than reports may have unique

formats (see Section 4). Use two-column

layout except for a report composed

primarily (75 to 80 %) of mathematical

equations, formulae, tables, or visual

material. In these exceptions, prepare a

double-spaced camera-ready copy in

single-column format. Place the complete

NUREG-series designator on the bottom

right-hand 'corner of an odd-numbered

page and on the bottom left-hand'corner of

an even-numbered'page. Place the page

numbers in'the center of each page (see

the pages in the appendix to this guide).

3.5 Visual Material

Tables, graphs, photographs, drawings,

charts,' and maps-often collectively called

visuals-can frequently express ideas'or

convey information that words alone

cannot. Tables allow the easy comparison

of large numbers of statistics that would be

difficult to understand if they appeared in

sentence form. Graphs make trends and

mathematical relationships immediately

evident. And drawings, photographs,

charts, and maps can indicate shapes and

relationships in space more concisely and

efficiently than text alone. See Sample

Figures 3.2 through 3.5 at the end of this

section for illustrations of properly

prepared visuals.

3.5.1 Selecting and Preparing Visuals

When the NRC staff is preparing a

document that includes visual material,

consult the Publishing Services Branch at

e-mail address <pubs> to have an editor

work with you and the Graphics Staff to

determine-

* whether the material meets

publication standards; '

* how to integrate the material in the

text;

I whether the'design of the material is

consistent with the design of the

document; and

* whether the material is in the best

form to convey the intended message.

Edit the visual material against the text in

the document to ensure that the data and

terminology in both are consistent. Prepare

tables using the table feature in word

processing software. Doing so is especially

important for publications that will be

posted to NRC's WWW site.

3.5.2 Style

Use a connsistent style for all the same

components-caption, head, and

NUREG-0650, Rev. 2 6
Planning Your Document

legend-of visual material. For example,

use an initial capital letter for each major

word of the caption or for all axis labels or

an initial capital letter for the first word of

the caption. Whatever your choice, adhere

to it consistently throughout the same

document. Avoid the use of abbreviations

except for measurements. Use the same

font for all figures in the document to the

extent possible.

3.5.3 Color

Visual material must generally be in black

and white or shades of grey because color

printing is significantly more 'expensive;

When the NRC staff wants approval to use

more than'one color for visual material or

any part of the publication, contact the

Publishing Services Branch at e-mail

address <pubs>.'

3.6 Guidelines for Figures,

-Three options are available for preparing

figures: (1) ask the Graphics Staff to

prepare the material; (2) use existing

material; or (3) use computer-prepared

material, printed on a laser printer with a

resolution of no fewer than 600 dots per

square inch (DPI). Follow these guidelines

regardless of how figures are prepared:

* Place a number and caption for each

figure under the figure.

* Number figures consecutively throughout a publication (e.g., Figure 1,

Figure 2) or consecutively within each

section or appendix of a publication

(e.g., Figure 1.1, Figure 2.1 or Figure

A.1, Figure A.2).

* Include a key (legend) that lists and

explains any symbols.

' Refer to the'figure and explain'its'

significance in the text immediately

preceding the figure.''

* Place the figure as close as possible

after its first reference in the text.

* If a report includes five or more

figures, list each figure number, its

caption, and page number under

"Figures" in the "Contents" section.

Figures in an appendix may be listed in

the "Contents"- section for the

appendix.

* Obtain the original or the most

reproducible copy of each figure for

printing. If a figure will not print well,

eliminate it or redo it.

Avoid the use of color if at all possible

to reduce printing costs.

* Use high-contrast, glosssy, clear black

a and white photographs, and submit the

original photographs.

* Indicate the orientation for the

photograph and the relative size of the

significant person or object in the

photograph by'placing a familiar

object, a person, a rule, or a scale, in

the photograph (see Figure 3.4).

Handle an original photograph with

care. Do not draw crop marks on the

original. Instead, make a copy of it,

draw crop marks' on 'the copy, and

submit it with the original for printing.

Do not trim the original to size. Do

not use paper clips without padding or

write on an original figure, a photograph, or an -overlay because either

practice will leave an impression on

the original that may be visible in the

printed publication. Also,'do not fold

or roll a photograph as these practices

will crack the emulsion, and the crack

will be visible after the photograph is

prmted. e. tp orh

* For maps, identify all boundaries

clearly and eliminate unnecessary

boundaries. Include a scale of miles or

7 NUREG-0650,' Rev. 2
Planning Your Document

kilometers to inches to indicate

proportions. Indicate which direction

is north. Show the features you wish to

emphasize by using shading, dots,

crosshatching, or appropriate symbols

when color reproduction cannot be

used. Include a key or legend

identifying the different shadings,

symbols, or colors.used (see Figure

3.3).

3.7 Guidelines for Tables

Use the following guidelines, and see

Figure 3.6 for a sample table:

* Place a number and title for each table

above the table.'

* If a table requires more than one page,

repeat the table number and title,

followed by "(continued)," on each

subsequent page.

* If a report includes five or more tables,

list each table number, its caption, and

page number under "Tables" in the

"Contents." Tables in an appendix may

be listed in the "Contents" for the

appendix.

* Number tables consecutively throughout a publication (e.g., Table 1, Table

2) or consecutively within each section

or appendix (e.g., Table 1.1, Table 2.1

or Table A.1, Table A.2).

* Present data on only one subject in

each table.

* Explain the purpose of the table or the

significance of its information in the

text preceding the table.

at the end of the section in which it is

cited.

3.8 Copyright Clearance

Copyrighted material, either text or visual,

cannot be reproduced in NRC publications

without written permission from the

copyright holder. Figure 3.7 is a sample

letter for requesting such permission.

In accordance with copyright law (17

U.S.C. 101 et seq.), non-Government

publications created after January 1, 1978,

receive copyright protection whether or not

they bear a copyright notice-copyright

notices usually appear on the back of the

work's title page. Therefore, material

drawn from a non-Government publication

is most likely subject to copyright

protection and should not be reproduced

without first obtaining copyright

permission from the copyright holder.

Copyrighted visual material such as a

figure or table also requires permission for

use from the copyright holder. To obtain

permission, send the copyright holder a

copyright permission request letter (see

Figure 3.7) to sign and return before the

document is printed. If the need for

permission is immediate, send the letter by

facsimile and request that the copyright

permission release be returned by

facsimile. The signed letter can

subsequently be mailed.

If permission to reproduce the copyrighted

material is granted, cite the copyright

holder in a source line where the

information is referenced. If the holder

does not request a particular source line,

use the following:

Permission to use this copyrighted

material is granted by (name of

copyright holder).

In accordance with the Fair Use Provision

of copyright law, up to 200 words of

material from a copyrighted work may

. . Place the table as close as possible

after its first reference in the' text.

I . I . .1. .. . .

* If a table is so long that it would

interfere with reading the text, place it

NUREG-0650, Rev. 2 8
Planning Your Document

generally be used without the permission

of or payment to the copyright holder as

long as the use is reasonable and not

harmful to'the rights of the copyright

holder'and as long as the source'is cited.

Contact the NRC's Office of the General

Counsel (OGC) for advice when (1) you

cannot determine who holds the copyright,'

(2) the copyright owner will not grant

permission for reproduction, or (3) you

have any, doubt about using material from

a non-Government work.

In addition, publications that explain the

copyright law in detail are available from

the Copyright Office, Library of Congress,

Washington, DC 20540-0001. The Web

.address is <http:/Ivww.loc.gov>. . i -

Although works published by the U.S.

Government are in the public domain and a;.

are not protected by copyright, an NRCemployee may obtain a private copyright

for a work related to NRC functions that is

not prepared as part of the employee's

official duties. Consult the OGC for a

ruling on whether to seek a private

copyright for a work related to NRC

functions.

'3.9 Patent Clearance .

If a publication involves a patent, consult

the Patent Counsel in the OGC about

obtaining patent clearance and have the

OGC counsel sign and date NRC Form

426, the publication release form (see

Section 5 of this publication).

3.10 Security Clearance

-Request that the Division of Facilities' and

Security, Office'of Administration, review

any document to be published in the

NUREG series that contains or may

contain classified or sensitive unclassified

information.

If a document contains classified

information (Restricted Data, Formerly

Restricted Data, or National Security

Information) or sensitive unclassified

information (Limited'Official Use, Official

Use Only, Proprietary, or Safeguards) that

requires markings, follow the procedures

'for preparing and marking these documents or for reproducing or disseminating

them, if permitted, in accordance with

Management Directive (MD) 12.2, "NRC

Classified Information Security Program,"

or MD 12.6, "NRC Sensitive Unclassified

Information Security Program." Ensure

that an unclassified version of a classified

document receives a securityreview before

it is published. Only unclassified

information is published in the NUREG

series. !

,, . : : .

9 NUREG-0650, Rev. 2
Planning Your Document

STYLE SHEET FOR DEPARTMENT OF ENERGY PILOT PROJECT REPORTS*

VERSION CONTROL SYSTEM: While writing separate sections before you compile the

first complete draft report, label each section Draft 1, 2, and so forth, and date each one

(using the date code feature) so that no confusion arises about which draft is the most

recent. Place this information in a footer on each page. For the complete document, use

the same system applied to control of the separate sections. Using this system will eliminate

the teams reviewing the incorrect draft.

Follow the sample report and draft style guide for (1) formatting; (2) formulating the list of

abbreviations, symbols, and references; (3) referring to references within the text; and (4)

preparing tables and figures.

Create a 5- to 10-page Executive Summary for the report.

Spell out each abbreviation at its first use in each section or appendix.

Request that authors define unusual terms as they write from which you can formulate a

glossary if needed.

Treat each appendix as though it were a standalone document. An appendix may have a

table of contents, list of references, and so forth. Often, a third-party appendix published in

its entirety will include these elements. Appendices may also contain the team's charter,

pc-generated data, or other information.

Use one term consistently for the same object, procedure, or phenomenon throughout,

including in the visual material.

Use "licensee," "position title," or "staff" rather than an individual's name.

Write in the active voice whenever possible (e.g., "The licensee recorded events in the log."

rather than "Events were recorded in the log by the licensee.")

Usually when information is included in a report, events have already transpired and the

past tense works in most constructions (e.g., "The licensee recorded...." rather than "The

licensee records....")

Refer to each table or graph before it is inserted in the document and place it as close to its

first reference as possible. Use the table feature in WordPerfect so that the tables are Web

compatible.

The editor will often amend a style sheet as team work progresses.

Figure 3.1 Sample Style Sheet

NUREG-0650, Rev. 2 10
Planning Your Document

Figure 1.1 An Aerial View af the Millstone Nuclear Power Plant in New London, Connecticut.

I '. ' t ! . ' .- .-

Figure 3.2 Sample Photograph

11 NUREG-0650, Rev. 2
Planning Your Document

-------

A * A

RI

DE

VA MD

4' sin5 

LIII Agreemnt Stats

W,/ NRC Stu Uate ha

*xpmssed hatrtto

sugn Agreements

0

Figure 3.3 Map Showing States That Have Agreements With the NRC

Figure 3.3 Sample Map

NUREG-0650, Rev. 2 12
Planning Your Document

11 II . . , -.1 . . : I 11 ! . - - . . . t -, - , 7 '. 

Figure 2.1 The Portable Alnor Dewpointer, Which Measures the Moisture Content in Gases, Is 10-1/4-

.. Inches Wide. The Opened View Shows a Thermometer on the Left and a Flowmeter on the

Right.

Figure 3.4 Sample Figure Denoting Size of Object

. i 13 NUREG-0650, Rev. 2
Planning Your Docurment

Year

3 Significant Events Safety . 3- .5-

S4 -

2-

z Z

0- 0

Equipmen . Forced Outage Rate (%) . 1000 Comrn

M

IS.0

U. - .X1.5

* 1 IIIIIIlWIl 0 w 0

Year

Collective Radiation Exposure

600- (Person-Centisievert)

egLegend:

~200-

Cdinwdwmyht1uw9

o. iv- D~eeueb 31. tUIK a

Figure 2.1 Performance Indicators - Annual Industi

Figure 3.5 Sample Figure with Legend

ry Averages

NUREG-0650, Rev. 2 14
Planning Your Document

. I ! .".

Table 1. Estimated Emissions from Electric Power Generation

(Tons per Gigawatthour)

Volatile

Sulphur Nitrogen Particulate Carbon Organic

Fuel Dioxide Oxides Matter Dioxide Compounds

Eastern Coal 1.74 2.90 0.10 1,000 0.06

Western Coal 0.81 2.20 0.06 1,039 0.09

Gas 0.003 0.57 0.02 640 0.05

Biomass 0.06 1.25 0.11 0- 0.61

Oil 0.51. 0.63 - 0.02 840 0.03

Wind 0 0 0 0 0

Geothermal 0 0 0 0 0

Hydro 0 0 0 0 0

Solar 0 0 0 0 0

Nuclear 0 0 - 0 - 0 0

aNet emissions.:

Source: Department of Energy - -.- - - .

Figure 3.6 Sample Table

"'15 NUREG-0650, Rev. 2
Planning Your Document

,VA UNITED STATES

0 NUCLEAR REGULATORY COMMISSION

t WASHINGTON, D.C. 20555-10

January xx, xxxx

[Addressee]

Dear_ _

Subject: Request for Permission To Reprint Copyrighted Material

I am preparing a [type of publication] entitled ["title"] for the U.S. Nuclear Regulatory Commission (NRC), which is a

Federal agency. Works prepared and published by the U.S. Government are not copyrighted and are in the public domain.

I would like your permission to reproduce the following material that is to be included in a U.S. Nuclear Regulatory

Commission publication:

Author.

Title and date of publication:_

Selection or illustration: [first and last words if a quotation; figure or page number if an illustrationl

Page _ _ to page

Approximate number of words and pages

The NRC will give full credit to the author and publisher. Please indicate any special wording you may require in a source

line.

If you are not the copyright holder and I need to obtain permission from another source, will you please identify this source.

A release form is provided for your convenience. The duplicate copy of this request is for your files. Should you have any

questions about this request, please call me at [area code-xxx-xxx-xxxx] or e-mail [xxx nrc.govJ.

Sincerely,

Name and Title

For a printed publication

[I or We] grant the NRC permission to use the material as stipulated For posting to the WWW_

for the purposes checked.

Date Signature

Title

Preferred Source Line

Figure 3.7 Sample Copyright Permission Letter

NUREG-0650, Rev. 2 16
4 GENERAL FORMAT AND CONTENT

In preparing most manuscripts for

publication in the NUREG series, adhere

to the following format guidelines.

However, certain staff- and '

contractor-prepared manuscripts, such 'as

safety'evaluations or standard review plans

or environmental impact statements, have

unique formats that are dictated by

licensing guidelines and NRC regulations.

In addition, brochures, conferenceproceedings, international agreement

reports, and books may have unique

formats that differ from the format for''

most other publications. Consult the

Publishing Services Branch at e-maili

address <tubs>'for information about the

format for these documents.-

Organize generic technical reports,

including drafts, usinig only those elements

appropriate to each report. Number the

'pages ~of the report consecutively'

throughout, including appendices. Ensure

that each niew section, or chapter in the

-case of a book, begins on an oddnumbered page. If a report includes a

preprinted appendix from another source,

number each appendix separately,

beginning with A-1, A-2, B-i, B-2, as

appropriate.-Follow the guidance in Table

4.1 at the end of this section.

4.1 Front Matter;

The front matter of a printed version of a

NUREG-serie's pubiication-may include

the cover, the availability notice, the title

page, a list of previous publications in a

series, the abstract, the table of contents,

the executive summary, the preface or

foreword, any acknowledgments, and a list

of abbreviations. Some of these,

components are optional as shown in Table

4.1. If the document is posted to the NRC

WWW site, information from the title page

will appear online in the "Publication

Information" section, and the cover will

not appear.

4.1.1 Cover

The Publishing Services Branch creates, or

has designed, the cover for most

publications in the NUREG series.

Staff Report: Supply the Publishing

Services Branch the following information

for the cover: (1) full title; (2) subtitle, if

'any; (3) type of report (e.g., draft,-final,

annual, team); (4) sponsoring office; and

(5) report number-obtain from the

Publishing Services Branch (see Block 1 in

Figures 5.3 and 5.5).

Contractor Report: Supply the Publishing

Services Branch the following information

for the cover: (1) full title; (2) subtitle, if

any, (3) type (e.g., draft, final, annual,

team); (4) contractor; (5) report number-

,.obtain from the Publishing Services Branch

(see Block 1 in Figures 5.3 and 5.5); and

(6) secondary contractor report number.

Omission of any of this information will

delay publication.

Title of Report: Select a succinct title-that

is specific to the topic and that suggests the

report's scope. Suchl a title' helps a

prospective user decide whether the topic

is of sufficient'interest or importance to

read the abstract, executive summary, or

the entire report. If the report covers a

specific period,'such as a month, quarter,

or year, include this fact in the title or in a

subtitle.

Example:

- Enforcement Actions: -Significant

Actions Resolved (Title),

-Quarterly Report for July-September

1997 (Subtitle)

17 NUREG-0650, Rev. 2
General Format and Content

Do not include in the title-

* the name of an NRC office;

* the word "report" or "technical

report," which is self-evident;

* abbreviations.

Good example:

Response Capabilities of Local Law

Enforcement Agencies

Poor example:

Office of Nuclear Reactor Regulation

Technical Report on LLEA Response

4.1.2 Availability Notice

The Publishing Services Branch inserts the

appropriate availability notice for each

publication. An availability notice lists the

publicly available sources of information

cited in reference lists and bibliographies

in NRC publications. These sources may

include the WWW or Internet sources in

addition to traditional sources for paper

copies.

4.1.3 Title Page

The Publishing Services Branch creates, .or

has designed, the title page for most

publications in the NUREG series.

Staff Report In addition to the

information supplied for the cover, supply

the (1) manuscript completion date,

(2) desired publication date, and (3) the

name of the division authorizing

publication of the report.

Contractor Report: In addition to the

information supplied for the cover, supply

the (1) manuscript completion date;

(2) NRC job code number (JCN), and (3)

the complete mailing address for the

contractor and any subcontractor.

Omission of any of this information will

delay publication.

4.1.4 Previous Reports in Series

If the report being prepared is one in a

series, list all previous reports in the series

on a separate page or several pages, if

necessary. Include the complete report

designator (volume, number, and revision,

if applicable) and the issuance date for

each report in the series.

4.1.5 Abstract

The abstract is a concise summary of the

report. This summary should be sufficient

in scope to enable readers to decide

whether to read the full work. Limit the

abstract to a single paragraph of 200 or

fewer words.

To prepare an abstract-

* Begin with a sentence that states the

report's main thesis; do not merely

rephrase the report's title.

* Summarize several major findings or

points.

* To help you limit the length of the

abstract-

- Use the active rather than the

passive voice wherever possible

(e.g., "The licensee identified

three deficiencies," rather than

"Three deficiencies were

identified by the licensee."

- Use the passive voice only to

emphasize the object or recipient

of the action when either is more

important than the doer;

* Use the third person: "the staff" or

"the author," rather than "we" or "I."

* Avoid the use of unfamiliar terms,

abbreviations, or symbols. If any are

NUREG-0650, Rev. 2 18
General Format and Content

included, define them the first time

they occur.

Avoid the use of equations and

formulas unless the abstract cannot be

understood without them.

Cite any computer code central to the

Itopic of the report. Describe aresearch technique or data source only

'to the degree necessary.

* Avoid mentioning tables, figures, or

- references unless the abstract cannot

be understood without them.

4.1.6 Contents

List the title of each section and subsection

and the page number on which it begins to

the third level of subordination (1., 1.1,

1.1.1). List appendices, figures, and tables

as part of the Contents (Figure 4.1).

Ensure that the page numbers and the

section titles in the contents match those in

the report. In the HTML version, link each

title to the appropriate section; page

numbers are unnecessary.

4.1.6.1 Figures

If five or more figures appear in the body

of the report, list the figure numbers;

captions, and page numbers in sequence in

the Contents. Fewer than five figures may

be listed. Ensure that the figure numbers

and captions match those in the report. In

an HTML version, link in sequence each

figure and title to the appropriate figure;

page numbers are unnecessary. ''

4.1.6.2 Tables

If five or more tables appear in the body of

the report, list the table numbers, titles,

and page numbers in the Contents. Fewer

'than five tables may be listed. Ensure that

the table numbers and titles match those in

the report. In an HTML version, link each

table number to the appropriate table;

page numbers are unnecessary.

4.1.7 Executive Summary

An executive summary is optional. This

summary is more complete than an

abstract. It (1) states the purpose of a

report, (2) gives a brief account of the

procedures or methodology used,

(3)' includes a concise overview of the

document, and (4) gives major findings,

conclusions, and recommendations. This

summary is usually 5 to;10 pages,.

depending on the scope and complexity of

the report. Longer summaries tend to

defeat the purpose of allowing a reader to

glean the crux of the report from the

summary and determine whether to peruse

certain sections or the entire report.

4.1.8 Preface

-The preface is an optional introductory

statement, usually written by the author,

*that announces the' purpose, background,

and scope of the report. Sometimes the

preface specifies the audience for whom

the report is intended or highlights the

relationship of the report to a given project

or program. A preface may also

acknowledge assistance received during the

project or while preparing the report: If the

report does not require a preface, place

this type of information, if it is essential, in

the introductory section. The author's

name may or may not appear at the end of

the preface. -'

4.1.9 ForewordaI;'

A foreword is an optional introductory

statement written by someone other than

the author. The writer of the foreword is

usually an'authority in thelfield, whose

name and affiliation and the date the

statement was written appear at the end of

the foreword. The author of the foreword

may also be a senior official of the

19 NUREG-0650, Rev. 2
General Format and Content

organization sponsoring or funding the

publication. The foreword provides

background information about the study's

significance or its relationship to other

works written in the field.

4.1.10 Acknowledgments

An acknowledgments section, which is

optional, gives credit to any persons or

groups who assisted in preparing and

producing the publication.

4.1.11 Abbreviations

The list of abbreviations in a document

includes initialisms and acronyms and may

include units of measurement (Figure 4.2).

This list usually appears as the last section

of the front matter, unless it is followed by

a list of symbols, or the list may appear as

an appendix. An acronym is a pronounceable term formed from the initial letters of

a compound expression (e.g., LOCA for

loss-of-coolant accident). An initialism is a

nonpronounceable term formed from the

initial letters of a compound expression;

the initial letters are pronounced as

separate letters (e.g., NRC for the Nuclear

Regulatory Commission).

4.1.12 Symbols

The list of symbols includes any printed or

written sign used to represent an

operation, an element, or a quantity,

quality, or relation, as in mathematics. This

list appears as the last section of the front

matter or as an appendix (Figure 4.3).

4.2 Body of the Report

Organize the text of the report so that

readers understand the subject and the

scope of information it will cover; the

details and their relationships; and, finally,

any findings, conclusions, and

recommendations.

4.2.1 First Section

In the first section, often called the

Introduction, indicate in a concise manner

the subject and purpose of the report, the

scope of information covered, and the

methodology used in analyzing the subject.

State why the report was written. Define

the limitations and boundary conditions

explicitly so that the reader is able to

ascertain quickly what the report does and

does not do. To illustrate, for an inspection

report, specify the areas or systems

inspected.' Describe the contents of each

subsequent section and each appendix in

no more than one sentence for each.

4.2.2 Subsequent Sections

Include a title and an introductory

paragraph for each major section. Indicate

in the introductory paragraph the material

covered in that section and the relationship

of this material to the overall report.

4.23 Findings, Conclusions, and

Recommendations

Findings provide the bases for conclusions

and recommendations. Nothing should

appear as a conclusion or a

recommendation unless the basis for it was

provided elsewhere in the report.

Conversely, significant findings in the

report are reflected in the conclusions and,

where appropriate, are the bases for

recommendations.

Distinguish clearly between findings and

conclusions, especially in inspection,

investigatory, and research reports:

* Afinding is information obtained

during the inspection, investigation, or

research. For example, a piece of

equipment failed; its failure caused the

loss of a system; plant operators'did

not respond quickly to the system

failure; procedure manuals do not

NUREG-0650, Rev. 2 20
- General Format and Content

address this specific sequence of

events.

A conclusion is a'judgment based on

the significance or implications of a

finding. For example, plausible

conclusions that follow from the

foregoing findings are that the

equipment failed because of poor

maintenance, that the maintenance

program has weaknesses, and that

operators were not properly trained to

respond to the sequence of events that

occurred.

* A recommendation suggests a course of

action on the basis of one conclusion

or a set of conclusions. For example,

the maintenance program should be

.improved, the procedures should be

revised, and operators should be

trained in the new procedures.

4.2.4 References

A list of references gives each source of

information used to prepare the

publication that is identified in the text

(compare with Section 4.3.1). A number of

systems for reference style are available.

To name a few, acceptable style guides are

published by the University of Chicago,

Modem Language Association of America,

American Institute of Physics, American

Psychological Association, and the

American Mathematical Society. Although

a variety'of styles is available, NRC has

adapted a style similar to that of the

American Psychological Association's

Publication Manual. Using the adapted

style, list the references in one of two ways

as illustrated in Figures 4.4 and 4.5:

1. alphabetically by author and corporate

author or

'2. numerically in'the sequence they are

referred to'in the text.

Select one way, and use it consistently

throughout a single document or a

collection of related documents.

4.2.4.1 Generic Information for Reference

Citations

Each reference must include sufficient

information for the reader to find it, as

follows:

* author: individual, agency,

corporation, or association;

* title: italicize the title of a book; place

the title of a journal article or the'

chapter of a book in quotation marks;

place the title of a journal article

before the italicized name of a journal;

and enclose in quotation marks the

title of a technical report, such as a

NUREG-series report, a regulatory

guide, an industry code, or an industry

standard;

* volume, if needed, or report number;

publisher and location; and

* date.

Basically, the elements of each reference

citation are arranged as follows:

(1) author; three or fewer authors are

listed by last name and two initials, if

available; and, if the work has more than

three authors, follow the first author with

et al.; (2) titles, using initial capital letters

for principal words; (3) location of the

publisher; (4) publisher; (5) in the case of a

journal article, volume and page numbers,

or in the case of a report, its number; and

(6) date. Items (3) and (4) are separated by

a colon; all other items are separated by

periods.

Each reference listed in an NRC publication must be publicly available. Do not

include documents from the Institute of

Nuclear Power Operations (INPO) as a

21 NUREG-0650, Rev. 2
General Format and Content

reference or discuss INPO documents in

the publication without INPO's express

permission.

4.2.4.2. Reference Citations for Electronic

Information

A number of styles for citing'electronic

information and verifying the information's

source are available online and in

hardcopy. One useful guide is Electronic

styles: A Handbook for citing electronic

information (1996), by Information Today,

Inc. <http://www.uvm.edu/- ncrane/

estyles/>.

For citing a document at a WWW site, use

the following format:

* author's name (if known)

* title of document in quotation marks

* title of complete work (if applicable),

in italics

* date of publication or last revision (if

known)

* uniform resource locator (URL), in

angle brackets

* dite of access, in parentheses

Example:

U.S. Nuclear Regulatory Commission,

"United States Nuclear Regulatory

Commission 1997 Information Digest."

1997. <http:/iww.nrc.gov/NUREG/

SR1350/ V9/indexhtml> (18 February

1998).

For citing an E-mail Message, use the

following format:

* author's name (if known)

* author's e-mail address, in angle

brackets

* subject line from posting, in quotation

marks

* date of transmission

* type of communication (personal

e-mail; distribution list, including

listserv; office communication)

* date of access, in parentheses

Example:

Malliakos, Asimios. <ACM1@nrc.gov>

"NUREG/IA-0010-Reply" 7 January

1998. [office communication]. (9

January 1998).

4.2.4.3 Identifying References in Text

4.2.4.3.1 Printed Documents

* If listing references numerically,

identify them in text in one of the

following ways:

- Capitalize and spell out the word

reference if it is part of a sentence:

"As indicated in Reference 1, each

organization develops its own

identity, often unrecognized."

- For a single reference, place in

parentheses at the end of the

statement the abbreviation for the

word reference and the reference

number:

"Organizations change their

identity over time (Ref. 1)."

- For multiple references, place in

parentheses at the end of the

statement the abbreviation for the

word references and the reference

numbers:

"To identify your type of organization, consult the guidance in one

of the NRC-endorsed standards

(Refs. 1, 3, and 6)."

NUREG-0650, Rev. 2 22
General Format and Content

* If listing references by author, use this

format:

"Members of an organization are

usually not conscious of its identity

(Diamond, 1987)."-

* If listing several references by one

author, identify them first by date, and

then by date and lowercase letter if the

date would not distinguish one

reference from another:

"Is it helpful for executives to recognize their organization's identity

(Diamond, 1987)"

"Most human resource organizations

agree that an executive should know

the organization's identity (Diamond,

1987, 1988a,1988b)."

* If listing references by organization,

use this format:

"Performance of deep soil foundations

under seismic loading is described in

ASCE Geotechnical Special'

Publication 51."

4.2.4.3.2 Electronic Documents

Identify electronic sources in text much as

you would printed sources,- referring to the

author or title of the source followed by

the year.

* To introduce a brief quotation or

- paraphrase or summarize material, use

either a signal phrase set off by a

comma or a signal verb with a "that..."

clause. -;

*Examples:

According to the U. S. Nuclear

Regulatoy Commission (NRC,1997),

110 commercial nuclear power reactors

were licensed to operate in 32 States in

1996.

NRC (1997) stated that it assesses;

approximately 1700 reports of reactor

events a year.

Documents posted to the WWW are not

paginated; therefore, to reference a

particular section of an electronic

document, substitute the name of a section

of text for the page number you would

generally include for a printed document.

Example:

The Radioactive Waste Section (1997)

states that NRC classifies low-level

waste on the basis of its potential

hazards as Class A, B, or C, Class A

containing the lowest concentrations of

radioactive material.

4.3 Back Matter

For NRC publications, back matter may

include a bibliography, a list of references,

a glossary, one or more appendices, and a

subject index.

43.1 Bibliography

A bibliography is a list of publications and

other materials (e.g., WWW source,

unpublished theses) used by the author to

prepare a report. It diffeis from a

reference list in that it lists all research

sources used to prepare the document,

including those specifically identified in the

text and included ini the list of references.

In other words, a bibliography is a

supplement to a list of references (see

Section 4.2.4). As with entries in the list of

References, separate the location of the

pubisher and the publisher with a colon

and all other items by a period (Figure

4.6). -. .

43.2 Glossary

A glossary defines terms that may be

unfamiliar to the intended audience.

:; 23 NUREG-0650, Rev. 2
General Format and Content

Arrange the terms alphabetically,

beginning each new entry and its definition

on a new line (Figure 4.7).

4.3.3 Appendix

An appendix includes information that is

supplemental to the publication, such as-

* explanatory or supportive information

not essential to the text,

* long charts, tables, or computer

printouts,

* a chronology,

* a bibliography,

* a glossary,

* a list of references,

* a list of abbreviations, or

* a list of symbols.

Identify each appendix with a heading and

title (e.g., Appendix A, "Burial Site Price

Schedules for the Current Year"). A single

appendix is not assigned a letter or number

while each appendix in a report having

more than one appendix receives a

designator such as Appendix A, Appendix

B or Appendix 1, Appendix 2, and so forth.

Ensure that references in the text to

Appendix A come before references to

Appendix B, and so forth. Provide a table

of contents for a lengthy appendix. Treat

each appendix as a stand-alone document,

making it clear and complete. Prepare a

list of abbreviations, symbols, or

references, as appropriate.

43.4 Index

An index lists all pertinent topics discussed

in the publication in alphabetical order and

cites the page number where each topic

can be found within the text. The index is

always the last section of a report. Divide

the index entries into headings that specify

particular subjects discussed within the text

and give their page references. A complete

entry consists of the principal entry,

subentries, and cross-references, if any.

Place each entry on a separate line as

indicated in the following example:

Principal entry:

Monitoring programs, 27-49

Subentries:

aquatic, 42

ecological, 40-49

meteorological, 37

radiological, 30

terrestrial, 41, 43-44

thermal, 27

Cross-reference:

See also Programs

Cross-references in the index are devices

inserted at appropriate places to guide the

reader to the complete information in the

text. They consist of two general kinds:

"See" references and "See also"

references. Use "See" references-

* when the indexer has chosen among

several key words:

- Economic costs

- See Benefit-cost analysis

* when the subject has been treated as a

subentry to a principal entry:

- Radiological impacts

- See Environmental effects of

station operation, radiological

impacts

* when the reference represents a

popular or shortened form of a term,

not the official, scientific, or full form:

China syndrome

- See Reactor core meltdown

NUREG-0650, Rev. 2 24
General Format and Content

Use "See also" references when additional 0

information can be found in another'entry - ; ,

or subentry:

Ecological programs, 40-49

- See also Monitoring programs

. ,

.. 25 NUREG-0650, Rev. 2
General Format and Content

CONTENTS

Page

Abstract...................................................................... iii

Executive Summary . ............................................................ vii

Abbreviations ................................................................. ix

1 Objectives ................................................................ 1

2 Relay Selection Basis ...................................................... . 3

3 Experimental Arrangement ................................ . 7

3.1 Relay Aging Procedures ............. ................................... 7

3.2 Relay Fire Testing ................. .................................... 9

4 Experimental Results ....................................................... 11

5 Conclusions ............................................................... 19

6 References ............................................................... 21

Appendices

A Temperature Exposure Plots for All Relays Tested ............................... 23

B Glossary G .................................................................. 35

Figures

1 Schematic of a Typical Armature Style Relay ................................... 4

2 Measurement Schematic for Each Contact Pair ................................. 7

3 Severe Combined Environments Test Chamber ................................. 12

4 Temperature Exposure Profiles .............................................. 15

5 Relay with Contact Stuck by Melted Contact Carrier ............................ 20

Tables

1 Relay Identification Scheme ............... .................................. 5

2 Overall Relay Test Results .............. .................................... 10

3 Temperatures Used With Each Experiment .................................... 11

4 T1ypes of Test Chambers ................ ..................................... 18

5 Types of Contact Pairs .................. .................................... 19

Figure 4.1 Sample Contents

NUREG-0650, Rev. 2 26
General Format and Content

ABBREVIATIONS

Al Automated Industries

BNL Brookhaven National Laboratory

CAL Confirmatory Action Letter

CFR Code of Federal Regulations

DOT Department of Transportation (U.S.)

DU depleted uranium

HMR Hazardous Materials Regulation

HMTA Hazardous Materials Transportation Act

IAEA International Atomic Energy Agency

IATA International Air Transportation Association

ICAO International Civil Aviation Organization

IN information notice

KINS Korean Institute of Nuclear Safety

KIT Korean Industrial Testing Company

LCO limiting condition for operation

LOOP loss of offsite power

LP low pressure

MOST Ministry of Science and Technology (Korea)

MOU Memorandum of Understanding

NRC Nuclear Regulatory Commission (U.S.)

NVOCC non-vessel operating common carrier

ORAU Oak Ridge Associated Universities

PPQ plant protection quarantine

PST Pacific Standard Time

RSO Radiation Safety Officer

SG steam generator

SI safety injection

UN United Nations

USCG Coast Guard (U.S.)

USDA Department of Agriculture (U.S.)

WCG West Coast Group

Figure 4.2 Sample List of Abbreviations

27 2 NUREG-0650, Rev. 2
General Format and Content

SYMBOLS

Anmeter

AND gate

Connection

D

No connection

Operational amplifier

OR gate D

Connector K- Oscilloscope os

Current source Resistor AvW

DC Power supply F- Sine-wave generator

Square-wave generator iTh 1Ground

Inductor WE\ Variable resistor

Figure 4.3 Sample List of Symbols

NUREG-0650, Rev. 2 28
- General Format and Content

SAMPLE REFERENCES ,

Statute Administrative Procedure Act, Sec. 6, 5 U.S.C. Sec.-555 (1982),

-22 U.S.C. Sec. 2567 (Supp. 1, 1983).

Book.- three authors - Alekseenko, S. V, V.E. Nakoryakov, and B. G. Pokusaev.

Institute of Thermophysics, Russian Academy of Sciences,

Novosibirsk. Wave Flow of Liquid Films. Fukuoka, Japan:

Begell House. 1994.

Reports: corporate aut

Book: one author

Newspaper article

Federal regulation

Book: committee auth(

Journal article

Book: two authors

E-mail message

hor American Society of Civil Engineers (ASCE). 'Analyses for

Soil-Structure Interaction Effects for Nuclear Power Plants."

Ad Hoc Group on Soil Interaction of the Committee on

Nuclear Structures and Materials of the Structural Division.

ASCE; New York. 1979.

."Performance of Deep Foundations Under Seismic

Loading." Geotechnical Special Publication 51. Proceeding of

sessions sponsored by the Deep Foundations and Soil

Properties Committees of the Geotechnical Engineering

Division. ASCE: New York. 1995.

"Seismic and ...-. Dynamic Analysis and Design

Considerations for High Level Nuclear Waste Repositories."

Subcommittee on Dynamic Analysis and Design of High Level

Nuclear Waste Repositories of the Technical Activities

Division of the Structural Engineering Institute. ASCE: New

York. 1997.

Bradley, D. J. Behind the Nuclear Curtain: Radioactive Waste in

the Former Soviei Union. Richland, Washington: Battelle

Press. 1997.

Broad, W J. ."New Work Proposed for Shuttles: Salvage in

Space." New YorkTi1mes (national edition), pp. B9, B14.

September 16, 1997.

-Code of Federal Regulations, Title 10, Energy, Part 72,

"Licensing Requirements for the Independent Storage of

Spent Nuclear Fuel and High-Level Radioactive Waste."-

or Committee on Innovative Remediation Technologies, National

Research Council. Innovations in Ground Water and Soil .

Cleanup. Washington, D.C.: National Academy Press. 1997.

King, N. "E-Mail Reinvents Itself." Internet World. Vol. 8, No.

11: November 1997.

Lutes, L D. and S. Sarkani. StochasticAnalysis of Structural

and Mechanical Vibrations. Prentice Hall: Upper Saddle River,

New Jersey. 1997.

Malliakos, Asimios. <ACM1@nrc.gov> "NUREG/

IA-0010-Reply" 7 January 1998. (9 January 1998).

I-Figure 4.4 Sample List of References: Listed Alphabetically

by Author or Corporate Author

29 NUREG-0650, Rev. 2
General Format and Content

SAMPLE REFERENCES (continued)

Federal Regster notice

Information: WWW

Reports: Federal Agency

Nuclear Regulatory Commission (U.S.), Washington; D.C.

"Electronic Freedom of Information Act: Implementation."

Federal Register. Vol. 63, No. 12. pp. 2873-2883. January 20,

1998.

Nuclear Regulatory Commission (U.S.), "United States

Nuclear Regulatory Commission 1997 Information Digest."

1997. <http://www.nrc.gov/NUREG/SR1350/V9/indexhtml>

(18 February 1998).

Nuclear Regulatory Commission (U.S.) (NRC). NUREG1568, "License Renewal Demonstration Program: NRC

Observations and Lessons Learned." NRC: Washington, D.C.

December 1996.

-----. NUREG-1612, "Status Report: Reactor Vessel

Integrity Database." NRC: Washington, D.C. July 1997.

-----. NUREG/CR-6451, 'A Safety and Regulatory

Assessment of Generic BWR and PWR Permanently

Shutdown Nuclear Power Plants." NRC: Washington, D.C.

August 1997.

Organisation for Economic Co-operation and Development.

"PSA Based Plant Modifications and Backfits."

OCDE/GD(97)130. OECD: Paris, France. 1997.

Proceedings of an International Conference on Radiation and

Society. "Radiation and Society: Comprehending Radiation

Risk." International Atomic Energy Agency (IAEA), Paris

24-28 October 1994. IAEA: Vienna, Austria. 1997.

Information Infrastructure Task Force: Intellectual Property

and the National Information Infrastructure, The Report of

the Working Group on Intellectual Property Rights.

"Managing Rights in Protected Works." U.S. Patent and.

Trademark Office: Washington, D.C. September 1995.

Chief Financial Officers Act of 1990, Pub. L. 101 -576, 104

Stat. 2838 (1990).

Report: foreign organization

Conference proceedings

Team report

Public Law Statutes at Large

Figure 4.4 Sample List of References: Listed Alphabetically

by Author or Corporate Author

NUREG-0650, Rev. 2 30
General Format and Content

SAMPLE REFERENCES

1. Diamond, M. A. The Unconscious Life of Organizations, Interpreting Organizational Identity.

Quorum Books: Westport, Connecticut. 1993.

2. Lutes, L. D. and S. Sarkani. StochasticAnalysis of Structural and Mechanical Vibrations.

Prentice Hall: 'Upper Saddle River, New'Jersey. 1997.

3. Proceedings of an International Conference on Radiation and Society. "Radiation and

Society: Comprehending Radiation Risk," International Atomic Energy Agency (IAEA), Paris

24-28 October 1994. IAEA Vienna,Austria.' 1997.

4. Turner, D. B. Workbook ofAtmospheric Dispersion Estimates: An Introduction to Dispersion

Modeling, Second Edition with Floppy Diskette. Lewis Publishers: Ann Arbor, Michigan. 1997.

5. King, N. "'E-Mail Reinvents Itself," Internet World, Vol.8, No.11. November 1997.

6. Halmshaw, R. Introduction to the Non-Destructive Testing of Welded Joints, Second Edition.

-Abington Publishing: Cambridge, England. 1996.

7. Terzaghi, K, R. B. Peck, and G. Mesri. Soil Mechanics in EngineeringPractice, Third Edition.

John Wiley & Sons, Inc.: New York. 1996.

8. Alekseenko, S. V., V. E. Nakoryakov, and B. G. Pokusaev. Institute of Thermophysics, Russian

Academy of Sciences, Novosibirsk. Wave Flow of Liquid Films. Begell House: Fukuoka,

Japan. 1994.;

9. Bradley, D. J. Behind the Nuclear Curtain:Radioactive WasteManagement in theFormerSoviet

Union. Battelle Press: Richland, Washington. 1997.

10. Administrative Procedure Act, Sec. 6, 5 U.S.C. Sec. 555 (1982), 22 U.S. C. Sec. 2567 (Supp. 1,

1983).-

11. Reagan, S. B., et al. Writing from A to Z: The Easy-to-Use Reference Handbook Mayfield

Publishing Company: Mountain View, California. 1994.

12. AIred, G. J., W E. Oliu, and C T. Brusaw. The Professional Writer, A Guide forAdvanced

Technical Writing. St. Martin's Press: New York. 1992.

.-. - ,1

Figure 4.5 Sample List of References: Listed Numerically

as Referred to in Text

31 NUREG-0650, Rev. 2
General Format and Content

BIBLIOGRAPHY

Book: three or fewer authors

Translation

Public Law: Statutes at Large

Alred, G. J., W E. Oliu, and C. T. Brusaw. The Professional

Writer, A Guide for Advanced Technical Writing. St. Martin's

Press: New York. 1992. pp. 330-336.

Daudel, R. The realm of molecules McGraw Hill: New York.

1993. (N. Harmann, Transl.). McGraw Hill: New York. 1993

Government Performance and Results Act, Pub. L 103-62,

107 Stat. 285 (1993).

Information Infrastructure Task Force: Intellectual Property

and the National Information Infrastructure, The Report of

the Working Group on Intellectual Property Rights.

"Managing Rights in Protected Works." U.S. Patent and

Trademark Office: Washington, D.C. pp. 191-194. September

1995.

Team report

Journal article King, N. "E-Mail Reinvents Itself." Internet World, Vol. 8, No.

11: pp. 80-95. November 1997.

Directory corporate author Lockheed Martin Corporation. 1996 Directory of Public

Information Contacts. Bethesda, Maryland. 1995

Federal Register notice Nuclear Regulatory Commission (U.S.), Washington, D.C.

"Electronic Freedom of Information Act: Implementation."

Federal Register, Vol. 63, No. 12: pp. 2873-2883. January 20,

1998.

Regulatory brochure Nuclear Regulatory Commission (U.S.), Washington, D.C.

"Instructions for Completing NRC's Uniform Low-Level

Radioactive Waste Manifest" (NUREG/BR-0204, Rev. 1).

Dictionary: single author Pfaffenberger, Bryan, Ph.D. QUE's Computer and Internet

Dictionary, 6h Edition. Que Corporation: Indianapolis,

Indiana. 1995

Conference proceedings Proceedings of an International Conference on Radiation and

Society; "Radiation and Society: Comprehending Radiation

Risk." International Atomic Energy Agency: Paris; 24-28 Sec.

3. October 1994.

Book: More than three authors Reagan, S. B., et al. Writing from A to Z. The Easy-to-Use

Reference Handbook. Mayfield Publishing Company:

Mountain View, California. 1994.

Figure 4.6 Sample Bibliography

NUREG-0650, Rev. 2 32
General Format and Content

GLOSSARY

Activity: a measure of the strength of a radioactive source, measured in units of curies.

Attenuation: reduction of radiation intensity as it passes through any material, for example, lead

shielding.

Background radiation: radiation emitted from naturally occurring radioactive materials in the

earth or from cosmic rays.

Breeder A reactor that produces more nuclear fuel than it consumes. A fertile material, such as

uranium-238, when bombarded by neutr6ns, is trainsfo'rmed into-a fissile'material, such as

plutonium-239, which can be used as fuel..

Byproduct material: radioactive material obtained as a byproduct from nuclear reactors.

Critical mass: The smallest mass of fissionable material that will support a self-sustaining chain

reaction.

Cytogenic evaluation: the study of blood cells to determine chromosomal aberrations induced by

radiation exposure.

Decommission: The process of closing down a facility followed by reducing residual radioactivity to

- a level that permits the release of the property for unrestricted use (see 10 CFR 20.1003).

Geiger-Mueller counter a gas-filled radiation-detection device that is highly sensitive.

Gray: the International System unit of absorbed dose. One gray is equal to an absorbed dose of

one Joule per kilogram (100 rads) (Gy).

Hot Cell: a shielded box or enclosure for sorting, processing, manufacturing or testing radioactive

materials that must be handled remotely..

Isotope: One of two or more atoms with the same number of protons but different numbers of

neutrons in their nuclei. Thus, carbon-12,'carbon-13, and carbon-14 are isotopes of the element

carbon, the numbers denoting the approximate atomic weights. Isotopes have very nearly the same

chemical properties but often different physical'propterties (for example, carbon-12 and -13 are

stable; carbon-14 is radioactive).

Labelling: a procedure in which one or'more radioactive atoms are attached to a molecule or

compound in order-to follow the compound or its fraggments through physical, chemical, or

biological processes by observing the radioactivity.

Liquid scintillation counting: the detection of light emissions resulting from the decay of

radioactive material immersed in a special chemical mixture.

7Time and motion study: an evaluation of the proximity and duration that an individual was near a

source of radiation for the purposes of estimating radiation exposure.

Figure 4.7 Sample Glossary

33 33 NUREG-0650, Rev. 2
General Format and Content

Table 4.1 Organization and Pagination for a NUREG-Series Report

Element Page number (Printed Version) Starts on right- or left-hand

page (Printed Version)

Cover None (prepared by NRC) Right

Availability Notice None (inserted by NRC) Left

Title Page None (prepared by NRC) Right

Previous Reports in None (optional ii) Left

Series

Abstract ini Right

Contents v Right

Figures Number consecutively as part of contents

Tables Number consecutively as part of contents

Appendices Number consecutively as part of contents

Executive Summary Small Roman (odd) Right

(optional)

Preface (optional) Small Roman (odd) Right

Foreword (optional) Small Roman (odd) Right

Acknowledgments Small Roman (odd or even) Right or left

(optional)

Abbreviations Small Roman (odd) Right

(optional) .

Symbols (optional) Small Roman (odd) Right

Text (first section of Arabic 1 Right

text) Continue consecutive numbering with Begin each section on new rightArabic numerals. hand page.

References Continue consecutive numbering with Right

Arabic numerals.

Bibliography, Continue consecutive numbering with Right

(optional) Arabic numerals.

Index (optional) Continue consecutive numbering with Right

Arabic numerals unless intervening

appendices are numbered independently.

In this case, number consecutively,

beginning with I-1.

NUREG-0650, Rev. 2 34
5U ,LH FORM S!, -

5 PUBLISHING FORMS

The forms described in this section are

7available electronically on the NRC

Informs system. The Publishing Services

Branch will send contractors appropriate

forms upon request (Figures 5.1 through

5.6) Complete and submit them with

camera-ready copy to the Publishing

Services Branch to authorize publication of

a NUREG-series document. These forms

are self-explanatory. Complete an NRC

Form 335 for all publications prepared by

the staff or by contractors except that you

need only complete this form for a -

brochure that will be available to the

public. Some brochures are intended only

for internal NRC use.

-Staff-Prepared NUREG-Series Publication

* NRC Form 426, 'Authorization To

Publish a NUREG-Series Document

Prepared by the NRC Staff"

* NRC Form 335, "Bibliographic Data

Sheet"

Contractor-Prepared NUREG-Series

Publication

* NRC Form 426A, 'Authorization To

Publish a NUREG-Series Document

Prepared by a Contractor for the NRC

Staff'

* NRC Form 335, "Bibliographic Data

Sheet"

For assistance in determining appropriate

NRC-established mailing lists to enter on

NRC Form 426 or 426A, call the

Publishing Services Branch.

35 NUREG-0650, Rev. 2
Publishing Forms

NRC FORM 335 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER I2-891 (AtIgnd bY NRC. Add Vol. Supp_ Rev, NRCMt 1102. nd Addenu.-m Nur.bw, If .yj

3201,3202 BIBLIOGRAPHIC DATA SHEET

(Se ins"tut ion7s on the reverJ

2. TITLE AND SUBTITLE

3. DATE REPORT PUBLISHED

MONTH YEAR

4. FIN OR GRANT NUMBER

5. AUTHOR(S) 6. TYPE OF REPORT

7. PERIOD COVERED aInciuso Dales

N. L H FI-UMINU UOUANIZA I IUN -NIAM ANIU AUDHC t Q1 NttC pfne'O DJof-. olr. UThC of Keo, u. IrmwflMe Mw O onoA rr nr ling ..MO, IfS5 re51ICM pev.',0

awe asd K anwilrn oast. .J

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC. type' Sa*ab as . if oroacWepni.'idrNRCDACjiwd. Officeor Region. U.S Nucdrwceg.dtror CD-WM..

and melting &ddrexJ

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 woft Mr Ara

NT wunu ru .n.r I UIiS rLlF 010f01 Of p.1mm 111*1 .eii 0t ,m.alr,,lr, Ill lUf*lll'f TOO moon., ,Z C 13. AVAILABILITY STATEMENT

14. SECURITY CLASSIFICATION

(rhi* PagJ

I rhi RepoeJ

15. NUMBER OF PAGES

16. PRICE

NRC FORM 33S t2c891

Figure 5.1 NRC Form 335, "Bibliographic Data Sheet

NUREG-0650, Rev. 2 36
Publishing Forms

NRC FOR M US NJCLEAR REGULATORY COMMISSION 1. REPORT NLINSER

(2-MG Asge yNC AddmL vatp. mRev..

not,322 1BIBIUOGRAPHIC DATA SHEET : AddNu abW

NUREGICR-6511, VoL 4

2. TITLE AND SUsTITLEANL-98115

Steam Generator Tube Integrity Program . R . .3. DATE RE3MPUBLISHED

Annual Report MONTH YEAR,

October 1996 - September 1997 January 1999

4. FIN ORGR WtANT NUER

W6487

S. AUTHOR) 6. TYPE OF REPORT

D.R. Diercks, S. Bakhtiarl, KE. Kasza, D.S. Kupperman,. T

S. Majumdar, J.Y. Park, W.J. Shack : - - CeRED cAuau

2~7 < ; <,- *tPERIODCOVERED AnkaoDas

Oct 1996 -Sept. 1997

.PERFMRINGORGANZATION - NA AND ADDRESS (VIO; rp a NReer sIr f U.S. M AwRidm.WedroeI sh mgaknb tab~ ae. d is~~ edJea).

Argonne National Laboratory

9700 South Cass Avenue

Argonne. IL 60439

9~~~~~~~~. --S:NORN NEADAOES~Ah .RAZTO ~e'eeseo~Iokc ~ ~ O~aRg' U. MiA~~ ,: !~

rJ. SPoNSRIN ORGANIZATION NAME AND ADDRESS drC 6 e-ambSo- jc**r ipamtw ARCD*o Ad 0m crROO UAm, wftUs Or -- Cam

and mav d*es.

Division of Engineering Technology

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washinoton. DC 20555-0001

10. SUPPLEMNTARY NOTES = ,

I J. Muscara, NRC Project Manager -' I - '

I M1ABSTRACTt~wwadsarjma) _-

This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube Integrity Program during

the period October 1996 through September 1997.' The program Is divided Into five tasks: (1) assessment of Inspection Reliability, (2) Research on ISI (inervice-Inspection) Technology, (3) Research on Degradation Modes and Integrity, (4) Tube Removals

from Steam Generators, and (5) Program Management Under Task 1, progress Is reported on the assembly of a steam generator tube mockup for round-robin studies and on the evaluation of NDE techniques for characterizing the tubes going Into the mockup. Inspection data from the Duke Power Company's McGuire Nuclear Station were evaluated to optimize the selection of tube

samples for removal from two retired steam generators. Under Task 2, results are reported on the application of signal processing,

visualization, and data analysis schemes to Improve the NDE of service-degraded tubing. Results are also presented on

Implementation of multivariate linear and nonlinear models to study potential correlations between eddy current measurements and

flaw size and tube falure pressure. In Task 3, a model boier mufitube corrosion cracking facility has been designed to simulate

steam generator thermal-hydraulic and chemistry conditions for the tube/crevice chemistry. A Pressure and Leak-Rate Test

Facility Is being built to determine failure pressures and leak rates for flawed tubing under normal operating and design-basis

accident conditions. An autoclave system and a room-temperature cracking facility are being used to produce cracked specimens

for pressure and leak-rate tests and NDE studies. The results of 15 severe-accident pressure tests on Aloy 600 tubing with

machined circumferential part-throughwal flaws are also reported.' Under Task 4, the selection and removal of service degraded tubes, tube sheet samples, and tube support-plate samples from the McGuire Nuclear Station are described.

12. KEY wORDSDESCRMPORS -W. wad b crpr< uhiuwassareude*enw hbceig , m tJ 13. AVALABLY STATh~EM

Steam Generator . - . - ..Tubes 14. SECtOWN ASWAN

Stress Corrosion Cracking - . - ' ' G.)

Eddy Current Testing Uncsasified

Nondestructive Evaluation .Tw .a_

In-service Inspection _ ' Undassifed

Pressure Testing - 1

Tube Burst 15. NUWBER OF PAGES

Laek Rate

Alloy 600, Inconel 600 16. PRICE

.,. F.R .'5 -~ ,.r .. --. mcl ,.,ue .y ,., .. d.s Fr,. h ,... . .. ,.... ..

MC FORM = C2-W , , - I . . 1 . ., . hs rm sI , .. ey~u~bE Fdw Fmkr

Figure 5.2 -Sample Completed NRC Form 335

37 NUREG-0650, Rev. 2
Publishing Forms

NRC FORM 426 U:.. NUCLEAR REGULATORY COMMISSION 1. REPORT NJMBER -C0e humbenr frm tme (" R)Technical PUN0060ft~ Section TIephane: 301415-7174, or E-mn" address b1nm c v

AUTHORIZATION TO PUBLISH A NUREG-SERIES

DOCUMENT PREPARED BY THE NRC STAFF

2. Tm£ AMD SUfntE (Sbetew 1t4 inm cspIgew. sV Jsh ii m w TYPE OF DOCUMENT

f REPORT

El BROCHURE

E BOOK

E CONFERENCE PROCEEDINGS

. INTERNATIONAL AGREEMENT

REPORT

3. DISTRIBUTK)N

A. List alpham nlo codes for dn ut liost such asiB or CY. See NUREG/BR40188, Dstibutkn List

Descriptions for NRC Repors and Dbcumens. or cal 301.415.2070 to obtain a opy.

B. Provid otf mailing hlbels ho addressees not included in NRC distribution riats I NRC staf. provide name and mad sop ony. if non-NRC addressees, prowd complete mailing address.

C. I more hn one copy Is required for an addressee. Indicat, the number of copies in parentheses on the label.

D. Include number of copies for the NRC Publication Project h rna geivng name nd mat dop.

YESe NO I4. CERTIFICATION (ANSW&HALL QU&SFIUONS) --(Conbtadftf J--j CW# Ss Branch, Otwic o d e Chbfhbflennon OMlcr at 301415-1234 brk sbuctDi ffport contas a corpucods)

Is llmatril rfeencd n tisreport available to the public either through a public libat. the Government E El A. REFERENCE AVAILABIUTY - Printing COMcor the Nationda Tedhical In Servc, or t NRC Pubic Documen Room? n hd below thes ift avaiability d each referene docunent.

. SPECICAVALABEJTY 0nrde r ,

lB. COPYRIGHTED MATERIAL - this reo coniain copyrighted matedaf? tyes, attach a etr o relase to pr orto podt to www the so e thatGT holds the copyright. See NUREG-0650. Rev. 2Preparing NURE aSede Publicatlons'

l C. PATENT CLEARANCE - Does this report reqire patent clearance? * JrLJ Ithe, yes NRC Patenl Counsel mud sir claance by sinn beowb.

NRC PATENT I COuM. (Type or prin name) SGNATt.RE DATE

Does thi report contain measurement and weight vales? Ifyes, all mud be conerted to the International El El E. METRIC UNIT CONVERSION - system of Units, followed by the English unh in brackets. punuant to the NRC Poricy Statentw

implementing the Omnibus Trad and Copties Act of 198M. Exutive Order 12770. July 25,1991.

El El F. FEDERALREGISTERNOTICE - Wills dS gisyerNot vmau bs ued ?

E E H. COLOR PRINTING - WI tHis report require color prin? If yes, use of color must be appved by th Chie, Publishing Servics Branch. oao. Altach a copy of apprv.

Contact the Records Management Branch (RMB), Office of the Chief Information Officer, at 301-415-7233 or E-mail address BJS1, to

review this NUREG-sedies document and have RMB staff sign below.

RM1 STAFF (Type or pint n) SIGNATURE DATE

I - . . II

A NUREG-series publication may not contain a legally binding regulatory requirement. Your signature in Block 7 certifies

that this publication contains none.

5. PUBLICATION FORMATS (Check approdte bao) E DISKETTE El WWW

In addion to paper, publish In the following formats: IV diskette, submit two copes Itlo be poste on thew , send with manuscript. request by a-mall to cnrvtmb2

-S6. NRC PUBUCATION PROJECT MANAGER | __ TO PRINT I.NCPBIAINPOETMNGR~ (Canot be the same Derson listed In block 61.)

NAME (TPlO aapg I

NRC OFFXcAL AUTHORZNG PUBLICATION (Type orprn nJe)

SIGNATURE

I

NRCFORM426 (1-19W - * PRINTED ONRECYCLEDPAPER - - I - This ftm Wa dsWod usng InForms

Figure 5.3 NRC Form 426, "Authorization To Publish a NUREG-Series Document

Prepared by the NRC Staff"

NUREG-0650, Rev. 2 38
Publishing Forms

NRC FORM 426 US. NUCLEAR REGULATORY COMMISSION 1. REPORT N -UOBE in n'nlber t Ie

Techdc PubliCabos Saubn, Telephoe:

*- 01j"--415-7174. or Emaiaddres pbtnorgov

AUTHORIZATION TO PUBLISH A NUREG-SERIES NUREG-1531.

DOCUMENT PREPARED BY THE NRC STAFF

2. TT=EAkDS tThLEfbb~hlg "wi s ^ eyseronn IlTYPE OF DOCUMENT

Final Environmental Impact Statement Related to the C REPORT

Reclamnationof.the'UraniumiMill Tailings at the Atlas" El BROCHURE

Site, Moab, -Utah, Source Material License No. SUA 917 El CONFERENCE PROCEEDINGS

Docket No.- 40-3453; -Atlas Corporation5 INEATOLAGEMT

REPORT

3. DISTRBUTION ' *

A. ISt alphanwr codes for distributon ists. such as IB or CY. S NUREG/BR41U, n U1

Depo tor NRC Reports and DocumeWta, or call 301.415-2070 to obtain a copy. 1H

B. Provide pedff mailing labels for addressee not Included hi NRC distribution lits,; I NRC staff, provide name . and nail top only; il non-NRC addressees, provide complete mailing address..

C. It more han one copy I required for an addressee. Indicate the number of copies in penthesea on the label.

o. -Include numberofcopiesfrth.NRCPublicefim ProjecMarr.givhinnameand malstop.' M. Fl iegel, T7-38 (75)

N4. CER7lFICATION (ANSWER ALL QUESTIONS)

(Contact theT CuslntwSer Btianch, Olilceofte ChhIlbmetihon Officar, at30 -415.1234 bhosbuco hl port contis a coprcode)

hsa material rlefnced in this report available to the public eiter hrough a public libraty, th Government E A. REFERENCE AVAILABILITY - PTWnOfte, to National Techical Information Service, or the NRC Public Document Room? It no, I below the specf aabby of ach referenced document.

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APPENDIX

This appendix contains a sample NUREG-series publication. The contents of

the various sections of this sample publication are not necessarily related, for

example, the abbreviations may not appear in the text. Each section is

designed to illustrate appropriate formatting or necessary components of the

section. For example, the sample shows references, how to refer to a reference

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pages in the appendix are numbered consecutively as they would be in a

report rather than as described in Section 4 of this guide.
NUREG/CR-6220

SAND94-0769

An Assessment of Fire

Vulnerability for Aged

Electrical Relays

Sandia National laboratories

SAMiPLEREPOR]p

,'.. .. ,.-t.

- 

vŽ-:.-,s".

U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research

Washington, DC 20555-0001

/-*0 "01-x

I'llS10
En

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NUREG/CR-6220

SAND94-0769

An Assessment of Fire

Vulnerability for Aged

Electrical Relays

Manuscript Completed: May 19XX

Date Published: May 19XX

Prepared by

R. A. Vigi,* S. P. Nowlen

Sandia National Laboratories

Albuquerque, NM 87185-0737

J. E. Doe, NRC Project Manager

Prepared for

Division of Enginering

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

NRC Job Code A1833

Science & Engineering Associates, Inc.

6100 Uptown Blvd. NE

Albuquerque, NM 87110
ABSTRACr

This report describes testing to assess the

impact of aging on the fire vulnerability of

Agastat and General Electric relays. Both

aged and unaged relays were tested. Aged

relays were subjected to operational cycling

under rated load and thermally aged for 60

days. All relays were exposed to one of three

different ire temperature profiles in the

Severe Combined Environments Test

Chamber located at Sandia National

Laboratories. The ability to operate properly

in the given fire environment was monitored.

Results for the aged and unaged relays were

examined to determine the impact of aging on

the relays' ability to sustain operation under

the test conditions. Overall results indicated

that the aged relays' performance was not

significantly different from that of the unaged

relays.

iii NUREG/CR-6220
CONTENTS

Page

Abstract ............... .... : ..... iii.................

Executive Summary .; ........... ...........;.. vii

Abbreviations. ............................................................... ix

I Introduction and Objectives .. I

2 Relay Selection Basis and Results .3....3

3 Experimental Arrangement.. 7

3.1 Relay Aging Procedures. 7

3.2 Relay Fire Testing. 7

3.3 Relay Operational Assessments. 9

4 Experimental Results .. 11

4.1 Aging .11

4.2 Thermal Exposure Results .11

4.2.1 Agastat GPI Results .12

4.2.2 General Electric HMA Results . ............................. 13

4.2.3 General Electric HGA Results .14

424 General Electric HFA Results .16

5 Conclusions ....... 19

6 References .. 21

Appendices

A SCETCh Temperature Exposure Plots for AU Relays Tested ......... ............. A-1

B Glossary. ................................................................. B-1

Figures

1 Schematic of a Typical Armature Style Relay. 4

2 Severe Combined Environments Test Chamber (SCETCh) at Sandia

National Laboratories. 7

3 SCETCh Temperature Exposure Profiles. 8

4 Measurement Schematic for Each Contact Pair and Measurement Matrix. 9

5 Agastat Al Relay With Normally Open Contact Stuck Because of a

Melted Contact Carrier .12

v NlUREG/CR-6220
CONTENTS (continued)

Page

6 General Electric HMA Relay B-3 After Thermal Exposure ...... ................ 14

7 General Electric HGA Relay C-i After Failure of the Spool's Top Plate ..... ...... 15

8 General Electric HGA Relay C-4 Failure of the Armature Because of Blockage .... 16

9 General Electric HFA Relay D-1 After Thermal Exposure .17

Tables

1 Relay Identification Scheme .5

2 Overall Relay Test Results .18

NUREG/CR-6220 vi
EXECUTIVE SUMMARY

The purpose of this test program was to assess

whether the fire vulnerability of electrical

relays increased with aging. A five-step

sequence followed for the test program was to

(1) identify specific relay types, (2) develop

three fire scenarios, (3) artificially age several

relays, (4) test the unaged and aged relays in

the fire exposure scenarios, and (5) compare

the results.

The relays tested were Agastat GPI, General

Electric (GE) HMA, HGA, and HFA. At least

two relays of each type were artificially aged

and at least two relays of each type were new.

Relays were operationally aged by cycling the

relay under rated load for 2000 operations.

These relays were then thermally aged for 60

days with their coil energized.

Temperature exposure testing was conducted

in Sandia's Severe Combined Environments

Test Chamber (SCETCh). Three exposure

profiles were developed for this test program,

which were representative of a generic mild,

moderate, or severe thermal exposure. The

exposure profile' consisted of two phases: The

initial phase consisted of a temperature ramp

to either 250 'C, 350 'C, or 450 'C, a 10-20

minute dwell at the desired temperature, and

then a temperature decrease toward ambient.

The second phase began shortly after the end

of the first phase and consisted of a

temperature ramp at a rate of 10 'C per

minute until failure was observed. The second

phase was only performed if the relay survived

the first phase.

Results for the Agastat GPI relays indicated

that aging would not significantly affect the

thermal vulnerability of the relay. All of the

relays tested were observed to fail at

temperatures ranging from 206 to 250 'C. In

fact, of the relays tested, only one-an aged

sample-survived the initial phase of the mild

exposure profile. Failures were generally

traced to either the coil rectification circuit or

the base socket.

Results for the GE HMA relays indicated that

the aged samples were, in fact, somewhat

more rugged than the unaged samples. During

exposures to the moderate exposure profile,

an unaged sample was observed to fail

whereas an aged sample survived the initial

phase of this profile. All failures were

attributed to failure of the armature. In three

of the four cases, actuation of the armature

failed because of an accumulation of an

unknown substance that formed on the top of

the coil's spool just below the armature. The

final failure was attributed to the armature

becoming used to the relay's housing.

Results for the GE HGA relays indicated that

aging did not impact the thermal vulnerability

of the relays. However, one of the aged

samples displayed a unique failure in that it

failed during the cool-down portion of the first

phase of the moderate exposure profile. The

remaining three relays survived to temperatures in excess of 450 'C. Three of the relay

failures were attributed to the accumulation of

an unknown substance that formed on the top

of the coil's spool just below the armature.

The final failure was attributed to deformation

of the coil top plate.

Results for the GE HEA relays indicated that

aging did not significantly impact the thermal

vulnerability. Both aged and unaged samples

were observed to survive the initial phase of

the mild exposure profile while failing during

the initial phase of the moderate exposure

profile. All failures were attributed to failures

of the armature.

In general, the conclusion was that aging did

not adversely affect the thermal vulnerability

of relays. Depending on the type of relay, the

effect of exposure to even mild temperature

excursions (>200 'C) may degrade relay

performance regardless of the relay's age.

Failure mechanisms were generally attributed

to failures in the armature.

vii NUREG/CR-6220
ABBREVIATIONS

Al Automated Industries

BNL Brookhaven National Laboratory

CAL Confirmatory Action Letter

CFR Code of Federal Regulations

DOT U.S. Department of Transportation

DU depleted uranium

ECG East Coast Group

EST Eastern Standard Time

HMR Hazardous Materials Regulations

HMTA Hazardous Materials Transportation Act

IAEA International Atomic Energy Agency

IATA International Air Transportation Association

ICAO International Civil Aviation Organization

KINS Korean Institute of Nuclear Safety

KIT Korean Industrial Testing Company

LSA low specific activity

MOST Ministry of Science and Technology (Korea)

MOU Memorandum of Understanding

NRC U.S. Nuclear Regulatory Commission

NVOCC non-vessel operating common carrier

ORAU Oak Ridge Associated Universities

PPQ plant protection quarantine

PST Pacific Standard Time

RSO Radiation Safety Officer

S/N serial number

UN United Nations

USCG United States Coast Guard

USDA U.S. Department of Agriculture

WCG West Coast Group

LX NUREG/CR-6220
1 INTRODUCTION AND OBJECIVES

Regulators of the nuclear industry have been

concerned that as nuclear power plants age,

protective measures taken to control and

minimize the impact of fire may become

ineffective or signitficantly less effective and,

hence, result in an increased fire risk. One

objective of the Fire Vulnerability of Aged

Electrical Components Program is to assess

the effects of aging and service wear on the

fire vulnerability of electrical equipment. An

increased fire vulnerability of components may

lead to an overall increase in fire risk to the

plant.

Because of their widespread use in various

electrical safety systems, electromechanical

relays were chosen to be the initial components for evaluation (Ref. 1). This test program assessed the impact of operational and

thermal aging on the vulnerability of these

relays to fire-induced damage. Only thermal

effects of a fire were examrined in this test

program. The impact of smoke, corrosive

materials, or fire suppression effects on relay

performance were not addressed in this test

program. In addition to discussing this test

program and conclusions drawn from it in

Sections 2 through 5 of this report, Appendix A has temperature exposure profiles for

each relay tested and Appendix B is a glossary.

1 NUREG/CR-6220
-2 RELAY SELECION BASIS AND RESULTS

An earlier study performed as a part of the

Fire Vulnerability of Aged Electrical Components Program identified and prioritized

nuclear power plant electrical equipment

potentially vulnerable to age-related increases

in fire vulnerability (Ref. 1). This study

included an eviluation of industry practice and

component count totals. As a result, relays

were identified as one of the'high priority

components.

Relays'used in'safety-related applications can

'typically be'divided into four categories:

protective, auxiliary, control, and timing.

Protective relays serve to protect electrical

distribution systems fromn electrical overloads.

Auxiliary relays serve 'to assist protective

relays,'especially when loads up to 35 amps

are present in the distribution system. Control

relays serve as direct controlling mechanisms

for various mechanical components. Timing

*relays perform similarly to control relays with

the exception that these relays are combined

with a timing'device that actuates the contacts

after a time period has passed from the receipt

of a control signal (Ref. 2).:

The dominaiit aging-related stress 'for relays

identified in Reference 1 is the thermal aging

of synthetic parts caused by continuous

energization or elevated cabinet temperatures.

Reference 1 'also identifies the following

possible failure modes and causes:

Relay Fallure Modes:'

* Failure to actuate when commanded

* Actuates without command

* Does not make or break current

* Failure to carry current

* High contact resistance

* Set-point shift

* Time delay shift

Relay Failure Causes:

* Phase-to-ground short

;- * Coil insulation breakdown

* Contact wear -

* Binding of contacts because of carrier

warpage

* Pitting, corrosion, and accumulation of

contaminants on contacts

0 Wear of moving parts

Loss of integrity of relay pin/socket

connection

* Vibration damage: contact chatter,

loosening of connections

* Shift in resistance and capacitive values

affecting time delay and relay set-point

-values

Reference 1 identifies those relay models

having the greatest'numbers in nuclear power

plants. In particular, three General Electric

(GE) models are identified as the most widely

used in industry: the GE model HFA (21%),

GE model HGA' (12%o), and GE model HMA

(7%). General Electric supplies approxinately

52 percent of all electromechanical relays to

the utilities that responded to the survey

(Ref. 1). Results of the survey showed that

Agastat/Amerace relays provided 10 percent

of all relays. In light of the survey results, the

following relays were chosen to be tested in

-this program:

* General Electric 12HFA51A49F

5 relays tested

* General Electric I2HMAl1A9

4 relays tested

* General Electric I2HGAIIA70F

4 relays tested

* Agastat/Amerace GPI

6 relays tested

All the relays chosen are armature style relays

and are rated for operation at 115 V and 12

amps (except for the Agastats, which are rated

at 10 amps). Figure 1 shows the basic

components of a typical armature style relay.

3 3 NUREGICR-6220
Arnature

X_ Nonnally Closed Conmc

-. NormIally Open Conta

* the coil's spool is comprised of high

thermal strength, glass-filled polyester for

extended life at elevated temperatures;

* the wire insulation is a polyamideimide

wire coating (180 .C rating) that retains

insulation integrity and mechanical

strength at elevated temperatures; and

* the encapsulation is described by the

manufacturer as polybutadiene,

solventless, and imprdgnant.

Figure 1 Schematic of a Typical Armature

Style Relay .

The relays tested in this program were

obtained directly from the suppliers. They are

effectively identical to UL recognized and

Class IE qualified devices sold to nuclear

power plants, although they were not procured

to Class IE specifications. The major

difference lies in the traceability of the relay

production.

General Electric relays are constructed with

either the standard life coil design or the

Century series coil design. Further analysis of

the survey data from Reference 2 indicates

that both types of coil designs for these relay

models are in use in various systems in nuclear

power plants. The GE HGA and HFA relays

tested in this program were constructed using

the standard life relay coil design. The GE

HMA models tested in this program were

constructed using the Century Series coil

design.

Basic design features of the Century Series

coil include the following.

Accelerated life tests conducted at an elevated

temperature and maximumryoltage have

established a projected service life of 40 years

at 55 C and 110 percent of rated voltage for

this coil design. The standard life coils are

simple coil designs with a phenolic spool and

an exterior tape wrap. The wire insulation is

similar to that of the Century Series.

The Agastat GPI relays are constructed using

an electromagnetic core. A W-shaped

mechanism is connected to the core to provide

contact switching movement. The coil provides

a low mean turn length and assists in heat

dissipation. The GPI relays also have a built-in

rectification circuit that retains the de

efficiency of the electromagnet. The current

peak upon coil energization is also eliminated

through the use of a capacitor. The GPI relays

require a screw terminal molded socket for

operation. Note that two socket models are

available. The model number of the socket

used in this test program was CR0067.

In all, 19 relays were tested as a part of this

program. Table 1 lists the scheme used to

identify each of the relays tested.

NUREG/CR-62204 4
Table 1 Relay Identification Scheme

Relay Identification Model Number Aging Condition

Al Agastat GPI Aged

A2 Agastat GPI Aged

A3 Agastat GPI Unaged

A4 Agastat &PI Unaged

A5 Agastat GPi Unaged

A6 Agastat GPI Unaged

BI GE 12HMA11lA9 Aged

B2 GE 12HMA1lIA9 Aged

B3 GE 12HMAlllA9 Unaged

B4 GE 12HMA111A9 Unaged

Cl GE 12HGAUIA70F Aged

C2 GE 12HGAlIA70F Aged

C3 GE 12HGAllA70F Unaged

C4 GE 12HGAlIA70F Unaged

Dl GE 12HFA5lA49F Aged

D2 GE 12HFA5lA49F Aged

D3 GE 12HFA5lA49F Unaged

D4 GE 12HFA51A49F Unaged

D5 GE 12HFA5lA49F Unaged

5 5 NUREG/CR-6220
3 EXPERIMENTAL ARRANGEMENT

3.1 Relay Aging Procedures

A general aging procedure was established

based on the information contained in IEEE

C37.105-1987, "Standard for Qualifying Class

1E Protective Relays." This procedure

included both operational and thermal aging.

Radiation aging of the relays was not included

in the aging procedure.,

The relays to be aged were cycled individually

under rated load for 2000 cycles to fulfill the

basic operational aging requirements defined

in IEEE C37.105-1987. The relay coils were

energized every minute for 0.4 seconds. After

each set of 500 cycles, the coil resistance was

measured for each relay. :

After completion of the operational aging, the

relays were thermally aged in an oven for 60

days at 110 'C. During this entire period, the

coil of each relay was energized to simulate

the additional thermal load produced by the

self-heating effects of the coil. (Note that The

two Agastat bases were not included with the

relays in the thermal aging portion of the test.)

The thermal aging procedure was intended to

represent a generic aging condition. That is,

the thermal aging protocol was not based on

achieving a particular aged condition for any

of the specific relay' materials. Rather, the

protocol was intended to provide nominal

aging conditions for the relay as a whole.

3.2 Relay Fire Testing

The fire exposure tests were 'conducted in

Sandia National Laboratories' (SNL:s) Severe

.Combined Environments lest Chamber

(SCETCh). The SCETCh facility, shown in

Figure 2, is able to simulate both transient and

steady-state thermal conditions. The SCETCh

facility was designed to simulate fire

environment effects. Additional capabilities of

the SCETCh facility include steam testing and

hydrogen burn simulation. The facility may be

used as a high temperature pressure vessel.

The SCETCh facility is designed to operate at

elevated temperatures as high as 1500 'C.

II

FI _ n Ifroment, Tes C -:: .C aa.h)aL:o .* ; e

Figure 2 Severe Combined Environments Test Chamber (SCETCh) at Sandia National Laborntories

7 7 NUREG/CR-6220
I

The SCETCh chamber is a cylindrical chamnber measuring 24-inches long by 18-inches in

diameter. The shell and cover plates are

constructed from Inconel 625. The elevated

temperatures are generated by a series of

quartz lamps mounted around the chamber.

Resistance coil heaters are used to beat

incoming fresh air for the chamber. The

desired temperature exposure profiles are

achieved using a computer-controlled 480 V ac

power supply.

Each of the sample relays was tested using one

of three thermal exposure profiles. These

profiles were intended to be representative of

generic mild, moderate, and severe thermal

exposures, respectively. That is, the profiles

were intended to represent various commonly

identified generic fire scenarios rather than

any given specific fire scenario. Transient

profile ramp rates, peak exposure temperatures, and profile durations were determined

on the basis of the results of available test data

and actual nuclear power plant fire event

reports. (Refs. 3-7)

Each of the three profiles consists of two

phases as shown in Figure 3. During the first

phase of the exposure-

* the exposure temperature was increased

from ambient at a rate of approximately

20 T/min (initial ramp);

* upon attaining a predetermined

temperature, the exposure was held

constant for a specified time (plateau);

and

* the exposure temperature was decreased

toward ambient conditions over a period

of approximately 20 minutes (cool-down).

For the mild exposure profile, the initial ramp

lasted for approximately 10 minutes, reaching

.600

i500

I-; 300

S

A' 200

0

0 10 20 30 40 SO 60 70 80 90

Tme (mi)

FIgure 3 SCETCh Temperature Exposure Profiles

NUREG/CR-62208 8
a plateau temperature of 250 .C, which was

held for an additional 10 minutes. For the

moderate exposure profile, the initial ramp

lasted for approximately 15 minutes, reaching

a plateau temperature'of 350 .C, which was

held for an additional 15 minutes. For the

severe exposure profile, the initial ramp lasted

for approximately 20 minutes, reaching a

plateau temperature of 450 'C, which was

held for an additional 20 minutes.

The second phase of each exposure profile

consisted of an upward ramp in temperature

at a rate of 10 *C/min until relay failure was

detected. The relay under test would undergo

the second phase only if it had survived the

first phase of the exposure profile. This second

phase of the exposure profile was intended to

assess the relative margin by which a relay had

survived the initial phase of the exposure

profile. For example, if the relay failed at a

substantially higher temperature than the first

phase plateau temperature, then it could be

concluded that the relay had survived the first

phase with significant margin.

3.3 Relay Operational Assessments

During each exposure, the test relay was

I operated under a 1 amp load for each contact

' set and was periodically required to actively

switch this load. In particular,'each'60-second

measurement cycle consisted of a period of 50

seconds during which the coil was energized

and 10 seconds when the coil was

de-energized. The relay's ability to switch the

load was monitored to verify operability.

Additional measurements made during each

measurement cycle included the relay's coil

resistance, contact set resistance, and leakage

currents. An electrical schematic of the

simulated load and performance monitoring

circuit used for each contact set is shown in

Figure 4. The measurement matrix is also

included for clarification.

20 Vac

Output Mearements Coil Coil

For Eaeh Contact Set Uneuergiwd - Euerged

I Lo1d Curent Measurmnt L C eaurem

2 Leakage Current Meamureent Lead Current Measmrment

3 Contact Resistance No Meaurement

4 No Measrenent Contact Reance

Figure 4 Measurement Schematic for Each Contact Set and Measurement Matrix

9 NUREG/CR-6220
This mode of operation is not representative

of typical in-plant applications. Typically, a

relay would be called upon either to hold its

current position throughout an event or to

switch positions once and hold the new position. However, the objectives of this test

program require that the relative performance

of the aged and unaged relays be compared.

Hence, assessing both the timing of relay

failure during a particular exposure profile as

well as the fact of survival or failure was

important. To meet this objective, the relays

had to be operated periodically to assess the

continuing operability throughout the

exposure.

NUREG/CR-6220 10
4 EXPERIMENTAL RESULTS

.4.1 Aging

No anomalies were recorded during the

operational cycling of the relays. The coil

resistance varied less than 4 percent during

the cycling for each of the relay types. No coil

failures or test equipment anomalies were

detected during the thermal aging of the

relays.

However, after the thermal aging, note that

the armature of the HGA relay was malfunctioning. As the HGA coils were energized, the

armatures for each relay easily switched from

the normally dosed to the normally open

position. However, when the coils were

deenergized, the armature did not completely

return to the normally closed position. The

hypothesis was that the thermal aging might

have caused the degradation of some unknown

lubricant in the pivot. (However, the

manufacturer stated that no lubricant was

used in the armature.) The manufacturer

hypothesized that particulates from outgassing.

during the thermal aging may prevent the

armature from returning to the normally

closed position. -

Another possibility for the improper operation of the relay was the failure of the return

spring. The return action of the armature was

controlled by a spring attached to a slotted,

flange on the armature. A spring from an . unaged relay was substituted for the one from

the aged relay. With the new spring in place,

the relay still did not return to the normally

closed position, which indicated that the spring

itself was not the cause of the problem. The

spring from the aged relay was returned to the

original position on the aged relay. The spring

was in the original slot position, which was the

middle'slot on the flange, during operational

and thermal aging. As the springwas'adjusted

to provide the greatest closing force, the first

relay still would not return to the normally

closed position.

By using low pressure air, the armature from - the first aged relay was cleaned to try to

remove any particulates that might be

hampering the armature movement. After the

-,pressurized air cleaning and the adjustment of

the spring's position, the armature returned to

the normally closed position when the relay's

coil was de-energized. The second relay was

also cleaned with pressurized air, and it also

had the spring adjusted to provide maximum

closing force. Likewise, this relay now

performed as required. The position of this

spring remained in the slot that provided the

greatest closing force so that the remainder of

the test program could be completed. The

exact cause of this failure was not fully

determined during this'test program, but it

may warrant further investigation. The

remaining relays did not experience any problems upon completion of the thermal aging.

-4.2 Thermal Exposure Results

For each relay type, the first exposure was

performed using the unaged samples followed

by testing of the aged samples. For each group

the first relay sample was subjected to the

moderate exposure profile. Based on the

result of this exposure, the next sample was

subjected to either the mild or severe exposure

profile. That is, if the first sample survived the

entire first phase of the moderate profile, then

the second sample was subjected to the severe

profile. Conversely, if the first sample failed

during the first phase of the moderate profile,

then the second sample was subjected to the

mild profile. Certain exceptions to this general

test sequence were exercised as described in

the next four paragraphs.

In preparation for testing, relays were energized for approximately 5 minutes before the

thermal exposure. Failures were determined

by either a loss of load-switching capability or

the opening of a 1-amp fuse located on the coil

input. Upon indication of failure, the

"experimental control program was allowed to

complete another full measurement cycle to

verify that a persistent failure had occurred.

The power to the SCETCh chamber, the relay

load, and the coil power was then shut off. The

f - 11 11 NURBGICR-6220
test relay remained in the chamber until the

chamber's temperature decreased.

Each relay type was tested in its expected

mounting position. The mounting hardware

included with each relay was used during the

testing. Complete panels were not used, only

frame supports as necessary to provide for

mounting.

The complete results for all relays tested can

be found in Table 2 at the end of this section.

Temperature exposure profiles of each relay

can be found in Appendix A. The specific

details for each relay type are discussed in the

following sections.

4.2.1 Agastat GPI Results

A previous test program, which evaluated

relay functionality during exposures to

secondary environments created by a fire,

indicated that the Agastat relays were not

likely to survive the mild exposure profile

(Ref. 7). Therefore, all of the Agastat samples

were tested in the mild exposure profile.

second-phase temperature ramp. The

temperature at the time of relay failure was

250 'C. Post-test analysis revealed two failure

mechanisms. The first failure was detected in

the base where two terminals were shorted

together because of warpage of the base

socket. The second failure discovered was a

melted contact carrier that prevented the

armature from returning to the normally

closed position, as shown in Figure 5. During

the previous test program (Ref. 7), an Agastat

GPi relay displayed a similar contact carrier

failure at a temperature of approximately

210 'C. (Note that this earlier program

utilized a slowly increasing temperature

profile until failure was detected.)

The second aged Agastat relay, A2, survived

approximately 24 minutes, failing during the

early stages of the cool-down period. The peak

exposure temperature was 241 'C, and the

temperature at the time of failure was 210 'C.

Post-test analysis revealed that a capacitor in

the oil rectification circuit had a visible burnt

crack at the top portion of the device. A

continuity check of the coil rectification circuit

indicated an open circuit.

The Agastat Al relay survived 64 minutes into

the mild thermal exposure, failing during the

Figure 5 Agastat Al Relay with Normally Open Contact Stuck Because of a Melted Contact Carrier

NUREG/CR-6220 12
~;s -1 ,

The unaged Agastat relays, A3 and A4, failed

approximately 11 and 14 minutes into the

exposure, respectively. In'each case, the

failures occurred early in the plateau period.

The temperatures at the time of failure were

206 'C and 221 'C, respectively. The failure

mode was similar to that of relay A2, namely,

an open circuit in the coil rectification circuits.

The capacitors did not display visible cracking

as in A2.

Agastat unaged relays AS and A6 failed

approximately 11 and 12 minutes into the

exposure, respectively. In each case, the'

failures occurred early in the plateau period.

The temperatures at the time of failure were

215 .C in both cases. In each case the failures

were traced to the bases. Post-test analysis

revealed that a short had occurred between

two terminal sockets in each base. The short

caused each relay'to fail.

Contact resistance measurements for all

Agastat delays were typically below 70 mQ.

The highest recorded contact resistance for

any relay was 86 mQ. Load currents remained

stable until failures were observed. Open

contact leakage currents were generally erratic

and provided limited information.

Failures for the Agastat relays were attributed

to three failure modes: shorting of the base,

failure of the built-in rectification circuit, or

warpage of the contact carriers. The

manufacturer recommended operatingtemperature range for this relay isO 'C to

60 C. All the failures observed occurred at

temperatures in excess of 200 * C.

fi I . . . . - -< > i

The'aged samples survived longer in the test

environment than the uiaged samples, which

suggests that the aging protocol enhanced the

relay's ruggedness. The aging process is

suspected to have annealed the coil

rectification circuit components, increasing

their tolerance to thermal exposures.

4.2.2 General Electric HMA Results.

The first aged relay, Bi, was tested in the

:moderate profile and failed at the end of the

cooldown portion of the exposure. The peak

exposure temperature was 352 'C, and the

temperature at failure was 129 'C The failure

observed was associated with an armature

actuation failure. Post-test analysis revealed

that a substance, apparently released from the

coil's spool, accumulated on the top of the coil

and prevented the armature from actuating.

The second aged relay, B2, was tested in the

severe profile and failed early in the plateau

period. The temperature at the time of failure

was 447 'C. The mode of failure was identical

to that of relay B1.

The first unaged relay, B3, was tested in the

moderate profile and failed midway through

the plateau period. The temperature at the

time of failure was 348 C. The mode of

failure was again associated with an armature

failure. However, in this case a closer

inspection revealed that the armature had

fused to the relay's housing. The point of the

fusing is shown in Figure 6. The armature arm

was separated from the housing when slight

pressure was applied. However, it still did not

actuate freely because of warpage of the

relay's housing.

The second unaged relay, B4, was tested in the

mild profile. The relay survived the entire first

phase of the exposure and failed during the

second phase. The temperature at the time of

failure was approximately 400 'C. The mode

of failure was identical to that observed for

relay B1. -

These results showed that the aged specimens

performed slightly better than the unaged

-specimens. Three of the four failures,

.including both of the aged and one of the

unaged samples, were attributed to the

accumulation of an unknown substance on top

of the coil and under the armature. The fourth

failure was attributed to fusing of the armature to the relay housing.

*6n ,i- .a.u-e:e -

Contact resistance measurements for all GE

HMA relays were typically below 60 mQ.

',Load currents remained stable until failure

was observed. Open contact leakage currents

were generally under 0.1 amp 'until failuire

occurred.

13 NUREG/CR76220
:

Figure 6 General Electric HMA Relay B-3 After Thermal Exposure

Note that during an earlier test program

(Ref. 7) an HMA relay (without a cover) was

also tested. During this test, failure occurred

at approximately 400 'C. However, this failure

was attributed to the external coil power lead

wires shorting together, rather than to a

failure in the relay itself. This failure also

caused the lead wire to ignite, and the

resulting fire destroyed the relay.

4.2.3 General Electric HGA Results

The first aged relay, CI, was tested in the

moderate profile and failed during the late

stages of the cool-down. The peak exposure

temperature was 353 'C, and the temperature

at the time of failure was approximately

150 IC.

(Note: Data during the cool-down portion of

the exposure were not recorded because of a

data logging error. The time of failure was

recorded by the test operator, but the final

temperature was not recorded. The temperature shown in Figure A-I1 of Appendix A is

an estimate based on other profiles.) The

failure was caused by warpage of the top plate

of the coil's spool, which curled upwards and

prevented the armature from actuating as

shown in Figure 7. Note that this was the only

instance in which this particular failure mode

was observed.

Since the first aged relay, C1, failed on the

cool-down before completing the first phase of

the moderate exposure, a decision was made

to deviate from the nominal testing protocol.

In particular, the second aged relay, C2, was

also tested in the moderate profile. This

deviation was implemented in order to verify

the results.

The second aged relay, C2, survived the first

phase of the profile and failed during the

second phase. At an exposure temperature of

480 'C, the specimen self-ignited. Shortly

thereafter, failure of the relay was observed.

The failure was associated with a loss of

armature actuation capability. Inspection of

the charred remains of the coil and the

armature showed that the armature and coil

had become fused together because of the

accumulation of an unknown substance

beneath the armature. (Recall that similar

behavior was noted in three of the four HMA

relays tested.)

NUREG/CR-6220 14
Figure 7 General Electric HGA Relay C-I After Failure of the Spool's Top Plate

The first unaged relay, C3, was tested in the program, which produced exposure profiles

moderate profile and survived the entire first that were very similar to the desired exposure

phase of the exposure. Failure was noted profiles.

during the second phase at a temperature of

488 'C. Failure was attributed to the The second unaged relay, C4, was tested in the

accurmilation of an unknown substance. -. severe profile and failed at the end of the

underneath the armature' on top of the coil's - plateau period. The temperature at the time

spool. This substance prevented the armature of failure was 453 *C. The failure mode was

from actuating. (Note that similar failure - identical to that of relay C3; namely, an

mechanisms occurred for the two different coil accumulation of an unknown substance

designs, the GE HMA and GE HGA.) . underneath the armature prevented the

armature from actuating. This substance can

be seen in Figure 8.

The C3 relay was the first GE relay tested

from among all relays. The control program -Based on the time to failure and final

used in this test was identical to that used for temperature; the two unaged relays appear to

the Agastat tests. Because of the variation - have performed slightly better than the aged

between the actual and the intended profile, -relays, given these temperature profiles.

the control program was modified to However, the difference in the results for the

compensate for this variation. The variation aged and unaged relays is not significant.

can be observed by comparing Figure A-13 to , - . .-

A-11 or to A-12. The difference was; Contact resistance measurements for all GE

determined to be caused by the controlling HGA relays were typically below 60 mQ. Load

thermocouple's location relative to the currents remained stable until failure was

chamber and the test specimen. The remaining i, observed. Open contact leakage currents were

relays were tested using the new control generally under 0.1 amp until failure occurred.

15 15 NUREG/CR-6220
Figure 8 General Electric HGA Relay C-4 Failure of the Armature Because of Blockage

4.2.4 General Electric HFA Results

The first aged relay, Dl, was tested in the

moderate profile and failed early in the

cool-down period. The peak exposure

temperature was 359 'C, and the temperature

at failure was 349 'C. The failure of two of the

six contacts pairs was noted in load current

measurements. Inspection showed that the

armature was warped or bowed. This warpage

was severe enough to prevent the closure of

two of the six contact pairs. However, the coil

remained functional during post-test analysis.

The second aged relay, D2, was tested in the

mild profile. The relay survived the first phase

of the exposure and failed during the second

phase at a temperature of 485 *C. The failure

was attributed to severe deformation of the

relay body. The relay's components were

misaligned, and the armature movement was

not free enough to complete contact (make or

break).

Relay D3 was tested in the moderate profile

and failed midway through the cool-down. The

peak exposure temperature was 348 'C, and

the temperature at failure was 298 'C. The

mode of failure was similar to relay Dl.

Relay D4 was tested in the severe profile and

failed midway through the plateau. At an

exposure temperature of approximately

450 'C, the specimen self-ignited. Shortly

thereafter, failure of the relay was observed.

The ensuing fire destroyed the relay.

The final relay tested was D5. It was tested in

the mild environment. The relay survived the

first phase of the exposure and failed during

the second phase at a temperature of 440 *C.

The test data indicated that the coil did not

actuate when power was applied. However,

post-test analysis did not find any problems

with the coil or the armature. The armature

was slightly misaligned and slightly warped,

but the contacts were all making contact. The

exact cause of the failure was not evident, but

when the coil was energized, the relay

hummed and chattered loudly. On one

subsequent energization, the armature failed

to actuate. Hence it was concluded that this

relay was subject to an intermittent failure.

NUREG/CR-6220 16
These results indicate that the aged and erratic but generally under 0.2 amp until

unaged relays behaved quite similarly under failure occurred.

the given test iofiditions. The resuilts of the-

-aged and unaged HFA-relays suggest that the - - T '

relays will most likely survive in a fire with an 1 All of the relays tested showed signs of

exposure similar to the mild profile: Survival- * deformation of the relay body. Many of the

*in fires corresponding to the'moderate and -; -- outer shells were cracked. Most of the relay

severe profiles is doubtful. bodies were also bowed orwarped, as can be :- seen in Figure 9. The deformation of the relay

Contact resistance measurements for all GE body was evident in each of the GE HFA

--HFA relays were typically below 90 mQ. Load: relays, with some more severe than others.

currents remained stable until failure was The failures for four of the GE HFA relays

observed. Open contact leakage currents were were attributed to warpage of the armature.

i ,. - .

I'

. .

L

- --- ' Figure 9 General Electric HFA Relay D-1 After Thermal Exposure

: . ,

, ,, __!, .. . _ ... ' _ . . . b

 i. , ".. ,  :   - . -, !. . .. -,  , ' - - .  i  

-'. 17 7 ' ' NUREG/CR-6220
Table 2 Overall Relay Test Results

Aged Survived Timeor Peako Temperature or Test 1st Failure Temperature at Failure

Relay # Unaged Profile Order phase (hlmm) (CC) ' (C)' Failure Mode

Agastat Aged Mild 5 Yes 01:04 250.4 250.4 Stuck contact t Base

Al shorted

Agastat Aged Mild 6 No 00:24 241.1 209.7 Rectification circuit

A2 failure

Agastat Unaged Mild 1 No 00:11 206.4 206.4 Rectification circuit

A3 failure

Agastat Unaged Mild 2 No 00:13 220.7 220.7 Rectification circuit

A4 failure

Agastat Unaged Mild 3 No 00:11 214.4 2144 Base shorted

A5

Agastat Unaged Mild 4 No 00:12 214.5 214.5 Base shorted

A6

GE HMA Aged Moderate 13 - Yes 00:49 352.4 129.1 Armature failed to

Bi actuate

GE HMA Aged Severe 14 No 00:23 446.9 446.9 Armature failed to

B2 actuate

GE HMA Unaged Moderate 11 No 00:20 348.2 348.2 Armature fused to

B3 side of relay

GE HMA Unaged Mild 12 Yes 01:19 402.9 402.9 Armature failed to

B4 actuate

GEHGA Aged Moderate 9 No 00:43' 352.6- 150* Armature blocked by CI . . warped top coil plate

GE HGA Aged Moderate 10 Yes 01:38 745.600 S51.900 Armature blocked, C2 relay destroyed

GE HGA Unaged Moderate 7 Yes 01:40 487.7 487.7 Armature failed to

C3 actuate

GE HGA Unaged Severe 8 No 00:36 453.4 4532 Armature failed to

C4 . actuate

GE HFA Aged Moderate 18 No 00:31 358.9 348.7 Armature warped DI

GEHFA Aged Mild 19 Yes 01:26 484.7 484.7 Armature warped

D2

GE HFA Unaged Moderate 15 NO 00:34 3482 297.5 Armature warped D3

GE HFA Unaged Severe 17 No 00:34 563.80* 563.8** Completely D4 destroyed by fire

GE HFA Unaged Mild 16 Yes 01:23 440.0 440.4 Intermittent Failure

D5S

-Exac time and temperature or failure not recorued because o0 a daa logging error. ranlure occuriezu unng cuwl- down ramp at the listed estimated time and temperature.

*Temperatures are higher than expected because the relay's materials ignited and burned.

NUREG/CR-6220 is
5 CONCLUSIONS

This test program assessed the impact of

operational and thermal aging on the thermal

vulnerability of relays. The relays evaluated

were Agastat GPI, General Electric HMA,

General Electric HGA, and General Electric

HFA. At least two relays of each type were

tested in an unaged condition and at least two

relays of each type were artificially aged

before testing. The aged samples were

operationally aged by cycling the relay under

rated load for 2000 operations. These relays

were then subjected to thermal aging for 60

days at a temperature of 110 'C with their

coils energized.

Thermal exposure testing was conducted in

SN1's Severe Combined Environments Test

Chamber (SCETCh). Three exposure profiles

were developed for this test program. These

profiles were representative of generic mild,

moderate, or severe thermal exposures,

respectively.

The Agastat GPI relay results indicated that

most relays would not survive in a mild

exposure (250 'C) environment. However, the

aged samples survived longer than the unaged

samples. Failures were generally traced to the

coil rectification circuit. However, failures in

the base socket were also encountered.

The GE HMA and GE HGA failures were

generally attributed to failure of the armature

to actuate properly. For both relay types, most

of the failures were attributed to an accumulated substance that formed on the top plate of

the coil's spool just below the armature. One

GE HMA relay failure was attributed to the

armature becoming fused to the relay's

housing. One GE HGA relay failure was

caused by the armature failing to actuate

because the top plate of the coil had curled

upwards, preventing movement of the

armature. Aging was not a significant factor in

any of the failures.

The GE HFA relay failures were generally

caused by warpage of the armature arm. This

warpage prevented certain contacts from ally

engaging. One GE HFA displayed an

intermittent coil actuation failure. All of the

relays tested exhibited severe distortion of the

relay body. Aging was not a significant factor

in the failures.

In general, the conclusion is that the effect of

aging on the fire vulnerability of relays

appears to be insignificant. Depending on the

relay type, the effect of exposure to even mild

temperature excursions (>200 'C) may affect

relay integrity independent of the relay's age.

Note that a relay may function properly at a

high temperature for a period of time and

subsequently fail upon cooling. This was

observed in four of the relays tested in this

program (one sample from each relay type).

The most common failure mode observed was

failure of the armature to actuate on

command because of blockage or warpage.

19 19 NUREGICR-6220
6 REFERENCES

1. Lowry, W and Vigil, R. A., "Prioritization

of Reactor Control Components

Susceptible to Fire Damage as a Consequence of Aging," NUREGICR-6103,

SAND93-7107, Science & Engineering

Associates, Inc., for Sandia National

Laboratories, January 1994.

2. Toman, G. J., Bacanskas, V P., Shook, T.

A. and Ladlow, C. C., 'An Aging

Assessment of Relays and Circuit

Breakers and System Interactions,"

Franklin Research Center, NUREG/

CR-4715 (BNL-NUREG-52017), June

1987.

3. Lambright, J. A., Nowlen, S. P., Nicolette,

V. F., and Bohn, M. P., "Fire Risk Scoping

Study: Investigation of Nuclear Power

Plant Fire Risk, including Previously

Unaddressed Issues," NUREG!

CR-5088, SAND88-0177, Sandia

National Laboratories, January 1989.

4. Cline, D. D., von Riesemann, W. A.,

Chavez, J. M., "Investigation of

Twenty-Foot Separation Distance as a

Fire Protection Method as Specified in

10 CFR Part 50, Appendix R,"

NUREG/CR-3192, SAND83-0306,

Sandia National Laboratories, October

1983.

5. Nowlen, S. P., "Enclosure Environment

Characterization Testing for the Base

Line Validation of Computer Fire

Simulation Codes," NUREG/CR-4681,

Sandia National Laboratories, March

1987.

6. Chavez, J. M., Nowlen, S. P. 'An Experimental Investigation of Internally Ignited

Fires in Nuclear Power Plant Control

Cabinets: Part 1: Cabinet Effects Test,

Part 2: Room Effects Test, Part 2: Room

Effects Tests," NUREG/CR-4527, Vols.

1 and 2, SAND86-0336, Vols. 1 and 2,

Sandia National Laboratories, April 1987

and November 1988.

7. Jacobus, M. J., "Screening Tests of Representative Nuclear Power Plant

Components Exposed to Secondary

Environments Created by Fires,"

NUREG/CR-4596, SAND86-0394,

June 1986.

21 NUREG/CR-6220
APPENDIX A

SCETCh TEMPERATURE EXPOSURE PLOTS

FOR ALL RELAYS TESTED
INTRODUCJ7ION -.

In this appendix, the temperature exposure

profiles are shown for each relay tested. Each

figure contains the desired profile (mild,

moderate, or severe) and the actual

temperature profile. Note that the relays were

tested in the order listed in Table 2 in the

report. The thermal exposures were perfomed

in Sandia National Laboratories' Severe

Combined Environments Test Chamber

(SCETCh).

A,

-. I

. I I . r  F _' , .

,.I A-1 A-i NUREG/CR-76220
Teimperature Profile for RdayAl (Agasts)

600

500

j.300

0 200

100 I il mi

0

0 10 20 30 40 SD 60 70 S0 90 100

Tmw (nialfc)

Figure A-1 SCETCh temperature exposure for relay Al

TCpWratm Parufe for Rely A2 (AgBetal)

600

500

j 3400 Foo. /mm

I-200 I

// \Ac PofikI

100 ,i [ Pc..j 

0

0 10 20 30 40 50 60 70 so 90 100

Tume (.TVs)

Figure A-2 SCETCh temperature exposure for relay A2

NUREG/CR-6220A- A-2
~Temperstw. Prefie for Ralay A3 (Agastat)

500

&40

I 2ssmu

j3ro&

0 10 20 30 40 5SO 60 70 3to~ 100

Tim (wim1~s)

Figure A-.3 SCETCh temperature exposure for relay A3

Tempe at=. ?refle for RWhyM 4(Aabt)

500

~-400

i

30

100

0- 10 -20 -30 40 50 60 -70 so go% o

Figure A-4 SCETCh temperature exposure for relay A4

A-3 NUREG/CR-6220
Temperstue ProM. for Relay AS (Apdatm

600

I~g400

r AN

Foahmminid

tooX - mmU prf

0 10 20 30 40 50 60 70 so 90 100

TMW= ) _ .. .

Figure A-5 SCETCh temperature exposure for relay A5

Tempesaw~ Profie for Rely AS(ApzsIa)

600

500

3d00

I- Ac~zd Profile

10

0 10 20 30 40 50 60 70 so 90 100

ThwM (ffiufts)

Figure A-6 SCETCh temperature exposure for relay A6

NUREGICR-6220 A-4
Tempmtp PLroy hefwr Salay 1 (GE MA)

450

400

350

300

-50

: 0 .

~0 10 20 c,3 0 40 50 60 70 to 50 .100

.,,..-.-- m (u m)

I Figure A-7 SCETCh temperature exposure for relay B1

' -' Figure A8 .SCETCh temperature exposure for relay B2

.-;- . A-5 NUREG/CR-6220
- - l

\ / Aehasl Profile

\V/ Medimn Proile

10 20 30 40 50 60 70 so 90 0oo

Tui (udnie)

Figure A-9 SCETCh temperature exposure for relay B3

Taupetruce Profil for Reley Be (GE HMA)

600

500

- 400

j300

200 1 

too

0

0 10 20 30 40 50 60 70 so 90 100

mt (mht)

Figure A-10 SCETCh temperature exposure for relay B4

NUREG/CR-6220 A-6
TVmpnam Prile for Relay Cl (GE HGA)

450

400

350

"O - bwPMo&l

.100 .* giudv~

50

0

0 10 20 30 40 50 60 70 t0 90 .100

. s Z

Figure A-11 SCEICh temperature exposure for relay Cl

Tcuperc Ir*e bor RcyC (Gt HCA)

100,

;0 lo .20 30 ,40 so 60 O mloo9 

600.

. :Figure A-12 SCET~-altemperature exposure for relay C2

-A-7 -NUREG/CR-6220
Tenpecat.. Profe for Reby C3 (CZ HCA)

500

430 FLOP ve

__ 350

ISO

100 I AethulProlo

0 10 20 30 40 SO 60 70 80 90 100

Tw ri (ffies)

Figure A-13 SCETCh temperature exposure for relay C3

Tanpmwwr Proie for Relay C4 (GE HGA)

300

SO

130

a,3O

ISO - Acwal P113file

100

50 - severe Profile

0

0 10 20 30 40 50 60 70 SD 90 100

rum (ArMIS)

Figure A-14 SCETCh temperature exposure for relay C4

NUREG/CR-6220 A-8
Tanpea Mo. Profak for Reby DI (GE TWA)

450

400

350

ISO

0

0 10 20 30 -. 0 so W. 70~ 30 90 100

Taut (mnumes)

Figure A-15 SCETCh temperature exposure for relay D1

Tempevatmo Prftik cr RaayVDi(GEHFA)

E00

SW0I FumOSMd

g 400 I

j3 00 - z e

-~At Dom ,Iw

100 1! , .'' _ _

0 O 10o; 20 30 40 50 6 ' 70 50 90 100

. -. -. -. Tm* (na c)

-, Figure A-16 SCETCh temperature exposure for relay D2

A-9 A-9 NUJREG/CR-6220
Figure A-17 SCETCh temperature exposure for relay D3

Tapempt mrWte hr Rdsy D4 (GE HYA)

__-faemowd 600

500

& 400

1300

100

0

0 10 

VV11

20 30 40 50 60 70 so 90 loo

r1=(fim*3)

Figure A-18 SCETCh temperature exposure for relay D4

NUREG/CR-6220 A-10
Figure A-19 SCETCh temperature exposure for relay D5

A-11 A-il NUREG/CR-6220
APPENDIX B

GLOSSARY
GLOSSARY

um-a micron, one millionth of a meter.

uW-a microwatt, one millionth of a watt (a

unit of power).

angle of incidence-the angle that a ray of light

falling on a surface makes with a ' perpendicular to the surface at the point of

incidence.

angle of reflection-the angle between a

reflected ray of light and a perpendicular to

the surface at the point of reflection.

attenuation-reduction of signal magnitude, or

loss, normally measured in decibels (dB).

avalanche photodiode (APD)-one of two.

semiconductor devices commonly used to

detect light signals and convert them toelectrical signals. The APD can detect very

faint light.; The other device is the PIN diode.

bandwidth-the difference between the high

and low frequencies of a transmission band.

With regard to light signals, the highest

' frequency that can be transmitted in'analog

operation.

bandwidth-length product-the measure of a

fiber's ability to transmit high-speed signals,

stated in MHz-km. It is influenced by modal

dispersion. The bandwidth-length product is

used to determine the bandwidth of a

particular length of fiber by dividing the length

into the bandwidth-length product.

biconic connector-a threaded fiber-optic

connector used in high-speed . 7 

telecommunications. It is designed to bring

* two fiber ends into physical contact,-

miunmizing loss. -.

bit-a binary digit, the smallest unit of

information in a binary system of notation.

bit rate-the rate, or speed, at which bits

(binary digits) are transmitted (e.g., bits per

second).

buffer-the protective coating that covers an

optical fiber.

chromatic dispersion-pulse spreading caused

by variation in light propagation with 7

wavelength. Units are picoseconds (of -

dispersion) per kilometer (of fiber length) per

nanometer (of source spectral width). Laser

sources minimize this effect due to their.

narrow spectral width.

cladding-the reflective outer layer of an

optical fiber that surrounds the light-carrying

core. The cladding retains the light in the core

and allows the fiber to guide light from one

end to the other. Th'e 'cladding has a lower

index of refraction than the core.

disintegration per minute (dpni)-a unit of

activity commonly used in laboratory work

because it is convenient for expressing the

quantities typicaly used.'One curie equals 2.22

X 1012 dpm (1 dpm = 1.67x 10-2 Bq).

dose rate-the absorbed dose delivered per

unit time.

effective dose equivalent (HE)-the sum of the

products of the dose equivalent to the organ

or tissue (HT) and the weighting factors (WT)

applicable to each of the body organs or

tissues that are irradiated. .. - --

eposure-being exposed to ionizing radiation

or to radioactive material.. - :

gamma raqyshort-wave lengthielectromagnetic radiation of nuclear origin emitted from

the nucleus.'

Geiger-Muellercounter-a gas-filled radiationdetection device that is highly sensitive.

'labelling (radiolabelling)-a procedure in which

one or more radioactive atoms are attached to

a molecule or compound in order to follow the

compound or its fragments through physical,

chemical, or biological processes by observing

the radioactivity.

liquid scintillation counting-the detection of

light emissions (scintillation) resulting from

B-1 BINUREG/CR-6220
decay of radioactive material immersed in a

special chemical mixture.

metrcprefixes-prefixes used with metric units

to express numbers in a convenient form.

micro (ti) = 10-6

milli (m) = 10-3

kilo (k) = 103

mega(M) = 106

giga (G) = 109

phantom-a device used to approximate a

human body for the calibration and

adjustment of radiation-measuring

instruments

public dose-the dose received by a member of

the public from exposure to radiation and to

radioactive material released by a licensee, or

to another source of radiation either within a

licensee's controlled area or in an unrestricted

area. It does not include occupational dose or

dose received from background radiation, as a

patient from medical practices, or from

voluntary participation in medical research

programs.

qualty assurance (QA)-planned and

systematic actions to ensure the accuracy of

measurements.

quality control (QC)-routine inspections and

tests to verify the continued accuracy of the

measurements.

radioactive decay-the disintegration of the'

nucleus of an unstable nuclide by spontaneous

emission of charged particles and/or photons.

radioactive half-life--the time required for a

radioactive substance to lose 50 percent of its

activity by decay.

radionuclide-a radioactive nuclide; a nuclide

is characterized by the number of protons and

the number of neutrons in its nucleus.

Standard Man-a person with the anatomical

and physiological characteristics defined in the

report of the ICRP Task Group on Reference

Man (ICRP Publication 23).

sievert-the SI unit of any of the quantities

expressed as dose equivalent. The dose

equivalent in sieverts is equal to the absorbed

dose in grays multiplied by the quality factor

(I Sv = 100 rems).

survey-an evaluation of the radiological

conditions and potential hazards incident to

the production, use, transfer, release, disposal,

or presence of radioactive material or other

sources of radiation.

total effective dose equivalent (TEDE)-the

sum of the deep-dose equivalent (for external

exposures) and the committed effective dose

equivalent (for internal exposures).

TypeA speciftc license of broad scope-a

specific license of broad scope authorizes a

wide range of radionuclides in any chemical or

physical form for a variety of purposes. A Type

A licensee is required to establish a radiation

protection committee.

void-verb: to evacuate urine; noun: the entire

volume of body waste eliminated in a

particular time.

whol-body counting-to measure directly, the

radiation emitted from radioactive material

deposited in the organs and tissues of a body,

using one or more radiation detectors to scan

the entire body or a large fraction of the body.

A variety of detector systems are used for

whole-body counting.

wipe test-an evaluation of removable

contamination on a surface or object, wherein

an absorb~ent material such as paper is rubbed

across a surface and subsequently analyzed for

radioactivity by a counting instrument.

NUREG/CR-6220B- B-2
NRC FORM 335 US. NUCLEAR REGULATORY COMMSSION 1 . REPORT NUMBER C2Aaeimgad by NRC. Add Vol.. Supp.. Rev.. NRCM I 102, Addwwm Numtr It".) 3201o. BIBUOGRAPHIC DATA SHEET Pe kufm on W rvn)NUREG/CR-6220

SAND94-0769 2. TITLE AD SUBTITLE

I DATE REPORT PUBUSHED

An Assessment of Fire Vulnerability for Aged Electrical Relays MONTH YEA

May 19XX 4. FIN OR GRANT NUMBER

A1833

. AUTHOR(S) 6. TYPE OF REPORT

Technical

. A. Vigil,* S. P. Nowlen 7. PEOCOVERE D)

. PERFORMNG ORGANZATION - NME AND ADDRESS (N NRC. PMv DWAwn. Cff= or Regkn U N. WOW Re"Iy Coic aw INV If WW*=r poio an. N no fulu addem)

Sandia National Laboratories Science & Engineering Associates, Inc.

Albuquerque, NM 87185-0737 6100 Uptown Blvd. NE

Albuquerque, NM 87110

9. SPONSORNORGNMAAION-NAME ANADAGRSNF rCa lyp. " ,eR.S oaorproND. o10OvaoorRegko.US.NSderRegtorConwioNd .Rabov.;NIf 

- -)

Division of Engineering

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

1a SUPPLEMAENTARYNOTES

John E. Doe, NRC Project Manager

11. ABSTRACT 90D orIe_)

This report describes testing to assess the impact of aging on the fire vulnerability of Agastat and General

Electric relays. Both aged and unaged relays were tested. Aged relays were subjected to operational

cycling under rated load and thermally aged for 60 days. All relays were exposed to one of three different

fire temperature profiles in the Severe Combined Environments Test Chamber located at Sandia

National Laboratories. The ability to operate properly in the given fire environment was monitored.

Results for the aged and unaged relays were examined to determine the impact of aging on the relays'

ability to sustain operation under the test conditions. Overall results indicated that the aged relays'

performance was not significantly different from that of the unaged relays.

lZ KEY WORDS/DESCRPTORS fu o pita... ff wso ressiws in Woolng to mpom) 13. AVAABKJTY STATEMENT

Unlimited . t14. SECLIRITY CLASSFICATION

Aging IFrw 1

Relays Unclassified

Fire vulnerability (Ak RKpon)

Unclassified

I& NUMBER OF PES

la. PRICE

NRC FORM 335 2-
NRC FORM 335 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(2-9) 1(Assigned by NRC. Add Vol, Supp, Rev,

NRCM 102,and Addendum Numfbers, if any.) 3M. 3202 BIBLIOGRAPHIC DATA SHEET

(See Insructons on Fe reverse)

2. TITLE AND SUBTITLE NUREG-0650. Rev. 2

Preparing NUREG-Series Publications

3. DATE REPORT PUBLISHED

MONTH YEAR

January 1999

4. FIN OR GRANT NUMBER

S. AUTHOR(S) 6. TYPE OF REPORT

7. PERIOD COVERED (Indmusi Dbates)

8. PERFORMING ORGANIZATION -NAME AND ADDRESS (IfNRCa pndeC4sbn. Offnc orRegpbn U.S. NuderReAty Conrssion., and.maiddeuiss:fmntror,

prvvide name and anrrg address.)

Information Management Division

Office of the Chief Information Officer

U. S. Nuclear Regulatory Commission

Washington, DC 20555-0001

9. SPONSORING ORGANIZATION -NAME AND ADDRESS (If NRC. Sae Same as aboveqfrdorprovde NRC Divisbn OfllceorRe9ion, US NucAearRegufaotoyCommrssfon, and nmwlg address.)

10. SUPPLEMENTARY NOTES

Juanita F. Beeson, Project Manager .

11. ABSTRACT (200 words rjrbss)

The guidance in this publication is for the staff and contractors who prepare manuscripts to be published In the NUREG series

for the U.S. Nuclear Regulatory Commission (NRC). This revision 2 to NUREG-0650, "Publishing Documents in the NUREG

Series," is retitled "Preparing NUREG-Series Publications. It gives more concise and up-to-date guidance, including certain

Internet and World Wide Web addresses. It describes how to cite references to electronic information and, in addition, refers

the NRC staff to online style guidance for Web site publishing.

1Z KEY WORDS/DESCRIPTORS (List words orphrss Va wwassistesearhers in cabsg a* report) 13. AVAiLABILITY STATEMENT

NUREG-series publications unlimited

NRC publications in the NUREG series 14. SECURITY CLASSIFICATION

report guidance Mirpage)

report style unclassified

reports (g,.* R"

unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 335 (249) This form was electonically produced by Erite Federat Foms. Irr-
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Federal Recycling Program