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Regulatory and Technical Reports (Abstract Index Journal). Annual Compilation for 1996
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	NUREG-0304, NUREG-0304-V21-N04, NUREG-304, NUREG-304-V21-N4, NUDOCS 9705010326
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NUREG-0304 Vol. 21, No. 4 Regulatory and Technical Reports (Abstract Index Journal)

Annual Compilation for 1996 U.S. Nuclear Regulatory Commission office ofInformation Resources Management

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AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1.

The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.

The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328 3.

The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; j

vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.

The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, grantee reports, and NRC booklets and bro-a chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission issuances.

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Documents available from the National Technical information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices. Federal l

and State legislation, and congressional reports can usually be obtained from these libraries.

l Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.

Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.

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, Rock-ville, MD 20852-2738, for 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, from the American National Standards institute,1430 Broadway, New York, NY 10018-3308.

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NUREG-0304 l

Vol. 21, No. 4 l

Regulatory and Technical Reports (Abstract Index Journal)

Annual Compilation for 1996 i

Date Published: April 1997 M. A. Sheehan, Project Manager Publications Branch Office ofInformation Resources Management U.S. Nuclear Regulatog Commission Washington, DC 20555-0001 y====e,

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CONTENTS Preface v

f Index Tab Main Citations and Abstracts.

1 Staff Reports e

Conference Proceedings e

Contractor Reports e

Grant Reports e

international Agreement Reports e

Secondary Report Number index 2

Personal Authorindex 3

Subject index.

4 NRC Originating Organization Index (Staff Reoorts) 5 NRC Originating Organization index (International Agreements) 6 NRC Contract Sponsor Index (Contractor Reports) 7 Contractor Index..

8 International Organization Index 9

Licensed Facility index 10 l

ill

l PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be appreciated. Please send them to:

Publications Branch Office of information Resources Management T-6 E7 U.S. Nuclear Regulatory Commission Washington, D.C. 20555- 0001 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NU-REG /CP-XXXX, NUREG/CR XXXX, and NUREG/lA-XXXX. These precede the following indexes:

Secondary Report Number Index Personal Author Index Subject index NRC Originating Organization Index (Staff Reports)

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor Index (Contractor Reports)

Contractor index International Organization Index Licensed Facility Index A detailed explanation of the entries precedes each index.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0808: MARKllCONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA. ANDER-SON, C. J. Division of Safety Technology. August 1981. 90 pp. 8109140048. 09570:200.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System acces-sion number, (8) the microfiche address (for internal NRC use).

Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABIL-ITY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.

141 pp. 8105280299. ANL-81-3. 08632:070.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization, (9) the microfiche ad-dress (for NRC internal use).

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Contractor Report

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NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R. Sandialabo-ratories. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.

l Where the entries are (1) report number, (2) report trtle, (3) report authors, (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization (if given), (9) the micro-fiche address (for NRC internal use).

Grant Report NUREG/GR-0013: APPLICATIONS OF A NEW MAGNETIC MONITORING TECHNIQUE TO IN SITU EVAL-UATION OF FATIOUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; BINER, S.B.; GOVINDARAJU, M.; et al. Iowa State Univ., Ames. IA. June 1994. 41 pp. 9407250286. 80328:195.

Where the entries are(1) report number, (2) report title, (3) report authors, (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization (if given), (9) the micro-fiche address (for NRC internal use).

International Agreement Report NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftweek Union. August 1986. 223 pp. 8608270424. 37659:138.

Where the entries are(1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System acces-sion number, (8) the report number of the originating organization (if given), and (9)the microfiche address (for NRC internal use).

The following abbreviations are used to identify the document status of a report:

ADD addendum APP

- appendix DRFT - draft ERR

- errata N - number R - revision S

supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO) or from the National Technical Information Service, Springfield, Virginia 22161. To purchase docu-ments from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:

Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202) 512-2249 or (202) 512-2171. Non-U.S. customers must make payment in ad-vance e'rther by International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.

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NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated re-port. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identifi.

cation replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being re-ported.

In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference pro-ceedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for international agreement reports.

Allthese report codes are controlled and assigned bythe staff of the Publications Branch of the NRC Office of Information Resources Management.

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Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is en NRC staff-onginated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement re aort. The bibliographic information (see Preface for details) is followed by a brief abstract of t1is report.

NUREG-0020 V20: LICENSED OPERATING REACTORS STATUS a quarterly report of such occurrences to be made to Congress.

SUMMARY

REPORT. Data As Of December 31, 1995.(Gray This report provides a desenption of those incidents and events Book i) HARTFIELD,R.A. Office of information Resources Man-that have been determined to be AOs during the period of April l

agement (Post 890205). June 1996. 342pp. 9606250180.

1 through June 30, 1995. This report addresses five AOs at 88702:001.

NRC-licensed facihties. One involved a reactor coolant system The Nuclear Regulatory Commission's annual summary of li-blowdown at a pressurized water reactor (PWR) nuclear power consed nuclear power reactor data is based primarily on the plant, one involved a previously unidentified path for the poten-report of operating data submitted by licensees for each unit for tial release of radioactivity at a PWR nuclear power plant, two the month of December because that report contains data for involved medical brachytherapy misedministrations, and one in-the month of December, the year to date (in this case calendar volved a medical therapeutic radiopharmaceutical misadminis-year 1995) and cumulative data, usually from the date of com-tration. Four AOs submitted by the Agreement States are in-mercial operation. The data is not independentfy venfied, but ciuded. One involved a medical teletherapy misadministration, i

vanous computer checks are made. The report is div6ded into invM MW Mchyt% Mminim%nt ed me two sections. The first contains summary highlights and the involved the overexposure of personnel at a medical center.

second contains data on each individual unit in commercial op-I The repwt also contains an update of one AO previously report-eration. Section 1 capacity and availability : actors are simple anthmetic averages. Section 2 items in the cumulative column ed by an NRC licensee and two AOs previously reported by the are generally as reported by the l6censee and notes as to the Agreement States. No "Other Events of interest" items are use of weighted averages and starting dates other than com.

being reported.

NUREG-0000 V18 NO3: REPORT TO CONGRESS ON ABNOR-NUREG-0040 Vit N04: LICENSEE CONTRACTOR AND MAL OCCURRENCES.luty-September 1995.

Office for Analy-VENDOR INSPECTION STATUS REPORT. Quarte ty sis & Evaluation of Operational Data, Director. February 1996.

Report, October-December 1995.(White Book)

Office of Nucle-23pp. 9602280295. 87272:268.

ar Reactor Regulation (Post 941001). February 1996. 73pp' Section 208 of the Energy Reorganization Act of 1974 identi-a an abnamal occunem M as an unsMM WM a

er the results of inspections performed by w eved mat me Nuclear Regdatwy Comme deWnes to the NRC's Special inspection Branch, Vendor inspection Sec-be Wg* ant from me stan@nt of puMc heam a safey and tion, that have been distributed to the inspected organizations requires a quarterly report of such occurrences to be made to during the penod from October through December 1995.

Congress. This report provides a description of those incidents NUREG-0040 V20 N01: LICENSEE CONTRACTOR AND and events that have been determined to be AOs during the VENDOR INSPECTION STATUS REPORT, Quarterly period of July 1 through September 30,1995. This report ad-ReportJanuary-March 1996(White Book)

Office of Nuclear dresses three AOs at NRC-licensed facilities. Two involved Reactor Regulation (Post 941001). May 1996. 91pp.

medical brachytherapy misadministrations and one involved in-9606250166. 88701:237.

gestion of radioactive material by research workers. One AO This periodical covers the results of inspections performed by submitted by the Agreement States is included. It involved im-the NRC s Special Inspection Branch, Vendor inspection Sec-portation into the United States of a package having exceserve tion, that have been distributed to the inspected organizations radiation. No updates of previously reported AOs are included in during the period from January through March 1996.

this report. No "Other Events of Interest" items are being re.

NUREG-0040 V20 N02: LICENSEE CONTRACTOR AND ported.

VENDOR INSPECTION STATUS REPORT. Quartorty Report. April-June 1996.(White Book)

Office of Nuclear Reac-NUREG-0304 V20 N03: REGULATORY AND TECHNICAL RE-tor Regulation (Post 941001). August 1996. 224pp.

PORTS (ABSTRACT INDEX JOURNAL). Compilation For Third 9609100272. 89604:009.

Quarter 1995, July-September.

Division of Freedom of informa-This periodical covers the results of inspections performed by tion & Publications Services (Post 940714). January 1996.48pp.

the NRC's Special Inspection Branch, Vendor inspection Sec-9602220246. 87210:306.

tion, that have been distributed to the inspected organizations This joumal includes all formal reports in the NUREG series during the period from April through June 1996.

prepared by the NRC staff and contractors; proceedings of con-NUREG-0090 V18 N02: REPORT TO CONGRESS ON ABNOR-ferences and workshops; as well as intemational agreement re-MAL OCCURRENCES. April-June 1995.

Office for Analysis &

ports. The entnes in this compilation are indexed for access by Evaluation of Operational Data, Director. October 1995. 29pp.

title and abstract, secondary report number, personal author, 9602120369. 87081:158.

subject, NRC organization for staff and intemational agree.

Section 208 of the Energy Reorganization Act of 1974 identi-ments, contractor, intemational organization, and licensed facili-fies abnormal occurrence (AO) as an unscheduled incident or ty.

event that the Nuclear Regulatory Commission determines to ba sigruficant from the standpoint of public health or safety requires 1

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2 Main Citations and Abstracts NUF EG-0304 V20 N04: REGULATORY AND TECHNICAL RE-NUREG4386 D07: UNITED STATES NUCLEAR REGULATORY PORTS (ABSTRACT INDEX JOURNAL). Annual Compilation COMMISSION STAFF PRACTICE AND PROCEDURE Foi 1995

DMsion of Freedom of information & Publications DIGEST. Commission, Appeal Board And Licensing Board Services (Post 940714). April 1996. 120pp. 9605220248.

Decisions. July 1972 - June 1995.

Office of the General Coun-88319:273.

sel (Post 860701). April 1996.1056pp. 9605220382. 88311:001, See NUREG 0304,V20.NO3 abstract.

This 7th edrbon of the NRC Practice and Procedure Digest i

contains a digest of a number of Commission, Atomic Safety NUREG4304 V21 N01: REGULATORY AND TECHNICAL RE.

and Ucensing Appeal Board, and Atomic Safety and Licensing PORTS (ABSTRACT INDEX JOURNAL). Compilation For First Board decisions issued during the period of July 1,1972 to Quarter 1996, January-March.

DMsion of Freedom of informa-June 30,1995, interpreting the NRC's Rules.

ica a es (Post 940714). June 1996. 43pp.

NUREG 0390 V10: TOPICAL REPOHT REVIEW STATUS.(Blue See NUREG 0304,V20,NO3 abstract.

Dook)

Office of Nuclear Reactor Regulation (Post 941001).

March 1996. 36pp. 9604150318. 87865:283.

NUREG-0304 V21 N02: REGULATORY AND TECHNICAL RE-This report provides industry with procedures for submitting PORTS (ABSTRACT INDEX JOURNAL). Compilation For mpwts, gWance on how the RS. Mar Reg @oy Second Quarter 1996 April June.

DMsion of Freedom of infor-Cwnmisson (NRC) pmcesses and mspoMs to topical mpwt

'" * " * * " 9

"**U'*"

mation & Publications Services (Post 940714). August 1996.

col report's currently accepte'd for review by the 'NRC. This 42pp. 9609100247,89600:307.

See NUREG4304,V20,NO3 abstract.

report is published annually.

i NUREG-0430 V15: LICENSED FUEL FACILITY STATUS MUREG-0325 R19: U.S. NUCLEAR REGULATORY COMMISSION REPORT. Inventory Difference Data. July 1,1994 - June 30, ORGANIZATION CHARTS AND FUNCTIONAL 1995.(Gray Book II). JOY,D.R. Office of Nuclear Material Safety STATEMENTS. January 31, 1996.

Ofc of Personnel (Post

& Safeguards. May 1996.18pp. 9607090152. 88956:319.

870413). January 1996. 67pp. 9603190 t 08, 87510:293.

NRC is committed to the periodic publication of licensed fuel Functional statements and organization charts for the U.S.

facility inventory difference data, following agency review of the Nuclear Regulatory Commission offices, divisions, and branches information and completon of any related NRC investigations.

are presented.

Information in this report includes inventory difference data for active fuel fabrication facilities possessing more than one effec-NUREG-0325 R20: U.S. NUCLEAR REGULATORY COMMISSION tive kilogram of special nuclear material.

NUREG-0525 V02 R04: SAFEGUARDS

SUMMARY

EVENT LIST

)

TATE TS. July 1,1

. Ofc of Pe nnel (Pos 7 July 1996' 68pp' 9608050055' 89244:273' (SSEL). January 1,

1990 Through December 31, 1995.

See NUREG-0325,R19 abstract.

FADDEN M.A.; YARDUMlAN.J. Operations Branch. Juty 1996.

109pp. 9608060289. 89262:238.

NUREG-0325 R21: U.S. NUCLEAR REGULATORY COMMISSION

. The Safeguards Summary Event List provides brief summa-ORGANIZATION CHARTS AND FUNCTIONAL ries of hundreds of safeguards-related events involving nuclear STATEMENTS. August 19, 1996.

Ofc of Personnel (Post mateM w facshs mgdateQ by N RS. Mear Watoy 870413). August 1996. 68pp. 9609100243. 89609:235.

Commission. Events are desenbed under the categories: Bomb-See NUREG-0325,R19 abstract.

a ed, inMon, Ngmgedy Stolen, Danspodam-Mab ed, Tampering / Vandalism, Arson, Firearms-related, Radiological NUREG-0383 V01 R19: DIRECTORY OF CERTIFICATES OF Sabotage, Non-rsdiological Sabotage, and Miscellaneous. Be-j COMPLIANCE FOR RADIOACTIVE MATERIALS cause of the public interest, the Miscellaneous category also in-PACKAGES. Report Of NRC Approved Packages.

Office of cludes events reported involving source material, byproduct ma-terial, and natural uranium, which are exempt from safeguards Nuclear Material Safety & Safeguards. October 1996. 644pp.

9611180287. 90808:001.

recluirements. Information in the event descriptions was ob-U The purpose of this directory is to make available a conven.

ient source of information on packagings approved by the U.S.

NUREG-0540 V17 N11: TITLE LIST OF DOCUMENTS MADE Nuclear Regulatory Commission. To assist in identdying packag-PUBLICLY AVAILABLE. November 1-30, 1995.

Division of ing, an index by Model Number and corresponding Cert $cate of Freedom of Information & Publications Services (Post 940714).

Compliance Number is included at the front of Volumes 1 and January 1996. 286pp. 9602220190. 87212:001.

2. An alphabetical listing by user name is included in the back This document is a monthly publication containing descrip-of Volume 3 of approved Quality Assurance programs. The re-tions of Information received and generated by the U.S. Nuclear ports include a listing of all users of each package design and Regulatory Commission (NRC). This information includes (1) approved Quality Assurance programs prior to the publication docketed material associated with civilian nuclear power plants date.

and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as NUREG 0383 V02 R19; DIRECTORY OF CERTIFICATES OF a regulatory agency. The following indexes are included: Per-COMPLIANCE FOR RADIOACTIVE MATERIALS sonal Author, Corporate Source, Report Number, and Cross PACKAGES Certificates Of Compliance.

Office of Nuclear Ma.

Reference of Enclosures to Principal Documents.

terial Sa ty & Safeguards. October 1996. 599pp. 9611180288.

NUREG-0540 V17 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. December 1-31, 1995.

Division of See NUREG-0383,V01,R19 abstract

Freedom of Information & Publications Services (Post 940714).

NUREG-0383 V03 R16: DIRECTORY OF CERTIFICATES OF February 1996. 298pp. 9603260311. 87641:001.

I COMPLIANCE FOR RADIOACTIVE MATERIALS See NUREG-0540,V17,N11 abstract.

l PACKAGES. Report Of NRC Approved Quality Assurance Pro-NUREG-0540 V18 N01: TITLE LIST OF DOCUMENTS MADE grams For Radioactive Materials Packages.

Office of Nuclear PUBLICLY AVAILABLE. January 1-31, 1996.

Division of Free.

Material Safety & Safeguards. October 1996. 180pp.

dom of information & Publications Services (Post 940714).

9611180289. 90819 001.

March 1996. 276pp. 9604230386. 87993:001.

See NUREG4383,V01,R19 abstract.

See NUREG 0540,V17,N11 abstract.

Main Citations and Abstracts 3

NUREG-0540 V18 N02: TITLE LIST OF DOCUMENTS MADE The Nuclear Regulatory Commission (NRC) and the Federal PUBLICLY AVAILABLE. February 1 29, 1996.

Dwisson of Free-Emergency Management Agency (FEMA) have added Siipple-dom of Information & Publications Services (Post 940714). April ment 3 to NUREG-0654/ FEMA-REP 1, Revision 1, which pro-1996. 264pp. 9605220337. 88310:001.

vides guidance for development of protectue action recommen.

See NUREG-0540,V17,N11 abstract.

dations for the public for severe reactor accidents involving NUREG-0540 V18 NO3: TITLE LIST OF DOCUMENTS MADE actual or projected core damage with the potential for loss of containment. Studies of severo reactor accidents and their con-PUBLICLY AVAILABLE. March 1 31, 1996.

Division of Free-1 sequences since the issuance of NUREG-0654/ FEMA-REP-1, dom of information & Pubications Services (Post 940714). May Revision 1, have led the NRC staff to conclude that the pre-1996. 319pp. 9606070098. 88487:001.

See NUREG-0540,V17,N11 abstract.

fened Mal protectue acbon 6 a sevem (com damage) an dent is to evacuate promptly rather than to shelter the popula-NUREG-0540 V18 N04: TITLE LIST OF DOCUMENTS MADE tion near the plant, bamng any constraints to evacuation. The PUBLICLY AVAILABLE. April 1-30, 1996.

Division of Freedom guidance in this document is intended to update and simphfy of information & Publications Services (Post 940714). June the decisionmaking process for protectue actions for severe re-1996. 425pp. 9606250175. 88700:001.

actor accidents grven ir Appendix 1 to NUREG-0654/ FEMA-See NUREG-0540,V17,N11 abstract.

REP-1, Revision 1.

NUREG-0540 V18 N05: TITLE LIST OF DOCUMENTS MADE NUREG-0700 R01 V01: HUMAN-SYSTEM INTERFACE DESIGN PUBLICLY AVAILABLE. May 1-31, 1996.

Division of Freedom REVIEW GUIDELINES. Process And Guidelines. Final Report.

of information & Pubications Services (Post 940714). July 1996.

Division of Systems Technology (Post 941217) June 1996.

367pp. 9608050217. 89245:233.

489pp. 9611260297. 90919:118.

See NUREG-0540,V17,N11 abstract.

NUREG-0700, Rev.1, provides human factors engineering NUREG-0540 V18 N06: TITLE LIST OF DOCUMENTS MADE (HFE) guidance to the U.S. Nuclear Regulatory Commission PUBLICf.Y AVAILABLE. June 1-30, 1996.

Dvision of Freedom staff for its: (1) review of the human system interface (HSI) of Information & Pubications Snvices (Post 940714). August design submittals prepared by licensees or applicants for a li-1996. 300pp. 9609030364. 89546:001.

cense or design certification of commercial nuclear power See NUREG 0540,V17,N11 abstract.

plants, and (2) performance of HSI reviews that could be under.

taken as part of an inspection or other type of regulatory review NUREG-0540 V18 N07: TITLE LIST OF DOCUMENTS MADE nvolving HS1 design or incidents involving human performance.

PUBLICLY AVAILABLE. July 1 31, 1996.

Drvision of Freedom The guidance consists of a review process and HFE guidelines.

of information & Pubications Services (Post 940714). Septem-The document describes those aspects of the HSI design ber 1996. 356pp. 9612040128. 91005:001.

review process that are irnportant to the identification and reso-See NUREG-0540,V17,N11 abstract.

lution of human engineering discrepancies that could adversely NUREG-0540 V18 N08: TITLE LIST OF DOCUMENTS MADE affect plant safety. Guidance is provided that could be used by PUBLICLY AVAILABLE. August 1 31, 1996.

Division of Free-the staff to review an applicants HSI design review process or dom of information & Publications Services (Post 940714). Oc-to guide the development of an HSI design review plan, e.g., as tober 1996. 318pp. 9611180279. 90810:001, part of an inspection actrvity. The document also provides de-See NUREG-0540,V17,N11 abstract.

tailed HFE guidelines for the assessment of HSI design imple-mentations. NUREG-0700, Revis;on 1, consists of three stand-NUREG 0540 V18 N09: TITLE LIST OF DOCUMENTS MADE alone volumes. Volume 1, Human System Interface Design PUBLICLY AVAILABLE. September 1 30, 1996.

Division of Review Guideline: Process and Guidelines, is the principal tech-Froedom of Information & Publications Services (Post 940714).

i nical document and provides a detailed discussion of both the November 1996. 324pp. 9612110223. 91063:001.

review procedures and HFE guidelines. Volume 2, Human See NUREG-0540,V17,N11 abstract.

System Interface Design Review Guideline: Reviewer's Check-NUREG-0540 V18 N10: TITLE LIST OF DOCUMENTS MADE list, provides the HFE guidelines in a checklist format. Volume PUBLICLY AVAILABLE. October 1 31, 1996.

Division of Free-3, Human System interface Design Review Guideline: Review dom of Information & Publications Services (Post 940714). De-Software and User's Guide, contains an interactiva software ap-cember 1996. 350pp. 9701130175. 91398:001.

plication to supoort design reviews.

See NUREG-0540,V17,N11 abstract.

NUREG4700 R01 V02: HUMAN-SYSTEM INTERFACE DESIGN NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND REVIEW GUIDELINES. Reviewer's Checklist. Final Report.

Divi-l EVALUATION OF RADIOLOGICAL EMERGENCY RESPONSE sion of Systems Technology (Post 941217). June 1996. 500pp.

PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR 9611260290. 90918:001.

POWER PLANTS.Critena For Emergency P;anning in An Early See NUREG-0700,R01,V01 abstract.

Site Permit Application. Draft Report For Comment. KANTOR,F.;

FOX,E.F. Offee of Nuclear Reactor Regulation (Post 941001).

NUREG-0700 R01 V03: HUMAN-SYSTEM INTERFACE DESIGN WINGERT,V.L.; et al. Federal Emergency Management Agency.

REVIEW GUIDELINES. Review Software And User's Guide. Final April 1996. 32pp. 9605220244. FEM A-REP-1. 88314:302.

Report.

Division of Systems Technology (Post 941217). June i

The Nuclear Regulatory Commission (NRC) and the Federal 1996. 42pp. 9611260324. 90920:305.

l Emergency Management Agency (FEMA) have added Supple.

See NUREG-0700,R01,V01 abstract.

ment 2 NUREG-0654/ FEMA-REP 1, Revision 1, to provide guid-NUREG-0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT l

Ence for the development, review, and approval of radiological COMMERICAL NUCLEAR POWER REACTORS AND OTHER l

cmergency information and plans submitted with an earty site FACILITIES,1994. Twenty-Seventh Annual Report.

l permit application under Subpart A of 10 CFR Part 52.

THOMAS,M.L Division of Regulatory Applications (Post NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND 941217). HAGEMEYER,D. Science Applications Intemational EVALUATION OF RADIOLOGICAL EMERGENCY RESPONSE Corp. (former1y Science Applications, Inc.). January 1996.

PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR 302pp. 9602220240. 87211:001.

POWER PLANTS. Criteria For Protective Action Recommenda-This report summartzes the occupational radiation exposure tions For Severe Accidents. Draft Report For... CONGEL,F.;

information that has been reported to the NRC's Radiation Ex-KANTOR,F.; MCKENNA,T.; et al. Office of Nuclear Reactor posure information Reporting System (REIRS) by nuclear power Regulation (Post 941001). July 1996. 10pp. 9608230202.

facilities and certain other categones of NRC licensees dunng FEMA-REP 1. 89452:321.

the years 1969 through 1994. The bulk of the data presented in l

_ _ ~ _ _ _ _ _ _ _ _ _...

l r

5 i

4 Main Citations and Abstracts the report was obtained from annual redletion exposure reports NUREG4700 V43 N01: NUCLEAR REGULATORY COMMISSION subrnated in accordance with the requirements of 10 CFR ISSUANCES FOR JANUARY 1996. Pages 111.

DMeion of 20.220 and the technical specifications of nuclear power plants.

Freedom of infortnation & Pubhcations Services (Post 940714).

The 1994 annual reporte submitted by about 303 licensees indi-March 1996.17pp. 9603260308. 87624:289.

cated that approximately 15e,028 individuals were rnonitored, See NUREG-0750,V41 abstract.

141,901 of whom were monitored by nucieer power facilsbes.

They incurred an avere0s indledual does of 0.1 rom (cSv) and NUREG4750 V43 N02: NUCLEAR REGUuTORY COMMISSION an average measurebio does of about 0.31 rom (cSv). Analysee ISSUANCES FOR FEBRUARY 1996. Pages 13-49.

DMeion of of transient worker data indicate that 18,178 indMduals com-Freedom of Information & Publications Services (Post 940714).

piehd wwk --

-,6 et two w mwe hcennes during th April 1996. 44pp. $604230336. 87976:198.

monNwing year. h dom distribubons we @ each yew See NUREG-0760,V41 abstract.

2 account fw the dupilcaw reporeng of transient workers by NUREG4700 V43 NO3: NUCLEAR REGULATORY COMMISSION muleple hcensees. In 1994, the average measurable does calcu-ISSUANCES FOR MARCH 1996. Pages 51121.

DMeson of lated from reported data was 0.26 cSv (rom). The corrected Freedom of Informaton & Pubhcations Services (Post 940714).

does distributon resuhed in an avera0s measurable does of May 1996. 79pp. 9605220426. 88310:269.

0.31 cSv (rem).

See NUREG-0750,V41 abstract.

NUREG4725 R11: PUBLIC INFORMATION CIRCULAR FOR NUREG4750 V43 N04: NUCLEAR REGULATORY COMMISSION l

SHIPMENTS OF 1RRADIATED REACTOR FUEL

Office of ISSUANCES FOR APRIL 1996.Page 123-210.

Division of l

Nuclear Material Safety & Safeguards July 1996. 32pp.

Freedom of information & Pubhcations Services (Post 940714).

[

9006210216. 89420:305.

June 1996. 93pp. 9607120203. 80006:158.

This circular has been prepared to provide information on the See NUREG 0750,V41 abstract.

i ohipment of irradiated reactor fuel (opent fuel) subject to reguis-Won by tM Nuclew ReguleMry Commineion (NRC), and to meet NUREG4700 V43 N06: NUCLEAR REGULATORY COMMISSION the requirements of Pubhc Law 96-295. The report provides a ISSUANCES FOR MAY 1996.

Dmeion of Freedom of Informa-brief descrtphon of NRC authonty for certain aspects of trans-tion & Pubhcations Services (Post 940714). July 1996. 30pp.

t pornng spent fuel, it provides descrtpuve statist 6cs on opent fuel 9608060271. 89258:145.

ehipmente regulated by the NRC from 1979 to 1995. It also hets See NUREG 0750,V41 abstract.

detened highway and raNway segments used wHhin each stak NUREG4780 V43 NOS: NUCLEAR REGULATORY COMMISSION from January 1,1993, through December 31,1995.

ISSUANCES FOR JUNE 1996.

DMeion of Freedom of Infor-NUREG4790 V41: NUCLEAR REGULATORY COMMISSION f29pp 5 97 I

ISSUANCES.Operuone And Deciosons Of The Nuclear Reguia-See NUREG-0750,V41 abstract.

l tory Commission With Selected Orders. January 4une 1995.

Di-l vision of Freedom of informanon & Pubhcanone Services (Post NUREG4750 V44 N01: NUCLEAR REGULATORY COMMISSION 1

l 940714). February 1996. 547pp. 9604020257. 87709:001.

ISSUANCES FOR JULY 1996.Pages 1-57,

Dmeion of Free-Legal issuanoes of the Co,,,,,M-7, the Atomic Safety and Li-dom of Information & Pubhcations Services (Post 940714). Sep-conoing Board Panel, the Admirustrative Law Judges, and NRC tomber 1996. 63pp. 9612040113. 91004:236.

Program Offices are presented.

See NUREG-0750,V41 abstract.

NUREG4700 V42102: INDEXES TO NUCLEAR REGULATORY NUREG4780 V44 NO2: NUCLEAR REGUuTORY COMMISSION COMMISSION ISSUANCES. July-December 1995.

DMeion of ISSUANCES FOR AUGUST 1996. Pages 59-78.

DMsion of l

Freedom of information & Publicatone Services (Post 940714).

Freedom of Information & Pubhcations Services (Poet 940714).

March 1996. 40pp. 9604020329. 87710:255.

October 1996. 27pp. 9611190210. 90824:321.

Digeste and indexes for issuances of the Commiseson, the See NUREG-0750,V41 abstract.

Atomic Safety and Llooneing Board Panel, the Administrative NUREG4700 V44 NO3: NUCLEAR REGULATORY COMMISSION Law Judges, the Directors' Decisions, and the Decisions on Po-t ISSUANCES FOR SEPTEMBER 1996. Pages79-106.

DMeion titions for Rulemaking are presented of Freedom of Information & Publications Services (Poet NUREG4750 V42 N05: NUCLEAR REGULATORY COMMISSION U G

,V abs act.

ISSUANCES FOR NOVEMBER 1995. Pages 181219.

DMeion of Freedom of Information & Publications Services (Post NUREG4700 V44 N04: NUCLEAR REGUMTORY COMMISSION 940714). January 1996. 45pp. 9002090022. 87066:244.

ISSUANCES FOR OCTOBER 1996. Pages 107 228.

Dmelon See NUREG-0750,V41 abstract.

of Freedom of information & Publications Services (Post l

940714). December 1996.129pp. 9701150176. 91421:175.

NUREG4760 V42 NOS: NUCLEAR REGULATORY COMMISSION See NUREG-0750,V41 abstract.

ISSUANCES FOR DECEMBER 1995. Pages 221-258.

DMeion of Freedom of information & Pubhcations Services (Post NUREG4000 DRFT PC: STANDARD REVIEW PLAN FOR THE 940714). February 1996. 44pp. 9602280302. 87272:185.

REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR See NUREG 0750,V41 abstract.

POWER PLANTS. LWR Edition. Draft Report For Comment.

i Office of Nuclear Reactor Regulation (Post 941001). June 1996.

NUREG4700 V43101: INDEXES TO NUCLEAR REGULATORY 7,046pp. 9606260017,88730:001.

COMMISSION ISSUANCES. January. March 1996.

DMoson of The Standard Review Plan (SRP) provides guidance to staff Freedom of Information & Pubhcations Services (Post 940714).

reviewers in the Office of Nuclear Reactor Regulation in per.

June 1996. 25pp. 9607090246. 88956:33,,

forming safety reviews of apphcations to construct or operate See NUREG-0750,V42,102 abstract.

nuclear power plants. The pnncipal purpose of the SRP is to i

aneure the quality and uniformity of staff safety reviews. In l

NUMEG4700 V43102: INDEXES TO NUCLEAR REGULATORY 1991, the Standard Review Plan Update and Development Pro-COMMISSION ISSUANCES. January-June 1996.

DMeion of gram (SRP-UDP) was established to update NUREG-0800 for Freedom of'information & Pubhcations Services (Poet 940714).

use in reviewing future reactor design applications. An "Imple-l September 1996. 49pp. 9612040124. 91007:012.

menting Procedures Document (IPD)", NUREG-1447, was l

See NUREG-0750,V42,102 abstract.

issued May 1992 to describe the SRP-UDP and establish the r

l l

l

l Main Citations and Abstracts 5

t procedures for updating the SRP. The pnncipal objectives of the SRP-UDP were to update the SRP to reflect the substantial have a significant potental for reducing risk. The safety prionty changes in regulation and regulatory guidance that occurred rankings are HIGH, MEDIUM, LOW, and DROP, and have been since the 1981 revision of the SRP and to reflect the experi-assigned on the basis of risk significance estimates, the ratio of er%ce of the safety reviews conducted of desegn carbfication ap-

'rtsk to costs and other impacts estimated to result if resolution plications for evolutionary nuclear plants. This document pro-of the safety issues were implemented, and the consideration of vides the results of the update program.

uncertaint>es and other quanttatsve or qualitative factors. To the extent practical, estimates are quantitative.

NUREG 0837 V15 N04: NRC TLD DIRECT RADIATION MONI-NUREG-0933 821: A PRIORITIZATION OF GENERIC SAFETY TORING NETWORK. Progress Report. October-December 1995 SSUES. EMRIT,R. Division of Engineenng Technology (Post STRUCKMEYER.R. Regeon 1 (Post 820201). March 1996-326pp. 9603260299. 87623:001.

2M Ncembw 10E 174pp. 0701130173. 91400:037.

ee O abstract.

This report provides the status and results of the NRC Ther-moluminescent Dosimeter (TLD) Direct Radiation Monitonng NUREG-0936 V14 N02:

NRC REGULATORY Network. It presents the radiatton levels measured in the vicinrty AGENDA.Samiannual Report. July-December 1995.

Division of of NRC licensed facilities throughout the country for the fourth Freedom of Information & Pubhcations Services (Post 940714).

quarter of 1995.

February 1996. 57pp. 9602280332. 87272:290.

NUREG-0837 V18 N01: NRC TLD DIRECT RADIATION MONI.

The NRC Regulatory Agenda is a compilation of all rules on TORING NETWORK. Progress Report. January-March 1996.

which the NRC has recently completed action, or has proposed STRUCKMEYER,R. Region 1 (Post 820201). May 1996. 227pp.

acbon, or is consdenng acbon, and au petibons for rulemaking 9606070096. 88486:026.

which have been received by the Commission and are pending This report provides the status and results of the NRC Ther-disposition by the Commission. The Regulatory Agenda is up-moluminescent Dosimeter (TLD) Direct Radiatson Monitonng dated and issued semiannually.

l Network. It presents the radiation levels measured in the v6cinity NUREG-0936 V15 N01:

NRC REGULATORY of NRC licensed facilities throughout the country for the first AGENDA. Semiannual Report. January-June 1996.

Division of I

quarter of 1996.

j Freedom of Information & Publications Services (Post 940714).

NUREG-0837 V16 N02: NRC TLD DIRECT RADIATION MONI-August 19%. 58pp. 9609100239. 89601:267 i

TORING NETWORK. Progress Report April-June 1996.

See NUREG-0936,V14,N02 abstract.

STRUCKMEYER.R. Region 1 (Post 820201). August 1996.

NUREG-0940 V14N3&4P1: ENFORCEMENT ACTIONS: SIGNIFI-248pp. 9609200268. 89727:134.

CANT ACTIONS RESOLVED INDIVIDUAL This report provides the status and results of the NRC Ther.

i ACTIONS. Semiannual Progress Report, July-December 1995.

moluminescent Dosimeter (TLD) Direct Radiation Monitorin9 Ofc of Enforcement (Post 870413). February 1996. 363pp.

l Network. It presents the radiation levels measured in the vicinity 9603050127.87335:001.

of NRC heensed facilities throughout the country for the second This compilation summartzes significant enforcement actions I

quarter of 1996.

that have been resolved dunng the period (July - December NUREG-0647 S20: SAFETY EVALUATION REPORT RELATED 1995) and includes copies of Orders and Notices of Violation l

TO THE OPERATION OF WATTS BAR NUCLEAR sent by the Nuclear Regulatory Commission to individuals with 1

PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391.(Ten-respect to these enforcement actions. It is anticipated that the nessee Valley Authority) TAM,P.S. Office of Nuclear Reactor information in this publication will be widely disseminated to Regulation (Post 941001). February 1996. 36pp. 9602280321.

managers and employees engaged in activities licensed by the 87272:231.

NRC. The Commission believes this information may be useful Supplement No. 20 to the Safety Evaluation Report for the to licensees in making employment decisions.

application filed by the Tennessee Valley Authority for license to NUREG-0940 V14N3&4P2: ENFORCEMENT ACTIONS: SIGNIFl.

operate Watts Bar Nuclear Plant, Units 1 and 2, Ducket Nos.

CANT ACTIONS RESOLVED REACTOR 50-390 and 50-391, located in Rhea County, Tennessee, has LICENSEES. Semiannual Progress Report, July-December 1995.

been prepared by the Office of Nuclear Reactor Regulation of

Ofc of Enforcement (Post 870413). February 1996. 241pp.

i the Nuclear Regulatory Commission. The purpose of this sup-9603040093. 87314:095.

plement is to update the Safety Evaluation with (1) additional in-This compilation summanzes significant enforcement actions l

formation submitted by the applicant since Supplement No.10 that have been resolved during the period (July - December was issued, and (2) matters that the staff had under review 1995) and includes copies of letters, Notices, and Orders sent l

when Supplement No.19 was issued.

by the Nuclear Regulatory Commission to reactor licensees with NUREG-0910 R02 802: NRC COMPREHENSIVE RECORDS DIS.

respect to these enforcement actions. It is anticipated that the POSITION SCHEDULE.

Information & Records Management information in this publication will be widely disseminated to i

Br!.nch (Post 890827). February 1996.195pp. 9605220230.

managers and employees engaged in activities licensed by the I

88332:076.

NRC, so that actions can be taken to improve safety by avoid-I The approved records disposition schedules specify the ap-ing future violations similar to those described in this publica.

propriate duratim of retention and the final disposstion for tion.

records created or maintained by the NRC NUREG-0910, Revi-NUREG-0940 V14N3&4P3: ENFORCEMENT ACTIONS: SIGNIFl.

sion 2, Supplement 2 makes editorial and administrative CANT ACTIONS RESOLVED MATERIAL changes to the National Archives and Records Administration's General Record Schedule (GRS) and forwards an entire updat-L.ICENSEES. Semiannual Progress Report, July-December 1995.

Ofc of Enforcement (Post 870413). February 1996. 250pp.

ed set of the General Records Schedule including GRS Subject 9603260287. 87620:001.

cnd Forms indexes.

This compilation summarizes significant enforcement actions NUREG-0933 820: A PRIORITIZATION OF GENERIC SAFETY that have been resolved during the period (July - December ISSUES. EMRIT,R. Division of Engineering Technology (Post 1995) and includes copies of letters, Notices, and Orders sent 94f 217). July 1996. 232pp. 9608050226. 89245:001.

by the Nuclear Regulatory Commission to material licensees The report presents the safety pnonty ranking for generic with respect to these enforcement actions. It is anticipated that saf!ty issues related to nuclear power plants. The purpose of the information in this publication will be widely disseminated to these rankings is to assist in the timely and efficient allocation managers and employees engaged in activities licensed by the of NRC resources for the resolution of those safety issues that NRC, so that actions can be taken to improve safety by avoid-I

6 Main Citations and Abstracts ing future violations similar to those desenbed in this publica-NUREG-1145 V12: U.S. NUCLEAR REGULATORY COMMISSION 1995 ANNUAL REPORT.

Office of Administration, Director tson.

(Post 940714). August 1998. 337pp. 9611210208. 90885:001.

HUREG-0940 V15 N1 P1: ENFORCEMENT ACTIONS: SIGNIFI-This report covers the major actrvibes, events, decisions, and CANT ACTIONS RESOLVED INDIVIDUAL planning that took place during Fiscal Year 1995 wrthin the U.S.

ACTIONS. Semiannual Progress Report, January-June 1996.

Nuclear Regulatory Commission (NRC) or involving the NRC.

Ofc of Enforcement (Post 870413). August 1996. 375pp.

NUREG-1214 R14: HISTORICAL DATA

SUMMARY

OF THE SYS-9609100232. 89603:001.

This compilation summartzes significant enforcement actions TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.

that have been resolved during the period (January - June GAMBERONI.D. Office of Nuclear Reactcf Regulation (Post 1996) and includes copees of Orders and Notices of Violabon 941001). October 1996. 50pp. 9612030264. 90980;109.

sent by the Nuclear Regulatory Commission to individuals with The Historical Data Summary of the Systematic Assessment respect to these enforcement schons. It is anticipated that the of Licensee Performance (SALP) is produced periodically by the informabon in this publicabon will be w6dely disseminated to U.S. Nuclear Regulatory Commission. This summary provides managers and employees engaged in activities licensed by the the results of the assessment of each facility by NRC region NRC. The Commission believes this information may be useful and is further divided into the following sections: Section 1 pre-sents the most recent SALP report ratings for facilities in oper-to licensees in making employment decisions.

ation. Section 2 presents a chronological listing of all SALP NUREG-0940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFl-report ratings for each operating facility since August 1,1988.

CANT ACTIONS RESOLVED REAClOR LICENSEES. Semiannual Progress Report, January-June 1996.

NUREG-1272 V09 Not: OFFICE FOR ANALYSIS AND EVALUA-Ofc of Enforcement (Post 870413). August 1996. 266pp.

TION OF OPERATIONAL DATA.1994-FY 95 Annual Report -

Reactors.

Office for Analysis & Evaluation of Operational 9609100251. 89601:001.

This compilaton summartzes significant enforcement actions Data, Director. July 1996. 306pp. 9609100257, 89600:001.

that have been resolved during the period (January June This annual report of the U.S. Nuclear Regulatory Commis-1996) and includes copies of letters, Notices, and Orders sent sion's Office for Analysis and Evaluation of Operational Data by the Nuclear Regulatory Commission to reactor licensees with (AEOD) describes activities conducted during CY 1994 and FY 1995. The report is published in three parts. NUREG-1272, Vol.

respect to these enforcement actons. It is anticipated that the 9, No.1, covers power reactors and presents an overview of Information in this publication will be widely disseminated to managers and employees engaged in actrvities licensed by the the operating experience of the nuclear power industry from the NRC, so that actions can be taken to improve safety by avoid.

NRC perspective, including comments about the trends of some ing future violations similar to those described in this publica-key performance measures. The report also includes the princi-pal findings and issuos identified in AEOD studies over the past tion.

year and summarizes informahon from such sources as licensee NUREG-0940 V15 N1 P3: ENFORCEMENT ACTIONS: SIGNIFI-event reports, diagnostic evaluations, and reports to the NRC's CANT ACTIONS RESOLVED MATERIAL Operations Center. NUREG-1272, Vol. 9, No. 2, covers nuclear LICENSEES. Semiannual Progress Report. January-June 1996.

materials and presents a review of the events and concerns Ofc of Enforcement (Post 870413). Augwt 1996. 350pp.

dunng 1993 associated with the use of licensed material in non-his ilation iartzes significant enforcement actions m

stra s Both Iso con n a d aru that have been resolved during the period (January - June sion of the incident investigabon Team program and summartze 1996) and includes copies of letters, Notices, and Orders sent both the incident investigation Team and Augmented inspecton by the Nuclear Regulatory Commission to material licensees Team reports. Each volume contains a hst of the AEOD reports witn respect to these enforcement actions. It is anticipated that issued from 1980 through 1995. NUREG 1272, Vol. 9, No. 3, tne information in this publicahon will be widely disseminated to covers technical training and presents the activities of the Tech managers and employees engaged in activities licensed by the nical Training Center in support of the NRC's mission.

NRC, so that actions can be taken to improve safety by avoid-ing future violations similar to those described in this publica-NUREG-1272 V09 N02: OFFICE FOR ANALYSIS AND EVALUA-TION OF OPERATIONAL DATA.1994-FY 95 Annual Report -

tion.

Nuclear Materials.

Office for Analysis & Evaluation of Oper-NUREG-1100 V12: BUDGET ESTIMATES. Fiscal Year 1997.

Di-stional Data, Director. September 1996.184pp. 9612120065.

vision of Budget & Analysis (Post 890205). March 1996,168pp.

91072:144.

9604020325, 87714:001.

See NUREG-1272,V09,N01 abstract This report contains the fiscal year budget justificahon to Con-gress. The budget provides estimates for salaries and expenses NUREG-1272 V09 NO3: OFFICE FOR ANALYSIS AND EVALUA.

and for the Office of the inspector General for fiscal year 1997.

TION OF OPERATIONAL DATA.1994-FY Annual Report -

Technical Training.

Office for Analysis & Evaluation of Oper.

NUREG-1125 V17: A COMPILATION OF REPORTS OF THE AD-ational Data Director. September 1996. 43pp. 9612030287.

VISORY COMMITTEE ON REACTOR SAFEGUARDS.1995 90980:220.

Annual.

ACRS - Advisory Committee on Reactor Safeguards.

See NUREG-1272,V09,N01 abstract.

April 1996.118pp. 9605130141. 88226:142.

This compilabon contains 44 ACRS reports submitted to the NUREG-1307 R06:

REPORT ON WASTE BURIAL Commission, or to the Executive Director for Operations, during CHARGES. Escalation Of Decommissioning Waste Disposal calendar year 1995. It also includes a report to the Congress on Costs At Low-Level Waste Burial Facilitses.

Division of Regula-the NRC Safety Research Program. All reports have been made tory Applications (Post 9J 1217). September 1996. 66pp.

available to the public through the NRC Pubhc Document Room 9609200324.89726:236.

and the U.S. Library of Congress. The reports are divided into One of the requirements placed upon nuclear power reactor two groups: Part 1: ACRS Reports on Project Reviews, and Part licensees by the U.S. Nuclear Regulatory Commission (NRC) is 2: ACRS Reports on Genenc Subjects. Part 1 contains ACRS for the licensees to periodically adjust the estimate of the cost reports by project name and by chronological order within of decommissioning their plants, in dollars of the current year, project name. Part 2 categorizes the reports by the most appro-as part of the process to provide reasonable assurance that pnate generic subject area and by chronological order within adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodi-subject area.

Maln Citations and Abstracts 7

cally, contains the development of a formula for escalating de-to establish generic findings covering as many plants as possi-commissioning cost estimates that is acceptable to the NRC, ble. This geis has three principal objectives: (1) to provide an and contains values for the escalation of radioactive waste understanding of the types and seventy of environmental irn-buriv sosts, by site and by year. The licensees may use the for-pacts that may occur as a result of license renewal of nuclear mula, th6 c.oefficients, and the bunal escalabon from this report power plants under 10 cfr part 54, (2) to identify and assess in their escdhon analyses, or they may use an escalabon rate those irnpacts that are expected to be genonc to license renew-at least equal tc the escalabon approach presented herein, al, and (3) to support a rulemaking (10 cfr part 51) to define the mmbw and scope of issues mat need to be ahssed by the NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION IN-apphcants in plant-by-plant license renewal proceedings. To ac-FORMATION DIGEST.1996 Edition. GARVER,M. Division of complish these objectives, the geic makes maximum use of en-Budget & Analysis (Post 890205). July 1996. 138pp.

me and safeh doceWe #wn Mgmal Mng 9609030260. 89545:001 agemes, me Nclear uW d,M m = and Meral regdatay pr ngs and Wormaton The Nuclear Regulatory Commission Information Digest sW, N open htwahe, and (digest) provides a summary of information about the U.S. No-profess

contacts, clear Regulatory Commission (NRC), NRC's regulatory responsi-bihties, NRC heensed actvities, and general information on do-NUREG-1437 V02: GENERIC ENVIRONMENTAL IMPACT mestic and worldwide nuclear energy. The dgest, published an-STATEMENT FOR LICENSE RENEWAL OF NUCLEAR nually, is a compilation of nuclear and NRC-related data and is PLANTS. Appendices.

Division of Regulatory Applications designed to provide a quick reference to major facts about the (Post 941217). May 1996. 553pp. 9606180469. 88633:001.

agency and the industry it regulates. In general, the data cover See NUREG 1437,V01 abstract.

1975 through 1995, with exceptions noted. Information on gen-NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS erating capactly and average capacity factor for operating U.S.

TO REGULATIONS FOR THE ENVIRONMENTAL REVIEW commercial nuclear power reactors is obtained from monthly FOR RENEWAL OF NUCLEAR POWER PLANT OPERATING operating reports that are submitted directly to the NRC by the hcensee. This information is reviewed by the NRC for consisten.

LICENSES. Final Report.

Division of Regulatory Applications cy only and no independent vahdation and/or verification is per.

(Post 941217). May 1996. 35pp. 9606180288. 88630:327.

' formed.

This regulatory analysis provides the supporting information for a rule that amends the nuclear regulatory commission's re-NUREG-1415 V08 N02: OFFICE OF THE INSPECTOR quirements for environmental review of applications for renewal GENERALSemiannual Report To Congress. October 1,1995 -

of nuclear power plant operating licenses. After considering var.

March 31,1996. BARCHI,T.; WATKINS.B.; GRODIN,M.; et al-ious options, the staff identified and analyzed two major alterna-Office of the Inspector General (Post 890417). June 1996 tives. Alternative a is to not amend the regulations and to per-43pp. 9606180278. 88634:231, form environmental reviews under the existing regulations. Alter.

The inspector General / set of 1978, as amended, requires native b is to assess, on a generic basis, the environmental im-that inspectors General submit a " Semiannual Report to Con-pacts of renewing the operating license of Individual nuclear gress" summartzing program activities. The inspector General's power plants, and define the issues that will need to be further report is submitted to the Chairman of the NRC not later than analyzed on a case-by-case basis. The findings of this assess-April 30, and October 31 for each reporting period. The Chair.

ment are codified in 10 cfr part 51, The staff has selected alter-man comments on the report and prepares the NRC's Semian-native b as the preferred attemative.

nual Report to Congress as required by the Act. The Chairman then submits the agency's report and the OlG's report no later NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE than November 30 and May 31, respectively.

VESSEL SUPPORTS. JOHNSON,R.E. Division of Enginoering Technology (Post 941217). LIPINSKl,R E. Idaho National Engi-NUREG-1415 V09 N01: OFFICE OF THE INSPECTOR neering Laboratory. May 1d96. 200pp. 9605220250. 88321:001.

GENERALSemiannual Report To Congress, April 1,1996 - Sep-The NRC Genenc Safety lasue No.15, (GSI-15), " Radiation tomber 30,1996. BARCHI,T.; WATKINS B.; GRODIN,M.; et al-Effacts on Reactor Pressure Vessel Supports," was established Office of the inspector General (Post 890417). November 1996.

to evaluate the concern that low-temperature, low-flux-level 39 21pE 4i MM-neutron irradiation might embrittle reactor pressure vessel sup-ports to a significant degree and compromise plant safety. Eval.

NUREG-1423 V06: A COMPILATION OF REPORTS OF THE AD.

uation of the surveillance samples from the High Flux Isotope VISORY COMMITTEE ON NUCLEAR WASTE. July 1995 - June Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) 1996.

Advisory Committee on Nuclear Waste. August 1996, led to the conclusion that the embrittlement rates of some ma-54pp. 9609030264. 89547:283.

tenals used for pressurized water reactor pressure vessel (RPV)

This compilation contains 8 reports issued by the Advisory supports could be higher than expected. This disclosure raised Committee on Nuclear Waste (ACNW) during the eighth year of a concem that a bnttle fracture of the RPV supports could its operation. The reports were submitted to the Chairman and occur dunng the anticipated hfe-span of the plant. A later study i

Commissioners of the U.S. Nuclear Regulatory Commission. All by the ORNL demonstrated that gamma radiation contributed a j

reports prepared by the Committee have been made available significant amount of the embrittlement in the HFIR surveillarce to the pubhc through the NRC Pubhc Document Room, the U.S.

specimens. However, the shiolding provided by the thick steel l

Ubrary of Congress, and the internet at http://www.nrc. gov /

shell of the RPV ensures that degradation of RPV supports from ACRSACNW.

gamma irradiation is improbable or minimal. This report (1) de-s n al ngs ms4 kn N M M M NUREG-1437 V01: GENERIC ENVIRONMENTAL lMPACT accM @ me WS Task Ach Ran aM @ was usM, h STATEMENT FOR LICENSE RENEWAL OF NUCLEAR 1

part, as the basis for technical resolution of the issue.

PLANTS. Main Report.

Division of Regulatory Applications (Post 941217). May 1996. 638pp. 9606180460. 88629:001, NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS The generic environmental impact statement (geis) examines REPORT. ELLIOT,B.J.; HACKETT,E.M.; LEE,A.D.; et al. Office the possible environmental impacts that could occur as a result of Nuclear Reactor Regulation (Post 941001). October 1996.

of renewing licenses of individual nuclear power plants under 10 42pp. 9611180284. 90820:259.

cfr part 54. The geis, to the extent possible, establishes the This report describes the issues raised as a result of the bounds and signricance of these potential impacts. The analy-staff's review of Generic Letter (GL) 92-01, Revision 1, re-i ses in the geis encompass all operating hght-water power reac-sponses and plant-specific reactor pressure vessel (RPV) as-tors. For each type of environmental impact the geis attempts sessments and the actions taken or work in progress to ad-l

8 Main Citations and Abstracts dress these issues. In addition, the report describes actions latter issues are relevant with regard to determining the efficacy taken by the staff and the nuclear industry to develop a thermal of certain accident management strategies for operating reac-annealing process for possible use at U.S. commercial nuclear tors as well as for advanced light water reactors. The experts plants to mit> gate the effects of neutron radiation on the fracture reviewed the status of understanding of the FCI phenomena in toughness of RPV rnatorials. The Nuclear Regulatory Commis-the context of these broader issues, identified residual uncer-sion (NRC) issued GL 92 01, Revision 1, Supplement 1, to tainties in the understanding, and recommended further re-obtain information needed to assess compliance wtth regulatory search (both experimental and analytical) to reduce the uncer-requirements and licensee commitments regarding RPV integrl-tainties.

ty. GL 92-01, Revision 1, Supplement 1, was issued as a result of generic issues raised in the NRC staff's review of licensee NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 responses to GL 92 01, Revision 1, and plant-specific RPV CFR PART 51 RULE FOR RENEWAL OF NUCLEAR POWER evaluations. In particular, an integrated review of all data sub.

PLANT OPERATING LICENSES AND SUPPORTING DOCU-mitted in response to GL 92-01, Revision 1, indicated that li.

MENTS: REVIEW OF CONCERNS AND NRC STAFF censees may not have considered all relevant data in their RPV RESPONSE. Executive Summary.

Division of Regulatory Appli-assessments.

cations (Post 941217). May 1996. 40pp. 9606180325.

88634:190.

NUREG 1518: DIFFERING PROFESSIONAL VIEWS OR OPIN-This report documents the nuclear regulatory commission IONS.1994 Special Review Panel.

Ofc of Personnel (Post (nrc) staff review of public comments provided in response to 870413). September 1996. 79pp. 9612040132. 91007:134.

the nrc's proposed amendments to 10 code of federal regula-In Jufy 1994, the Executive Director for Operations of the U.S.

tions (cfr) part 51, which establish new requirements for the en-Nuclear Regulatory Commission (NRC) appointed a Special vironmental review of applications for the renewal of oporating Review Panel to assess the Diffenng Professional View or Opin-licenses of nuclear power plants. The public comments include ion (DPV/DPO) process, including ".its effectiveness, how well those submitted in writing, as well as those provided at public it is understood by employees, and the organizational climate meetings that were held with other federal agencies, state for having such views aired and property decided." An addition-agencies, nuclear industry representatsves, public interest al ates within this review was to address ".the effectiveness of groups, and the general public. This report also contains the nrc the DoO procedures as they pertain to pubhc access and confi-stati response to the various concems raised, and highlights the dentiallty." Further, the Panel was charged with the review of the submittals completed since the last review to identify em-changes made to the final rule and the supporting documents in response to these concems.

ployees who made significant contributions to the agency or to public health and safety but had not been adequately recog-NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 nized for this contribution. The report presents the Special CFR PART 51 RULE FOR RENEWAL OF NUCLEAR POWER Review Paners evaluation of the NRC's current process for PLANT OPERATING LICENSES AND SUPPORTING DOCU-dealing with Differing Professional Views or Opinions. Provided MENTS: REVIEW OF CONCERNS AND NRC STAFF in this report are the results of an employee opinion survey on RESPONSE. Appendices.

Division of Regulatory Applications the process; highlights and suggestions from interviews with in-(Post 941217) May 1996. 671pp. 9606180333. 88627:001.

dividuals who had submitted a Differing Professional Viow or See NUREG 1529,V01 abstract.

Opinion, as well as with agency managers directly involved with the Differing Professional Views or Opinions process; and the NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT Spec'.al Review Panel's recommendations for improving the RELATED TO RECLAMATION OF THE URANIUM MILL TAIL-DPV/DPO process.

INGS AT THE ATLAS SITE,MOAB, UTAH. Source Material Li-cense No. SUA-917, Docket No. 40-3453. (Atlas Corporation)

NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN BLASING,T.S.; EASTERLY,C.E. Oak Ridge National Laboratory.

ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF FLIEGEL,M.; et al. Division of Waste Management (NMSS THE CURRENT UNDERSTANDING OF BROADER FUEL-940403). January 1996. 300pp. 9602050062. 86981:001, COOLANT INTER ACTION ISSUES. Report Of The Second This Draft Environmental impact Statement (DEIS) has been Steam Explosion Review Group Workshop. BASU.S. Division of prepared by the Nuclear Regulatory Commission (NRC), Office Systems Technology (Post 941217). GINSBERG,T, Brookhaven of Nuclear Material Safety and Safeguards, to address potential National Laboratory. August 1996. 200pp. 9608230217, environmental impacts associated wtth a request by Atlas Cor-89450:001.

poration to amend its existing NRC License No. SUA-917 to re-This report summartzes the review and evaluation by experts claim an existing uranium mill tailings pile near Moab, Utah. The of the current understanding of the molten fuel-coolant interac-proposed reclamation would allow Atlas to (1) reclaim the tail-tion (FCl) issues covering the complete spectrum of interac-ings pile for permanent disposal and long-term custodial care by tions, i e., from mild quenching to very energetic interactions in-a govemment agency in its current location on the Moab site, ciuding those that could lead to the alpha-mode containment (2) prepare the 182-ha (400 acre) Moab site for site closure, failure. The experts' review and evaluation took place in the and (3) relinquish responsibikty of the site after having its NRC form of a Second Steam Explosion Review Group (SERG-2) license terminated. The DEIS describes and evaluates (1) the Workshop, held in Annapolis, Maryland, on June 15 and 16-purpose of and need for the proposed action. (2) attematives 1995. The first such workshop (SERG-1) took place in 1985.

considered (3) potentially affected environmental resources, (4)

Extensive discussions took place at the SERG-2 workshop on environmental consequences of the proposed action, and (5) the alpha 4 node failure issue, based on the experts' responses costs and benefits associated with reclamation attematives.

to the questions raised, and consensus opinions on the status Public and agency comments on this DEIS will be considered in e

of resolution of the issue emerged from the discussions. Of the the Final Environmental Impact Statement.

eleven experts polled, all but two concluded that the alpha-mode failure issue was resolved from a risk perspective, mean-NUREG 1532: DRAFT TECHNICAL EVALUATION REPORT FOR ing that this mode of failure is of very low probability, that it is of THE PROPOSED REVISED RECLAMATION PLAN FOR THE little or no significance to the overall risk from s nuclear power ATLAS CORPORATION MOAB MILLSource Material License plant, and that any further reduction in residual uncertainties is No.

SUA-917, Docket No.

40-3453.(Atlas Corporation) not hkely to change the probability in an appreciable manner. To BRUMMETT,E.; FLIEGEL,M.; IBRAHIM A.; et al. Division of a lesser degree, discussions also took place on the broader FCI Waste Management (NMSS 940403). January 1996. 128pp.

issues such as mild quenching of core melt during non-explo-9602070045. 87015:139.

sive FCl, and shock loading of lower head and ex vessel sup.

This Draft Technical Evaluation Report (DTER) summartres port structures arising from explosive localized FCis. These the U.S. Nuclear Regulatory Commission staff's review of Atlas

Main Citations and Abstracts 9

Corporation's proposed reclamation plan for its uranium mill tail-quiring and anatyring information about the existing materials li-ings pile near Moab, Utah. The proposed reclamation would censing process and the steps necessary to radically change allow Atlas to (1) reclaim the tailings pile for permanent disposal this process to the envisioned future process.

and long-term custodial care by a govemment agency in its cur-NUREG-1540: BWR STEEL CONTAINMENT CORROSION.

rent location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC TAN C P; BAGCHl,G Office of Nuclear Reactor Regulation license terminated. The NRC staff review has identified open (Post 941001). April 1996. 217pp. 9604230397. 87094:001.

leaues in geology, seismology, geotechnical engineering, ero.

The mport describes regulatory actons taken aher poson sion protect 6on, water resources protection and radon attenu.

was discovered in the drywell at the Oyster Creek Plant and in ation. The NRC will not approve the proposed reclamation plan the torus at the Nine Mile Point 1 Plant. The report describes until Atlas adequately resolves these open issues.

the causes of corrosion, requiremeqts for mondonng corroson, and measures to mitigate the corrosrve environment for the two NUREG 1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY plants. The report describes the issuances of generic letters SPENT FUEL STORAGE SYSTEMS. Draft Report For Cor*

and information notices either to collect information to deter-ment.

Office of Nuclear Material Safety & Safeguards. Febru-mine whether the problem is genene or to alert the licensees of ary 1996.172pp. 9603190122. 87516:147.

similar plants about the existence of such a problem. Irnplemen-The Standard Review Plan (SRP) for Dry Cask Storage Sys" taten of measures to enhance the containment performance tems provides guidance to the Nuclear Regulatory Commission under severe accident conditions is discussed. A study by staff in the Spent Fuel Project Office for performing safety re" Brookhaven National Laboratory (BNL) of the performance of a views of dry cask storage systems. The SRP is intended to degraded containment under severe accident conditons is sum-ensure the quality and uruformity of the staff reviews and martzed. The details of the BNL study are in the appendix to the present a basis for the review scope and requirements. Part 72, report.

Supart B generally specifies the information needed in a license application for the independent storage of spent nuclear fuel NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CON.

and high level radioactive waste. Regulatory Guide 3.61 " Stand-SOLIDATING AND UPDATING MATERIALS LICENSING ard Format and Content for a Topical Safety Analysis Report for GUIDANCE. Draft Report For Comment. WHITTEN,J.E.;

a Spent Fuel Dry Storage Cask" contains an outline of the spe-VACCA,P.C.; BROWN K.D.; et al. Division of Industrial & Medi-cific information required by the staff. The SRP is divided into cal Nuclear Safety (Post 870729). Apnl 1996. 39pp.

14 sections which reflect the standard application format. Regu-9605130135. 88220:239.

latory requirements, staff position, industry codes and stand-This report describes the concept and approacn for develop-ards, acceptance criteria, and other information are discussed.

ing the Materials Electronic Library (MEL). The Business Proc-Comments on this draft, will be considered and incorporated ess Redesign team for the licensing of materials conceived, as into the SRP as appropriate. The SRP is scheduled for publica.

an integral part of its vision for the redesign of this hcensing tion as an NRC NUREG document late in 1996. Comments, process, the idea for MEL To establish MEL, the NRC will con-errors or omissions, and suggestions for improvement should be solidate and update numerous regulations and policy and guid-sent to the Director, Spent Fuel Project Office, U.S. Nuclear ance documents supporting the materials licensing process into Regulatory Commission, Washington, DC 20555-0001.

a single, comprehensive electronic repository for use by the NUREG-1537 PT01: GU'DELINES FOR PREPARING AND RE-NRC, Agreement and non-Agreement States, licensees, appli-VIEWING APPLICATIONS FOR THE LICENSING OF NON, cants, and the public.

POWER REACTORS.Part 1: Format And Content.

Office of NUREG-1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR Nuclear Reactor Regulation (Post 941001). February 1996, 1995. CONNELLY,S.R. Office of the Controller (Post 890205).

523pp. 9604020335. 87711:001.

April 1996. 85pp. 9607120159. 88982:220.

NUREG-1537, Part 1 gives guidance to non-powe' reactor li-The U.S. Nuclear Regulatory Commission (NRC) is one of six censees and appItcants on the format and content of applica-Federal agencies participating in a pilot project to streamline fi-tions to the Nuclear Regulatory Commission for '.acensing ac-nancial management reporting. The goal of this pilot is to con-tions. These licensing actions include constructior, permits and solidate performance-related reporting into a single accountabil-initial operating lecenses, license renewals, athendmerus, con-ity report in accordance with the Gover iment Management versions from highty enriched uranium to low-enriched uranium, Reform Act (GMRA) of 1994. The NRC's first accountability decommissioning, and license termination.

report consolidates the information previously reported in the NUREG-1537 PT02: GUIDELINES FOR PREPARING AND RE.

NRC's annual financial statement required by the Chief Finan-VIEWING APPLICATIONS FOR THE LICENSING OF NON-cial Officers Act of 1990, as amended; the Chairman's annual POWER REACTORS.Part 2: Standard Review Plan And Accept.

report to the President and the Congress, required by the Fed-ance Criteria.

Office of Nuclear Reactor Regulation (Post eral Managers' Financial Integrity Act of 1982; and the Chair-941001). February 1996. 300pp. 9604020339. 87713:001.

man's semiannual report to the Congress on management deci-NUREG-1537. Part 2 gives guidance on the conduct of licens.

sions and final actions on Office of Inspector General (OlG) ing action reviews to NRC staff who review non-power reactor audit recommendations, required by the inspector General Act licensing applications. These licensing actions include construc.

of 1978, as amended. This report also includes performance tion permits and initial operating licenses, license renewals, measures, as required by the Chief Financial Officers Act of amendments, conversions from highty enriched uranium to low.

1990, enriched uranium, decommissioning, and license termination.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S DECOMMISSIONING OF THE SHIELDALLOY METALLURGI-MATERIALS LICENSING PROCESS REDESIGN.

CAL CORPORATION, CAMBRIDGE. OHIO, FACILITY. Docket No.

RATHBUN,P.A.; BROWN.K.D.; MADERA.J.R.; et al. Division of 40-8948, License No. SMB-1507. WADE,M.C.; BLASING,T.J.;

industrial & Medical Nuclear Safety (Post 870729). April 1996.

CURTIS,A.H.; et al. Oak Ridge National Laboratory. Juty 1996.

82pp. 9604160379. 87884:179.

249pp. 9608060185. 89260:063.

This report describes the work and vision of the team char-Shieldalloy Metallurgical Corporatic.n holds a license from the tered to redesign the process for licensing users of nuclear ma-U.S. Nuclear Regulatory Commission (NRC) for the possession terials. The Business Process Redesign team was chartered to of source material at its Cambridge, Ohic, facility. The source improve the speed of the existing licensing process while main-material is in the form of slag and is located in two piles that taining or improving public safety and to achieve required re-contain a total of 546,000 metric tons (606.000 tons) of materi-source levels. The report describes the team's methods for ac-al. The piles also contain chemical contaminants that may re-

10 Main Citations and Abstracts quire remediatiort Shieldalloy proposed to stabilize, cap, and NUREG-1550: STANDARD REVIEW PLAN FOR APPLICATIONS grade the slag piles as part of decommissioning the arte and.

FOR SEALED SOURCE AND DEVICE EVALUATIONS AND terminating the NRC license. The DEIS evaluates radiological REGISTRATIONS.

Division of Industrial & Medical Nuclear and nonradiological impacts associated with the proposed Safety (Post 870729). November 1996. 96pp. 9612110179.

action and five altemative actions, including no action. Impacts 91064:185.

are assessed for land use, soc 6oeconomics and cultural re.

The purpose of this document is to provide the reviewer of a sources, geology, air quality, water quality and wetlands, human request for a sealed source or device safety evaluation with the health, and biological resources. The staff concludes that the information and materials necessary to make a determination environmental impacts of the on-site and the off-site disposal ai-that the product is acceptable for licensing purposes. It provides ternauves are not significant if mitigabon as described is carried the myiewer wMh a hsung of the applcable regulabons and in-out and that there is no obviously supertor attomative. A cost dustry standards, policies affectng evaluation and registration, benefit analysis shows that the proposed action is less costly certain administrative procedures to be followed, and informa-than all other alternatives except no action. The no-action alter.

tim m how to pedorrn me evaluatm and wnte me mgistrabon native has no economic benefits. The on-site disposal attema-certificate. Standard review plans are prepared for the guidance tives have identical economic benefits, and the off site disposal attemative has the greatest associated economic benefits to sponsible for the review of a sealed source or device applica-local residents.

tson. This document is made available to the public as part of the Comtrussion's poley to inform the nuclear industry and the NUREG-1544: STATUS REPORT: INTERGRANULAR STRESS general public of regulatory procedures and policies. Standard CORROSION CRACKING OF BWR CORE SHROUDS AND s

u s and c la s t OTHER INTERNAL COMPONENTS.

Office of Nuclear Reac-quired. Published standard review plans will be revised periodi-tor Regulation (Post 941001). March 1996.115pp. 9604150308-cally, aa appropnate, to accommodate comments and to reflect 87877:165-new information and expenence. Comments and suggestions On July 25, 1994, the U.S. Nuclear Regulatory Commission for improvement will be considered and should be sent to the (NRC) issued Generic Letter (GL) 94-03 to obtain information U.S. Nuclear Regulatory Commission, Office of Nuclear Material l

needed to assess compliance with regulatory requirements re-Safety and Safeguards, Washington, DC 20555-0001.

garding the structural integrity of core shrouds in domestic boil-ing water reactors (BWRs). This report begins with a brief de-NUREG 1551: FINAL REPORT OF THE NRC-AGREEMENT senption of the safety signifcancs of intergranular stress corro-STATE WORKING GROUP TO EVALUATE CONTROL AND sion cracking (IGSCC) as it relates to the design and function of ACCOUNTABILITY OF LICENSED DEVICES.

Division of in-l BWR core shrouds and other intemal components. It then pre-dustrial & Medical Nuclear Safety (Post 870729). October 1996, 70 II sents a brief history of shroud cracking events both in the U.S.

.S.

uclea'r og t Commission statt acknowledged and abroad, followed by an indepth summary of the industry ac-tions to address the lasue of IGSCC in BWR core shrouds and that licensees wore having problems maintaining control over other intemal components. This report summartzes the staff's and accountability for devices containing radioactive material. In basis for issuing GL 94-03, as well as the staff's assessment of June 1995, the Commission approved the staff's suggestion to form a joint NRC-Agreement State Working Group (WG) to plant-specific responses to GL 94 03. The staff is continually evaluate the problem and propose solutions. The staff indicated evaluating the licensee Inspection programs and the results that the formation of the WG was necessary to address the I

from examinations of BWR core shrouds and other intemal concems from a national perspective, allow for a broad level of components. This report is representative of submittals to and Agreement State (AS) input, and to reflect their experience. AS evaluations by the staff as of September 30,1995. An update of participation in the process is essential since some AS already this report will be issued at a later date.

have implemented effective programs for oversight of device I

users. This report includes the five recommendations proposed NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLE.

by the WG to increase regulatory oversight, increase control MENTING ALTERNATIVE TEMPERATURE-TIME CURVE FOR and accountability of devices, ensure proper disposal, and TESTING THE FIRE RESISTANCE OF BARRIERS FOR NU-ensure disposal of orphaned devices. Specifcally, the WG rec-CLEAR POWER PLANT APPLICATIONS. COOPER,LY.;

ommends that 1) NRC and AS increase regulatory oversight for STECKLER,K.D. National institute of Standards & Technology users of certain devices; 2) NRC and AS impose penalties on (formerty National Bureau of Standa.

Office of Nuclear Reac.

persons losing devices; 3) NRC and AS ensure proper disposal tor Regulation (Post 941001). August 1996. 125pp.

of orphaned devices; 4) NRC encourage States to implement 9609200310. 89729:001, similar oversight programs for users of Naturally-Occurring or Advances in fire science over the past 40 years have offered Accelerator-Produced Material (NARM); and, 5) NRC encourage the potential for developing technicalty sound attemative tem.

non-licensed stakeholders to take appropriate actions, such as perature-time curves for use in evaluating fire barriers for areas instituting programs for meterial identification.

where fire exposures can be expected to be signifcantly differ-NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLE-ent than the ASTM E-119, standard temperature-time exposure.

AR POWER PLANTS. BAJWA,C.S.; WEST,K.S. Office of Nucle.

This report summarizes the development of the ASTM E-119 ar Reactor Regulation (Post 941001). July 1996. 55pp.

standa.-d temperature-time curve, and the efforts by the federal 9608230207. 89455:045.

govemment and the petrochemical industry to develop altema-Nuclear power plants are divided into separate fire areas by live fire endurance curves for specific applications. The report fire-rated structural barriers. Fire-rated penetration seals are in-also provides a frarnework for the development of attemative stalled to seal certain openings in these barriers. The seals curves for application at nuclear power plants. The staff has maintain the fire-resistive integrity of the barriers and provide conckaded that in view of the effort necessary for the develop-reasonable assurance that a fire will be confined to the area in ment of nuclear power plant specific temperature-time curves, which it started. The U.S. Nuclear Regulatory Commission con-such curves are not a viable approach for resolving the issues ducted a comprehensive technical assessment of penetration concoming Thermo-Lag fire barriers. However, the approach seals to address reports of potential problems, to determine if may be useful to Icensees in the development of performance.

there were any problems of safety significance, and to deter-based fire protection methods in the future.

mine if NRC requirements, review guidance, and inspection pro-cedures are adequate. The staff did not find plant-specific prob-

Main Citations and Abstracts 11 lems of safety significance or concerns with generic implica-ternal flooding, but excluding intemal fire). The IPE submittals tions. The staff concluded that the general condition of penetra-were reviewed to gain perspectives in three major areas: (1) im-tion seal programs in industry is satisfactory. The staff also con-prove nents made to individual plants as a rd of their IPEs cluded that actions it had taken in 1988 and 1994 to address and the collective result of the IPE program, (2) plant-specific potential penetration seal problems increased industry aware-design and operational features and modeling assu:nptions that ness of such problems and resulted in more thorough surveil-significantly affect the estimates of CDF and containment per-lances, maintenance, and corrective actions. These previous formance, and (3) the quality of the IPEs with respect to their staff actions, together with continued licensee upkeep of exist" potential role in risk-informed regulation. These perspectives ing penetration seal programs and continued NRC inspections, were gained by assessing the core damage and containment are adequate to maintain public health and safety, performance results, including overall CDF, accident sequences, NUREG-1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT dominant contributions to component failure and human error, MATERIALS LICENSES. Program-Specific Guidance About Port-and containment failure modes. These results were assessed in able Gauge Licenses. Draft Report For Comment. VACCA,P.C.;

relation to the design and operational characteristics of the varl-WHITTEN.J E.; ARREDONDO,S.A.; et al. Drvision of Industrial &

ous reactor and containment types, and by comparing the IPEs Medical Nuclear Safety (Post 070729). September 1996.09pp.

to attributes of a quality probabilistic risk assessment. Methods 9612030289. 91001:001.

data, boundary conditions, and assumptions used in the IPEs As part of its redesign of the materials licensing process, were considered in understanding the differences and similarl-NRC is consolidating and updating numerous guidance docu-ties observed among the various types of plants.

ments into a single comprehensive repository as described in NUREG-1539 and draft NUREG 1541. Draft NUREG-1556, Vol.

NUREG 1560 V2P2-5DFC: INDIVIDUAL PLANT EXAMINATION 1, !s the first program-speciflc guidance developed for the new PROGRAM: PERSPECTIVES ON REACTOR SAFETY AND process and may serve as a template for subsequent program-PLANT PERFORMANCE. Parts 2-5. Draft Report For Comment.

specific guidance. This document is ultimately intended for use Division of Systems Technology (Post 91217). November by applicants, licensees, and NRC staff and will also be avail-1996. 554pp. 9612160337. 91122:001, able to Agreement States. This document combines the guid-See NUREG-1560,V01 P01,DFC abstract.

ance previously found in draft Regulatory Guide DG-0008, "Ap-plications for the Use of Sealed Sources in Portable Gauging NUREG-1561: STANDARD REVIEW PLAN MAINTENANCE PRO-Devices," and in NMSS Policy and Guidance Directive 2-07, GRAM IMPLEMENTING PROCEDURES DOCUMENT.

Office

" Standard Review Plan for Applications for the Use of Sealed of Nuclear Reactor Regulation (Post 941001). November 1996.

Sources in Portable Gauging Devices." This draft NUREG takes 68pp. 9612030270. 90980:041, a graded, more performance-based approach to licensing porta-The Imphmenting Procedures Document (IPD) was devel-etai) id support of n ap ica no t se se dev es oped by the inspection Program Branch, Office of Nuclear Re-Note that this document is strictly for public comment and NOT actor Regulation, with assistance from Pacific Northwest Labo-for use in preparation or review of portable gauge licenses until ratory, for the Standard Review Plan Maintenance Program it is published in final form.

(SRP-MP). The SRP-MP was established to maintain the Stad ard Review Plan (SRP) on an on-going basis. The IPD provides NUREG-1557:

SUMMARY

OF TECHNICAL INFORMATION AND guidance, including an overall approach and procedures, for AGREEMENTS FROM NUCLEAR MANAGEMENT AND RE-SRP-MP ta:,ks. The objective of the IPD is to ensure that revi-SOURCES COUNCIL INDUSTRY REPORTS ADDRESSING Li-sions to the SRP reflect current NRC requirements and guid-CENSE RENEWAL REGAN.C.; LEE S. Office of Nuclear Reac-ance, and that a consistent methodology is used to develop and tor Regulation (Post 941001). CHOPRA,0.K.; et al. Argonne Na-revise SRP sections.

tional Laboratory. October 1996. 188pp. 9611180290.

90805:141.

NUREG-1563: BRANCH TECHNICAL POSITION ON THE USE in about 1990, the Nuclear Management and Resources OF EXPERT ELICITATION IN THE HIGH-LEVEL RAD;OACTIVE Couned (NUMARC) submitted for NRC review ten industry re-WASTE PROGRAM. KOTRA,J.P.; LEE.M.P.; EISENBERG,N.A.;

ports (irs) addressing a0ing issues associated with specific strudures and components of nuclear power plants and one IR et at Division of Waste Manegement (NMSS 940403). Novem-addressing the screening methodology for integrated plant as-ber 1996. 71pp. 9612110187, 91062:268.

sessment. The NRC staff had been reviewing the ten NUMARC The U.S. Nuclear Regulatory Commission staff expects that IRu; their comments on each IR and NUMARC responses to the subjective judgments of individual experts and, in some cases, comments have been compiled as public documents. This groups of experts, will be used by the U.S. Department of report provntes a brief summary of the to::hnicalinformation and Energy (DOE) to interpret data obtained during site character-NUMARC/NRC agreements from the ten irs, except for the ization and to address the many technical lasues and irherent Cable License Renewal IR. The technical information and uncertainties associated with predicting the performance of a agreements documented herein represent the status of the repository system for thousands of years. NRC has traditionally NRC staffs review when the NRC staff and industry resources accepted, for review, expert judgment to evaluate and interpret were redirected to address rule implementation issues. The the factual bases of license applications and is expected to give NRC staff plans to incorporate appropriate technical information appropriate consideration to the judgments of DOE's experts re-and agreements into the draft stancard review plan for license garding the geologic repository. Such consideration, however, terrowal.

envisions DOE using expert judgments to complement and sup-NUREG-1560 V1 P1 DFC: INDIVIDUAL PLANT EXAMINATION plement other sources of scientific and technical information, PROGRAM: PERSPECTIVES ON REACTOR SAFETY AND such as data collection, analyses, and experimentation. In this PLANT PERFORMANCE. Summary Report. Draft Report For document, the NRC staff has set forth technical positions that:

Comment.

Division of Systems Technology (Post 941217). Oc-(1) provide general guidelines on those circumstances that may tober 1996. 270pp. 9611190256. 90817:034.

warrant the use of a formal process for obtaining the judgments This report provides perspectives gained by reviewing 75 Indi-of more than one expert; and (2) describe acceptable proco-vidual Plant Examination (IPE) submittals pertaining to 108 nu-dures for conducting expert elicitation when formally elicited clear power plant units. IPEs are probabdistic analysis that esti-judgments are uaed to support a demonstration of compliance mate the core damage frequency (CDF) and containment per-with NRC's geologic disposal regulation, currently set forth in 10 1

formance for accidents initiated by intemal events (including in-CFR Part 60.

12 Main Citations and Abstracts NUREG 1664: LONG-TERM KINETIC EFFECTS AND COLLOID NUREG-1568: LICENSE RENEWAL DEMONSTRATION PRO-FORMATIONS IN DISSOLUTION OF LWR SPENT FUEL GRAM: NRC OBSERVATIONS AND LESSONS LEARNED.

AHN.T.M. Division of Waste Management (NMSS 940403). No.

PRATO,R.J.; KUO,P.T.; NEWBERRY,S.F. Office of Nuclear Re-vember 1996. 60pp. 9612110158. 91068:147.

acter Regulation (Post 941001). December 1996. 25pp.

This report evaluates continuous dissolution and cohoid for-9701130209. 91400:012.

mation during spent fuel performance under repository condi-This report summartzes the Nuclear Regulatory Commission tions in high-level waste disposal. Various observations suggest staff's observations and lessons learned from the five License that reprecipitated layers formed on spent-fuel surfaces may not Renewal Demonstration Program (LRDP) site visits performed be protective. This situation may lead to continuous dissolution by the staff from March 25,1996, through August 16,1996.The of highly soluble radionuclides such as C 14, Cl-36, Tc-99, l-LRDP was a Nuclear Energy Institute (NEI) program intended to 129, and Co-135. However, the diffusion limits of various spe-assess the effectiveness of the guidance provided by NEl 95-cies involved may retard dissolution significantly. For low-solubiL 10, Revision 0, " Industry Guideline for implementing the Re-ity actinindes such as Pu-(239+ 240) or Am-(241 + 243), various quirements of 10 CFR Part 54 The Ucense Renewal Rule," to processes regarding colloid formation have been analyzed. The implement the requirements of Title 10 of the Code of Federal processes analyzed are condensation, dispersion, and sorptson.

Colloid formation may lead to significant releases of low-solubilh Regulations, Part 54 (10 CFR P.rt 54), " Requirements for Re-ty actsnides. However, because there are only hmsted data avail-newal of Operating Licenses for Nuclear Power Plants." in gen-able on matrix dissolution, colloid formation, and solubehty limits, eral, NEl 95-10, appeared to contain most of the guidance many uncertainties still exist. These uncertainties must be ad-needed for scoping, screening, identifying aging effects, devel-dre fore the significance of radionuchde releases can be o ng aging management programs, and evaluating time-limited aging analysis. However, as expected, the LRDP arte-visit re-views identrfied the need for some improvements to assist appli-NUREG-1565: DRY OXIDATION AND FRACTURE OF LWR cants in developing license renewal applications and supporting SPENT FUEL AHN.T.M. Dnnaion of Waste Management (NMSS documentation. The improvements and additions to NEl 9510 940403). November 1996. 40pp. 96121 0153. 91064:281, that are needed for developing an license renewal program cord This report evaluates the characteristics of oxidation and frac-sistent with the intent of the rule, will be included in NEl 95-10 ture of hght-water reactor (LWR) spent fuel in dry air, it also dis.

or the apphcable Regulatory Guide.

cusses their effects on radionuclide releases in the anticipated high-level waste repository environment. A sphere model may NUREG-1575 DRFT FC: MULTI-AGENCY RADIATION SURVEY describe diffusion-hmited formation of lower oxides, such as AND SITE INVESTIGATION MANUAL (MARSSIM). Draft For U(4)O(9), in the oxidation of the SF matnx. Detrimental higher Public Comment.

Division of Regulatory Applications (Post oxides, such as U(3)O(8), may not form at temperatures below 941217). December 1996. 601pp. 9701130202. 91396:001, a threshold temperature. The nucleation process suggests that The MARSSIM provides information on planning, conducting, a threshold temperature exists. The calculated results regarding evaluating, and documenting environmental radiological surveys fracture properties of the SF matrix agree wtth experimental ob-for demonstrating compliance with dose-based regulations. The servations. Oxidation and fracture of Zircaloy may not be signifi.

MARSSIM, when finalized, will be a multi-agency consensus cant under anticipated conditions. Ur. der saturated or unsaturat-document. MARSSIM was developed collaboratively over the w aqueous conditions, oxidation of the SF matrix is believed to past three years by four Federal agencies having authority for increase the releases of Pu-(239+ 240), Am-(241 +243), C-14, control of radioactive materials; EPA, DOD, DOE, and NRC (60 Tc-99, !-129, and Cs-135. Under dry conditions,1-129 releases FR 12555). MARSSIM's objective is to describe standardized are likely to be small, unlike C-14, in lower oxides; Cl-36, Tc-99, and consistent approaches for surveys, which provide a high l-129, and Cs-135 may be released fast in higher oxides-degree of assurance that established dose-based release crite-NUREG-1567 DRFT FC: STANDARD REVIEW PLAN FOR SPENT

"*' sa s ' E

"' g*n are a au ss, e at me sam he FUEL DRY STORAGE FACILITIES. Draft Report For Comment.

Office of Nuclear Material Safety & Safeguards. October maging an ehem use of resoums. h unWs, j

1996. 655pp. 9611100199. 90872:001.

meadologies, and philosophies that form the bases of this manua were developed to be consistent with current Federal The Standard Review Plan (SRP) for Spent Fuel Dry Storage Faciht>es provides guidance to the staff of the U.S. Nuclear limits, guidelines, and procedures. The draft manual was pre-j Regulatory Commission for performing safety reviews of Spent pared by a multi agency technical working group composed of Fuel Dry Storage Facilit>es. The SRP is intended to ensure the representatives from DOD, DOE, EPA, and NRC. Contractors to quahty and uniformity of the staff reviews by establishing the the NRC, EPA, and DOE, and members of the pubhc have been j

review scope and requirements. Part 72, Subpart B generally present during the open meetings of the MARSSIM work group.

specifies the information needed in a hcense apolication for the Independent storage of spent nuclear fuel and high level radio.

NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY THIRD 1

active waste. Regulatory requirements, staff rasition, industry WATER REACTOR SAFETY INFORMATION MEETING. Plena'Y codes and standards, acceptance criteria, ani other information Session, High Burnup Fuel Behavior, Thermal Hydrauhc Re-l are discussed. Comments on this draft, will be considered and search. MONTELEONE,S. Brookhaven National Laboratory.

it.corporated into the SRP as appropr%e. The SRP is sched.

March 1996. 278pp. 9604150352. 87868:001.

uled for pubhcation as an NRC NUREG document in 1997. A This three-volume report contains papers presented at the separate Standard Review Plan for Dry Cask Storage Systems Twenty-Third Water Reactor Safety Information Meeting held at (DCSRP) was issued for public comment in February 1996. The the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-DCSRP is scheduled to be pubhshed as an NRC NUREG docu-25,1995. The papers are printed in the order of their presenta-ment in January 1997. To ensure consistency between the two tion in each session and describe progress and results of pro-standard review plans (SRPs), comments on sections common grams in nuclear safety research conducted in this country and to both SRPs will be incorporated, as appropriate, in both abroad. Foreign participation in the meeting included papers NUREG. Comments, errors or ommissions, and suggestions for presented by researchers from France, Italy, Japan, Norway, improvement should be sent to the Churf, Rules Review and Di-Russia, Sweden, and Switzerland. The titles of the papers and rectives, Dmsion of Freedom of information and Publication the names of the authors have been updated and may differ Services, Mail Stop T-8-D-59. U.S. Nuclear Regulatory Commis-from those that appeared in the final program of the meeting.

sion, Washington, DC 20555-0001.

l 1

Main Citations and Abstracts 13 NUREG/CP-0149 V02: PROCEEDINGS OF THE TWENTY THIRD NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/

WATER REACTOR SAFETY INFORMATION MEETING. Human ASME SYMPOSIUM ON VALVE AND PUMP TESTING. Held At Factors Research, Advanced l&C Hardware & Software, Severe The Hyatt Regency Hotel, Washington,DC, July 15-18, 1996.

Accident Research, Probabilistic Risk Assessment Topics, Indi-Office of Nuclear Reactor Regulation (Post 941001).

American vidual Plant Examination. MONTELEONE,S. Brookhaven Nation-Society of Mechanical Engineers. July 1996. 700pp.

d Laboratory. March 1996. 542pp. 9604150357. 87866:001.

9608140271. 89352:001.

See NUREG/CP-0149,V01 abstract, The 1996 Symposium on Valve and Pump Testing, jointly sponsored by the Board on Nuclear Codes and Standards of l

NUREG/CP.4149 V03: PROCEEDINGS OF THE TWENTY THIRD the Amencan Society of Mechanical Engineers and by the Nu-WATER REACTOR SAFETY INFORMATION clear Regulatory Commission, provides a forum for the discus-MEETING. Structural & Seismic Engineering. Primary Systems sion of current programs and methods for inservice testing and Integrity, Equipment Operability And Aging. ECCS Strainer motor operated valve testing at nuclear power plants. The sym-Blockage Research & Regulatory issues. MONTELEONE,S.

posium also provides an opportunity to discuss the need to im-Brookhaven National Laboratory. March 1996. 246pp.

prove that testing in order to help ensure the reliable perform-9604150363. 87865:037, ance of pumps and valves. The participation of industry repre.

See NUREG/CP-0149,V01 abstract.

sentatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding ttra im-NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES provement of inservice testing of pumps and valves at nuclear IN REPOSITORY DESIGN AND PERFORMANCE power plants.

ASSESSMENT. Held At Holiday Inn Crowne

Plaza, NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER Rockville, Maryland, September 19-20, 1994., Center for Nucle.

PLANT SAFETY ISSUE PRIORITIZATION INFORMATION DE-ar Waste Regulatory Analyses. April 1996.266pp.9606030259.

88422 M VELOPMENT. DALING,P.M.; LAVENDER.J.C. Battelle Memorial instrtute, Pacific Northwest Laboratory. July 1996. 237pp.

The Center for Nuclear Waste Regulatory Analyses organized 0608050237. PNL 4297. 89243:001.

and hosted a workshop on Rock Mechanics lasues in Reposi-This is the sixth in a series of reports to document the use of tory Design and Performance Assessment" on behalf its spon-a methodology developed by Pacific Northwest Laboratories to sor the U.S. Nuclear Regulatory Commission (NRC). This work-calculate, for prioritization purposes, the risk, dose, and cost im-shop was held on September 19-20, 1994 at the Holiday Inn pacts of implementing resolutions to reactor safety issues Crowne Plaza, Rockville, Maryland. The objectivas of the work.

(NUREG/CR-2800, Andrews, et al.,1983). This report contains shop v sre to stimulate exchange of technical information the results of issue-specific analyses for 34 generic issues. The cmong parties actively investigating rock mechanics issues rele-results are referenced, as one consideration in setting prionties vant to the proposed bth-level waste repository at Yucca for reactor safety issues, in NUREG-0933, A Prioritization of Go-Mountain and identify /c.% m rock mechanics issues important neric Safety issues.

to repository design ar., A <formance assessment. The work-shop contained three te& cal sessions and two panel discus.

NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIO-sions. The part:cipants included technical and research staffs ACTIVE RELEASES FROM NUCLEAR POWER PLANT representing the NRC and the Department of Energy and their SITES. Methodology And Data Bass. BAKER,D.A. Battelle Me.

contractors, as well as researchers from the academic, com.

morial institute, Pacific Northwest Laboratory. June 1996.

mercial, and international technical communities. These pro.

250pp. 9607090240. 88957:001.

ceedings include most of the technical papers presented in the This manual describes a dose assessment system used to technical sessions and the transcripts for the two panel discus.

estimate the population or collective dose commitments re-sions.

ceived v(a both airborne and waterborne pathways by person living within a 2-to 80-kilometer region of a commercial operat-NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' ing power reactor for a specific year of eff!uent releases. Com-l MEETING ON CRACKING IN LWR RPV HEAD puter programs, data files, and utility routines are included PENETRATIONS. Held At ASTM Headquarters, Philadelphia, which can be used in conjunction with an IBM or compatible Pennsylvania, May 2-3, 1995. PUGH.C.E.; RANNEY,S.J. Oak personal computer to produce the required dose commitments Ridge National Laboratory. July 1996. 304pp. 9608210221, and their statistical distributions. In addition, maximum individual ORNL/TM-13187. 89420:001.

airbome and waterborne dose commitments are estimated and l

This report contains 17 papers that were presented in four compared to 10 CFR Part 50, Appendix 1, design objectives.

sessions at the IA'cA Specialists

Meeting on Cracking in LWR NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIO-RPV Head Penetratixs held at ASTM Headquarters in Philadel-ACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES phia on May 2-3, 1995. The papers are compiled here in the IN 1992. AABERG,R.L; BAKER.D.A. Battelle Memorial institute, order they were presented in the sessions, and they relate to Pacific Northwest Laboratory. March 1996.196pp.9604170363.

operational observations, inspection techniques, analytical M PNL-4221. 87903:120.

eling, and regulatory control. The goal of the meeting was to Population and individual radiation dose commitments have allow international experts tc review expenence in the field of been estimated from reported radionuclide releases from com-l ensuring adequate performance of reactor pressure vessel mercial power reactors operating dunng 1992. Fifty-year dose (RPV) heads and penetrations. The emphasis was aimed at commitments for a one-year exposure from both liquid and at-better understanding of behavior of reactor component materi-mosphenc releases were calculated for four population groups j

l cis, to provide guidance and recommendations assunng reliabil-(infant, child, teenager, and adult) residing between 2 and 80 l

ity, adequate performance, and drections for further investiga-km from each of 72 reactor sites. This report tabulates the re-l tions. The intemational nature of the meeting is illustrated by suits of these calculations, showing the dose commitments for the fact that papers were presented by researchers from 10 both water and airbome pathways for each age group and countries. There were technical experts present from other organ. Also included for each of the sites is an estimate of indi-countries who participated in discussbns of the results present-vidual doses that are compared with 10 CFR Part 50, Appendix ed. The IAEA issued a Working Material version of the meeting I design objectives. The total collective dose commitments papers (IAEA IWG-LMNPP-95/1), and this present document in-(from both liquid and airborne pathways) for each site ranged corporates the final version of the papers as received from the from a high of 3.7 persordrem to a low of 0.0015 person-rem for cuthors.

the sites with plants in operation and producing power dunng l

14 Main Citations and Abstracts the year. The anthmetic mean was 0.66 person-rem. The total whether a slow strain rate applied during different portions of a population dose for all sites was estimated at 47 person-rem for tensile-loading cycle are equally effective in decreasing fatigue the 130 million people considered at risk. The individual dose life. Tensile properties and microstructures of several heats of

i. vin...;L,ents estimated for all sites were below the Appendix 1 Alloy 600 and 690 were characterized for correlation with EAC of the alloys in simulated LWR environments. Effects of DO and i

design objectives.

electrocheeal pomal on sug% 2 mgradar ca&

NUREQ/CR 4219 V11 N2: HEAVY-SECTION STEEL TECHNOL-ing of high-and commercial-purity Type 304 SS specimens from OGY PROGRAM. Semiannual Progress Report For April-Sep-control-blade absort>er tubes and a control-blade sheath irradi-tomber 1994. PENNELL,W.E. Oak Ridge National Laboratory.

ated in boiling water reactors were determined in slow-strain-April 1996.117pp. 9605130075. ORNL/TM-9593. 88220:126.

rate-tensile tests at 289 degrees C. Microchemical changes in The Heavy-Section Steel Technology (HSST) program is con-the specimens were studied by Auger electron spectroscopy ducted for the Nuclear Regulatory Commission (NRC) by Oak and scanning electron microscopy to determine whether trace Ridge National Laboratory (ORNL). The program focus is on the impurity elements may contribute to IASCC of these materials.

development and validation of tm,ri.vloiri or the assesment of f

fracture-prevention margins in commercial nuclear reactor pres-NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACK-sure vessels. The HSST Program la organized in seven tasks:

ING IN LIGHT WATER REACTORS. Semiannual Report. April December 1995. CHOPRA,0.K.; CHUNG,H.M.;

(1) program management, (2) constraint effects analytical devel-1995 opment and validation, (3) evaluation of cladding effects, (4)

GRUBER E.E.; et al. Argonne National Laboratory. July 1996.

ductile to-cleavage fracture-mode conversion, (5) fracture analy-87pp. 9608210264. ANL-96/1. 89422:253.

sis methods development and application, (6) material property This report summadzes work pouvined by Argonne National data and test methods, and (7) integration of results. The pro-Laboratory on fatigue and environmentally assisted cracking gram tasks have been structured to p! ace emphasis on resolu-(EAC) in light water reactors (LWRs) from April 1995 to Decem-tion fracture issues with near-term licensing significance. Re-ber 1995. Topics that have been investigated include (a) fatigue sources to execute the research tasks are drawn from ORNL of carbon and low-alloy steel used in reactor piping and pres-with subcontract support from universities and other research sure vessels, (b) EAC of Alloys 600 and 690, and (c) irradiation-laboratories. Close contact is maintained with the sister Heavy-assisted stress corrosion cracking (IASCC) of Type 304 SS f a-Section Steel irradiation (HSSI) Program at ORNL and with re-tigue tests were conducted on femtic steels in water that wo-lated research programs both in the United States and abroad.

tained various concentrations of dissolved oxygen (DO) to de-This report provides an overview of principal developments in termine whether a slow strain rate applied dunng different por-each of the seven program tasks from April 1994 to September tions of a tensile-loading cycle are equally effective in decreas-1994.

ing fatigue life. Crack-growth-rate tests were conducted on com-NUREQ/CR-4219 V12 N1: HEAVY-SECTION STEEL TECHNOL.

pact. tension specimens from several heats of Alloys 600 and 690 in simulated LWR environments. Effects of fluoride-ion con-OGY PROGRAM. Semiannual Progress Report For October 1994 - March 1995. PENNELL.W.E. Oak Ridge National Labora.

tamination on susceptibihty to intergranular cracking of high-and commercial-purity Type 304 SS specimens from control-tory. Juty 1996. 146pp. 9608070004 ORNL/TM-9593.

blade absorber tubes irradiated in boiling water reactors were 89285:040.

determined in slow-strain-ra'.9 tensile tests at 288 degrees C.

The Heavy-Section Steel Technology (HSST) Program is con.

ducted for the U.S. Nuclear Regulatory Commission (NRC) by Microchemical changes in the specimens were studied by Auger Oak Ridge National Laboratory (ORNL). The program focus is electron sp6Gv cepy and scanning electron microscopy to de-termine whether trace impurity elements may contribute to on the development and validation of technology for the as.

IASCC of these materials.

sessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION seven tasks: (1) program management, (2) constraint effects INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress analytical development and validation, (3) evaluation of cladding Report On Field Experiments At A Humid Region effects, (4) ductile to cleavage fracture mode conversion, (5)

Site,Beltsville, Maryland. SCHUL 2,R.K. Califomia, Univ. of, Los fracture analysis methods development and applications, (6)

Angeles, CA. RIDKY,R.W. Maryland, Univ. of, College Park, MD.

j material property data and test methods, and (7) integration of O'DONNELL,E. Division of Regulatory Applications (Post i

results into a state-of the-art methodology. The program tasks 941217). August 1996. 30pp. 9609030360. 89546:303.

have been structured to place emphasis on the resolution frac-The project objective is to assess means for controlling waste ture issues with near-term licensing significance. Resources to infiltration through waste disposal unit covers in humid regions.

execute the research tasks are drawn from ORNL with shon-Experimental work is being performed in large scale lysimeters

(

tract support from universities and other research laboratories.

(70'x45'xlO') at Beltsville, MD,and results of the assessment are Close contact is maintained with the sister Heavy-Section Steel applicable to disposal of LLW, uranium mill tailings, hazardous irradiation Program at ORNL with related research programs waste, and sanitary landfills. Three concepts are under investi-both in the United States and abroad. This report provides an gation: (1) resistive layer barrier, (2) conductive layer barrier, overview of principal developments in each of the seven pro-and (3) bioengineering water management The resistive layer t

l gram tasks from October 1994 - March 1995.

barrier consists of compacted earth (clay). The conductive layer NUREQ/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACK-barrier is a special case of the capillary barrier and it requires a ING IN LIGHT WATER REACTORS.

Semiannual flow layer (e.g. fine sandy loam) over a capillary break. As long March 1995.

CHUNG.H.M.;

as unsaturated conditions are maintained water is conducted by Report, October 1994 CHOPRA,0.K.; GAVENDA,D.J.; et al Argonne National Labora-the flow layer to below the waste. This barrier is most efficient tory. January 1996. 72pp. 9602050045. ANL-95/41. 86980:234.

at low flow rates and is thus best placed below a resistive layer This report summartzes work performed by Argonne National banier. Such a combination of the resistive layer over the con-Laboratory on fatigue and environmentally assisted cracking ductive layer bamer promises to be highly effective provided (EAC) in hght water reactors (LWRs) from October 1994 to there is no appreciable subsidence. Bioengineering water man-March 1995. Topics that have been investigated include (a) fa-agement is a surface cover that is designed to accommodate t>gue of cart)on and low-alloy steel used in reactor piping and subsidence. It consists of impermeatsie panels which enhance pressure vessels, (b) EAC of Alloy 600 and 690, and (c) Irradia-rurn-off and limit infiltration. Vegetation is planted in narrow tion-assisted stress corrosion cracking (IASCC) of Type 304 SS.

openings between panels to transpire water from below the Fatigue tests were conducted on ferritic steels in water with panels. This systom has successfully dewatered two lysimeters several dissolved-oxygen (DO) concentrations to determine thus demonstratir g that this procedure could be used for reme-

M:In Citations cnd Abstracts 15 e

dial acnon " drying out existing water-logged disposal sites at described, and simple illustrations of the impact on reliability of low cost.

structural degradation are provided. The role of nondestructive evaluation in time-dependent relist,ility analysis, both in terms of NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.

defect detection and sizing.is examined. A Markov model pro-HEASLER,P.G.; DOCTOR,S.R. Battelle Memonal Institute, Pacif-vides a tool for accountmg for time-dependent changes in ic Northwest Laboratory. April 1996. 196pp. 9604230383.

damage condition of a structural component or system.

1 PNNL 10475. 87992:143.

The piping inapection round robin was conducted in 1981 at NUREG/CR-5535 V07 R1:

RELAPS/ MOD 3 CODE the Pacific Northwest National Laboratory (PNNL) to quantify MANUALSummaries And Reviews Of Independent Code As-3 the capability of ultrasonics for inservice inspechon and to ad-sessment Reports. MOORE.R.L; SLOAN,S.M.; SCHULTZ,R.R.;

dress some aspects of reliability for this type of. nondestructive et al. Idaho National Engineering Laboratory. October 1996.

evaluation (NDE). The research was sponsored by the U.S. Nu-139pp. 9611190220. INEL-95/0174. 90823:110.

clear Regulatory Commession Office of Research, under a pro-Summanes of RELAPS/ MOD 3 code assessments, a listing of gram entitled, Evaluation and improvement of NDE Reliability the assessment matrix, and a chronology of the various ver.

I for Inservice inspecton of Light Water Reactors." The round robin measured the crack detection capabilities of seven field sions of the code are given. Results from these code assess-ments have been used to formulate a compilation of some of inspedion teams who employed procedures that met or ex, coeded the 1977 edition through the 1978 addenda of the the strengths and weaknesses of the code. These results are documented in the report. Volume 7 was designed to be updat-American Society of Mechanical Engineers (ASME)Section XI Code requirements. Three different types of material were em-ed periodecally and to include the results of the latest code as-ployed in the study (cast stainless steel, clad ferritic, and sessments as they become available. Consequently, users of wrought stainless steel), and two different types of flaws were Volume 7 should ensure that they have the latest revision avail-able.

implanted into the specimens (intergranular stess corrosion cracks (IGSCCs) and thermal fatigue cracks (TFCs)). When con-NUREG/CR-5591 V06 N2: HEAVY-SECTION STEEL IRRADIA-sidenng near side inspection, far-side inspection, and false call TION PROGRAM. Semiannual Progress Report For April rate, the overall performance was found to be best in clad ferrit-Ic, less effective in wrought stainless steel and the worst in cast Through September 1995. CORWIN,W.R. Oak Ridge National stainless steel. Depth sizing performance showed little correla.

Laboratory. August 1996. 73pp. 9612040119. ORNL/TM-11568.

91007 m tion wtth the true crack depths.

The goal of the Heavy-Section Steel Irradiation Program is to NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS:

provide a thorough, quantitative assessment of effects of neu-LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM tron irradiation on material behavior, and in particular the frac-FOR FISCAL YEAR 1995. Annual Report. MCCONNELL,J.W.;

ture toughness properties, of typical pressure vessel steels as ROGERS R.D.

Idaho National Engineenng Laboratory.

they relate to light-water reactor pressure-vessel integrity. Ef-JASTROW,J.D.; et al. Argonne National Laboratory. June 1996.

fects of specimen size, matenal chemistry, product form and mi-82pp. 9607090111, INEL-94/0278. 88958:118.

crostructure, irradiation fluence, flux, temperature and spectrum, The Field Lysimeter investigations: Low-Level Waste Data and post-irradiation annealing are being examined on a wide Base Development Program, funded by the U.S. Nuclear Regu-range of fracture properties. The HSSI Program is arranged into latory Cvmm; ;06, is (a) studying the degradation effects in or-14 tasks: (1) program management, (2) fracture toughness I

genic lon-exchange resins caused by radiation. (b) examining (K(Ic)) curve shift in high-copper welds, (3) crack-arrest tough-the adequacy of test procedures recommended in the Branch ness (K(la)) curve shift in high-copper welds, (4) irradiation ef-Technical Position on Waste Form to meet the requirements of facts on cladding, (5) K(Ic) and K(la) curve shifts in low upper-10 CFR 61 using solidified ion-exchange resins, (c) obtaining shelf welds, (6) annealing effects in low upper-shelf welds, (7) performance information on solidified ion-exchange resins in a irradiathn effects in a commercial low upper-shelf weld (8) mi-disposal environment, and (d) determining the condition of liners crostructural analysis of irradiation effects, (9) in-service aged used to dispose the lon-exchange resins. Compressive test re-material evaluations, (10) correlation monitor materials, (11) sutts of 12-year old cement and vynyt ester-styrene edidified special technical assistance, (12) JPDR steel examination, (13) waste forms are presented, which show effects of aging and technical assistance for JCCCNRS Workinc Groups 3 and 12, self-irradiation. Results of the tenth year of data acquisihm from and (14) additional requirements for matenals. This report pro.

the field testing are presented and discussed. Dunng tie con-vides an overview of the actMties within each of these tasks tinuing field testing, both portland type I-il cement and Dcm vinyl from April Through September 1995.

ester styrene waste forms are being tested in fysimeter sirrays located at Argonne National Laboratory-East in Illinois and at NUREG/CR-5595 R01: FORECAST: REGULATORY EFFECTS Oak Ridge National Laboratory. The study is designed to pro-COST ANALYSIS SOFTWARE MANUAL Version 4.1.

vide continuous data on nuclide release and movement, as well LOPEZ,B.; SCIACCA,F.W. Science & Engineering Associates, as environmental -.., over a 20-year period.

Inc.

S. Cohen & Associates, Inc. July 1996. 143pp.

NUREG/CR-5442: RELIABILITY-BASED CONDITION ASSESS-9608050060. SEA 95-2755010A1. 89250:001.

MENT OF STEEL CONTAINMENTS AND LINERS.

The FORECAST program was developed to facilitate the ELLINGWOOD,B.R.; BHATTACHARYA,B.; ZHENG,R-H.; et al.

preparation of the value-impact portion of NRC regulatory analy-Johns Hopkins Univ., Baltimore, MD. November 1996.109pp.

ses. This PC program integrates the ma}or cost and benefit con-9612160327 ORNL/TM-13244. 91099:113.

siderations that may result from a proposed regu!atory change.

The evaluation of steel containments and liners for continued FORECAST automates much of the calculations typically sonnce must provide assurance that they are able to withstand needed in a regulatory analysis and thus reduces the time and future extreme loads during the service period with a level of re-labor required to perform these analyses. More importantly, its liability that is sufficient for public safety. This research demon-integrated and consistent treatment of the different value impact strates the feasibility of using reliability analysis as a tool for considerations should help assure comprehensiveness, uniform-performing condition assessments and service life predictions of ity, and accuracy in the preparation of NRC regulatory analyses, steel containment and liners. Mathematical models that de-The current FORECAST version 4.1 has been upgraded from scribe time-dependent charges in steel due to aggressive envi-the previous version and now includes an uncertainty package ronmental factors are identfied, and statistical data supporting and an automatic cost escalation package, in addition, it now the use of these models in time @ndent reliability analysis explicitly addresses public health impacts, occupational health are summartzed. The analysis of steel containment fragility is impacts, onsite property damage, and govemment costs.

1

l 16 Main Citations and Abstracts i

NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIO-juana was responsible for the highest percentage of positive

)

NUCLIDE BURDENS TO PRENATAL RADIATION DOSES.

test results (53.08%), followed by cocaine (24.24%) and alcohol SlKOV,M.R.; HUI,T.E.; TRAUB,R.J.; et al. Battelle Memortal Ir>

(17,17%).

stitute, Pacife Northwest Laboratory. May 1996. 380pp.

9606070092. PNL-7445. 88485:001.

NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER This report describes approaches to calculating and express-GUIDANCE CITED IN REGULATORY DOCUMENTS.

1 ing radiation doses to the embryo / fetus from internal radionu-NICKOLAUS,J.R.; BOHLANDER,K.L Battelle Memonal Institute, I

clides. Information for occupationally and medically significant Pacific Northwest Laboratory. August 1996.

555pp.

radioelements was used to dertve biokinetic transfer models 9609030269. PNL-8482. 89548:001.

)

and integrated with metabolic pattems. Placental transfer and As part of the U.S. Nuclear Regulatory Commission (NRC) radioactivty levels in the embryo / fetus were calculated as a Standard Review Plan Update and Development Program (SRP-UDP), Pacifc Northwest National Laboratory developed a listing I

ar g en e of de on ret n mb fetus. Methodologies described by MIRD were extended to cal-of industry consensus codes and standards and othw govem-culate radiation absorbed doses to the embryo /fotus using a ment and industry guidance referred to in regulatory documents.

scenario that assumed injection of a bolus into the woman's The SRP-UDP has been completed and the SRP-Maintenance blood. Calculations were WM for administration at suc.

Program (SRP-MP) is now maintaining this listing. Besides up-J cessive months of pregnancy to accommodate stage depend.

dating previous information, Revision 3 adds approximately 80 ence of geometric relationships and biological behaviors of re-citations. This listing identifies the version of the code or stand-dionuclides. The gestational-stage-dependent dosimetric dose ard cited in the regulatory document, the regulatory document, factors are based on radiation absorbed doses. Multiplication by and the current version of the code or standard. It also provides appropriate quality factors conve.t these to dose equivalent, the a summary characterization of the nature of the citation. This most common quantity for stating prenatal dose limits in the listing was developed from electronic searches of the Code of i

United States. The dose factor tabulations are supplemented Federal Regulations and the NRC's Bulletins, information No-with tables of correlations and surrogate dose factors.

tices, Circulars, Enforcement Manual. Generic Letters, inspec-i hUoWCR-5753: AGING OF SAFETY CLASS 1E TRANSFORM.

tion Manual, Policy Statements, Regulatory Guides, Standard ERS IN.iAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

Technical Specifications and the Standard Review Plan ROBERTC.E.W.; EDSON,J.L; UDY,A.C. Idaho National Engi.

(NUREG 0800).

neering Laboratory. February 1996. 64pp. 9603010296. INEL.

95/0573.87307:067, NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED This report discusses aging effects on safety-related power ULTRASONIC INSERVICE INSPECTION SYSTEM.

transformers in nuclear power plants. It also evaluates mainte.

HARRIS.R.V.; ANGEL,L.J. Battelle Memorial institute, Pacife nance, testing, and monitoring practices, with respect to their Northwest Laboratory. December 1995.129pp. 9604090369.

effectiveness in detecting and mitigating the effects of aging.

PNL-8919. 87807:001.

The study follows the U.S. Nuclear Regulatory Commission's This supplement reviews the P-scan system, a computer-(NRC) Nuclear Plant-Aging Research approach. It investigates based ultrasonic system used for inservice inspection of piping the materials used in transformer construction, identifies stros*

and other components in nuclear power plants. The supplement sors and aging mechanisms, presents operating and testing ex-was prepared using the methodology described in detail in Ap-perience with aging effects, analyzes transformer failure events pendix A of NUREG/CR-5985, and is based on one month of J

reported in various databases, and evaluates maintenance prac-using the system in a laboratory. This supplement describes tices. Databases that were analyzed included the NRC's Licens-and charactertzes: computer system, ultrasonic components, ee Event Report (LER) system and the Institute for Nuclear and rnechanical components; scanning, detection, digitizing, im-e rations' Nuclear Plant Reliability Data System ag ng, data interpretation, operator interaction, data handling, and record-keeping. It includes a general description, a review NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR checklist, and detailed resurts of all tests performed.

POWER INDUSTRY Annual Summary Of Program Performance Reports CY 1995.

SILBERNAGEL,M.;

BRICHOUX,J.;

NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN DURBIN,N. Battelle Seattle Research Center. July 1996. 96pp.

SAFETY TESTING. Technical Report On The Findings Of Task 9608060285. PNL-11202,89258:230.

4 investigation of Failed Nitinol Brachytherapy Wire.

This report summarizes the data from the semiannual reports BENAC,0.J.; BURGHARD,H.C. Southwest Research Institute.

of fitness-for duty program submitted to the NRC by utilities for March 1996. 268pp. 9605130090. 04-4448-010. 88228:047.

two reporting penods: January 1 through June 30,1995,and This report covers an investigation of the nature and cause of July 1 through December 31,1995. During 1995, licensees re-failure in Nitinol brachytherapy sourcewires. The investigation ported that they conducted 150,121 tests for the presence of was initiated after two clinical incidents in which sourcewires illegal drugs and alcohol. Of these tests, 1,476 (.98%) were failed during or immediately after a treatment. The investigation confirmed positive. Positive test results varied by category of determined that the two clinical Nitinol sourcewires failed in a test and category of worker. The majority of positive test results brittle manner, which is atypical for Nitinol. There were no mate-rial anomalies or subentical flaws to explain the brittle failures.

d on w ha ng access t protected are 8

The bend tests also dernonstrated that neither moist envirork were positive from random testing and 139 were positive from for-cause testing. Follow-up testing of workers who had previ.

ment, radiation, nor low-temperature structure transformation ously tested positive resulted in 35 positive tests. For-cause was a likely root cause of the failures. However, degradation of testing resulted in the highest percentage of posdive tests; the PTFE was consistently evident, and those sourcewires about 18% of for cause tests were positrve. in comparison, shipped or stored with PTFE sleeves consistentty failed in labo-1.41% of pre-access tests and.27% of random tests were posi-ratory bend tests. On the basis of the results of this study, it tive. Positive test rates also varied by category of worker. When was concluded that the root cause of the in-serwce failures of I

all types of tests are combined (pre-access, random, for-cause the sourcewires was environmentally induced embrittlement due and follow-up testing), short. term contractor personnel had the to the breakdown of the PTFE protective sleeves in the pres-highest positive test rate at 1.44%. Licensee employees and ence of the high-radiation field and subsequent reaction or inter-long-term contractors had lower combined positive test rates action of the breakdown products with the Ndinol alloy.

(.34% and.40%, respectivey). Of the substances tested, mari-

Main Citations and Abstracts 17 NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL NUREG/CR-6174 V01: REVISED ANALYSES OF DECOMMIS-EXPERIMENTS.Results And Lessons Learned.

SiONING FOR THE REFERENCE BOILING WATER REACTOR RASMUSSEN,T.C.

Georgia, Univ.

of.

Athens, GA.

POWER STATION. Effects Of Current Regulatory And Other RHODES S.C.; GUZMAN,A.G.; et al. Arizona, Univ. of, Tucson, Considerations On The Financial Assurance Requirements Of AZ. March 1996.110pp. 9604020277. 87714:170.

The Decommissioning Rule And..

SMITH.R.I.;

Data from laboratory and field experiments in unsaturated BIERSCHBACH,M.C; KONZEK,G.J.; et al. Battelle Memorial in-fractured rock are summartzed and interpreted for the purpose stitute, Pacific Northwest Laboratory. July 1996. 120pp.

cf evaluating conceptual and numerical models of fluid, heat 9608210240. PNL-9975. 89428:001, c.nd solute transport. The experiments were conducted at four With the issuance of the Decommissioning Rule in 1988, nu-l scales, in small cores (2.5-cm long by 6-cm across), a large clear power plant licensees are required to submit to the U.S.

core (12-cm long by 10-cm across), a small block containing a Nuclear Regulatory Commission (NRC) decommissioning cost I

sirigle fracture (20 x 21 x 93 cm), and at fielu scales in bore-estimates for review. This reevaluation study provides some of holes (30-rn long by 10-cm across) at three scales (1/2,1. and the needed bases documentation to the NRC staff that will 3-metors). The smallest scale in the laboratory provided isother-assist them in assessing the adequacy of the licensee submit-mal hydraulic and thermal properties of untractured rock. Noni-tals. This report presents the results of a review and reevalua-sothermal heat, iluid and solute transport experiments were tion of the PNL 1980 decommissioning study of the WNP-2 nu-conducted using the large core. Isothermal gas and liquid flow clear plant for the DECON, SAFSTOR, and ENTOMB decom-expenments were conducted in the fractured block. Field-scale missioning attematives. These alternatives now include an initial experiments using air were used to obtain in situ permeability 5-7 year period during which the spent fuel is stored in the estimates as a function of the measurement scale, interpreta-spent fuel pool, prior to beginning major disassembly or ex-tion of experimental results provides guidance for resolving un-tended safe storage of the plant. This report also includes NRC certainties related to radionuclide migration from high level consideration that decommissioning activities leading to termi-waste repositories in unsaturated fractured rock.

nation of the nuclear license be completed within 60 years of l

final reactor shutdown, consideration of packaging and disposal NUREG/CR-6124: CHARACTERIZATION OF RADIONUCLIDE-requirements for Greater Than-Class C low-level waste, and re-CHELATING AGENT COMPLEXES FOUND IN LOW-LEVEL flects all costs in 1993 dollars. Sensitivity of the total license RADIOACTIVE DECONTAMINATION WASTE. Literature termination cost to the disposal at different low-level radioactive Review. SERNE,R.J.; FELMY,A.R.; CANTRELL,K.J.; et al. Bat-waste disposal sites, and to different depths of contaminated telle Memurial Institute, Pacific Northwest Laboratory. March concrete surface removed, is also examined.

1996.168pp. 9604160360. PNL-8856. 87884:011.

The U.S. Nuclear Regulatory Commission is responsible for NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMIS-regulating the safe land disposal of low-level radioactive wastes SIONING FOR THE REFERENCE BOILING WATER REACTOR that may contain organic chelating agents. Such agents include POWER STATION. Effects Of Current Regulatory And Other EDTA, DTPA, picoline acid, and citric acid, which can form radi-Considerations On The Financial Assurance Requirements Of onuclide-chelate compicxes that my enhance the migration of The Decommissioning Rule And...

SMITH,R.I.;

radionuclides from disposal sites. Data from the available litera-BIERSMRACH,M.C; KONZEK,G.J.; et al. Battelle Memorial in-ture indicate that chelates, can leach from solidified decontami-s A.. Pacific Northwest Laboratory. July 1996. 252pp.

nation wastes in moderate concentration and can potentially 9608210245. PNL-9975. 89422:001, complex certain radionuclides in the teachates. The effects of With the issuance of the Decommissioning Rule in 1988, nu-the formation of such radionuclide-chelate complexes on the mi-clear power plant licensees are required to submit to the U.S.

gration of radionuclides in groundwater systems is still difficult Nuclear Regulatory Commission (NRC) decommissioning cost to quantitatively predict. However, in general it appears that estimates for review. This reevaluation study provides some of both EDTA and DTPA have the potential to mobilize radionu-the needed bases documentation to the NRC staff that will clides from waste disposal sites because such chelates can assist them in assessing the adequacy of the licensee submit-leach in moderate concentration, form strong radionuclide-che-tals. This report presents the results of a review and reevalua-late complexes, and can be recalcitrant to biodegradation. It tion of the PNL 1980 decommissioning study of the WNP-2 nu-also appears that oxalic acid and citric acid will not Dreatly en.

clear plant for the DECON, SAFSTOR, and ENTOMB decom-hance the mobility of radionuclides from waste disposal sites missioning alternatives. These attematives now include an initial because these chelates do not appear to leach in high concen-5-7 year period during which the spent fuel is stored in the i

tration tend to form relatively weak radionuclide-chelate com-spent fuel pool, prior to beginning major disassembly or ex-plexes, and can be readily biodegraded. In the case of picolinic tended safe storage of the plant. This report also includes NRC acid, insufficient data are available to make definitive predic-consideration that decommissioning activities leading to termi-

tions, nation of the nuclear license be completed within 60 years of l

final reactor shutdown, consideration of packaging and disposal NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISI-requirements for Greater TharWlass C low-level waste, and re-i TION AND ANALYSIS OF EDDY CURRENT ARRAY PROBE flects all costs in 1993 dollars. Sensitivity of the total license l

DATA. PATE J.R.; DOOD,C.V. Oak Ridge National Laboratory-termination cost to the disposal at different low-level radioactive July 1996.186pp. 0608210249. ORNL/TM-13212. 89424:001, waste disposal sites, and to different depths of contaminated i

The objective of the improved Eddy-Current ISI for Steam concrete surface removed, is also examined.

Generators Tubing program is to upgrade and validate eddy-cur-rent inspections, including probes, instrumentation, and data NUREG/CR-6189: A SIMPLIFIED MODEL OF AEROSOL RE-processing techniques for inservice inspection of new, used, MOVAL BY NATURAL PROCESSES IN REACTOR CONTAIN-and repaired steam generator tubes; to improve defect detec.

MENTS. POWERS,D.A.; WASHINGTON,K.E. Sandia National I

tion, classification and characterization as affected by diameter Laboratones. BURSON,S.B.; et al. Division of Systems Technol-and thickness variations, denting, probe wobble, tube sheet, ogy (Post 941217). July 1996. 263pp. 9608060182. SAND 94-tube supports, copper and sludge deposits, even when defect 0407. 89278:001.

types and other vanables occur in combination; to transfer this Simplified formulae are developed for estimating the aerosol advanced technology to NRC's mobile NDE laboratory and decontamination that can be achieved by natural processes in staff. This report documents computer programs that were de-the containments of pressurized water reactors and in the veloped for acquisition of eddy-current data from specially-de-drywells of boiling water reactors under severe accident condi-signed 16-coil array probes. Complete code as well as instruc-tions. These simplified formulae were derived by correlation of tions for use are provided.

results of Monte Carlo uncertainty analyses of detailed models I

18 Main Citations and Abstracts of aerosol behavior under accident conditions. Monte Carlo un-tines. The programs produce files containing ASCll table = of certainty analyses of decontamination by natural aerosol proc-values and output files that can readily be imported into a com-esses are reported for 1000, 2000, 3000, and 4000 MW(th) mercial spreadsheet to be graphed or for further computations.

pressurized water reactors and for 1500, 2500, and 3500 NUREG/CR-6227: PERFORMANCE DEMONSTRATION TESTS MW(th) boiling water reactors. Uncertainty distributions for the decontamination factors and decontamination coefficients as FOR EDDY CURRENT INSPECTION OF STEAM GENERATOR functions of time were developed in the Monte Cario analyses TUBING. KURTZ,R.J.; HEASLER,P.G.; ANDERSON,C.M. Bat-by considering uncertainties in aerosol processes, material telle Memorial Institute, Pacific Northwest Laboratory. May properties, reactor geometry, and severe accident progression.

1996. 54pp. 9606180253. PNNL-9433. 88630:275.

Phenomenological uncertainties examined in this work included This report describes the methodology and results for devel-uncertainties in aerosol coagulation by gravitational collision, opment of performance demonstration tests for eddy current Brownian diffusion, turbulent diffusion, and turbulent inertia. Un-(ET) inspection of steam generator tubes. Statistical test design certainties in aerosol deposition by gravitational rettling, thermo-pnnciple were used to develop the performance demonstration phorests, diffusiophoresis, and turbulent diffusion were exam-tests. Thresholds on ET system inspection performance were ined. Electrostatic charging of aerosol particles in severe acci.

selected to ensure that field inspection systems have a high dents is discussed. Median (50 percentile),90, and 10 percent.

probability of detecting and correctly sizing tube degradation.

lie values of the uncertainty distributions for effective decon.

The technical basis for the ET system performance thresholds tamination coefficients were correlated with time and reactor is presented in detail. Statistical test design calculations for thermal power. These correlations constitute a simplified model probability of detection and flaw sizing tests are described. A that can be used to estimate the decontamination by natural recommended performance demonstration test based on the aerosol processes at three levels of conservatism. Example ap-design calculations is presented. A computer program for grad-plications of the simplified model are described.

Ing the probability of detection portion of the performance dem-

U *"'

NUREG/CR4202: LONG-TERM AGING AND LOSS-OF-COOL-ANT ACCIDENT (LOCA) TESTING OF ELECTRICAL NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CABLES.U.S./ French Cooperative Research Program.

CFR PART 61 AND OTHER SELECTED NELSON,C.F. Sandia Natonal Laboratories. GAUTHIER,G.;

RADIONUCLIDES.Uterature Review.

THOMAS,C.W.;

CARLIN,F.; et al. France. October 1996.146pp. 9611190225.

THOMAS,V.W.; ROBERTSON,D.E. Battelle Memorial Institute, IPSN 94-03. 90821:177.

Pacific Northwest Laboratory. March 1996. 42pp. 9604150341.

Experiments were performed to assess the aging degradation PNL-9444. 87865:319.

and loss-of-coolant accident (LOCA) behavior of electrical A comprehensive literature review and assessment was con.

cables subjected to long-term aging exposures. Four different ducted to identify and evaluate radioanalytical technology and cable types were tested in both the U.S. and France.1. U.S. 2 procedures used for measuring 10CFR61 radionuclides and conductor with ethylene propylene rubber (EPR) insulation and other long-lived isotopes. This review evaluated radiochemical a Hypalon lacket 2. U.S. 3 conductor with cross-linked polyeth-procedures currently in use at a number of laboratories in the ylene (XLPE) insulation and a Hypalon Jacket. 3. French 3 cork US, as well as identifying new advanced methods and tech-ductor with EPR insulation and Hypalon Jacket. 4. French co-niques which could be adapted for routine radiochemical analy-axial with polyethylene (PE) insulation and a PE jacket. The ses of low-level radioactive waste. The 10CFR61 radionuclides data represent up to 5 years of simultaneous aging where the include (14)C, (60)Co, (59,63) Ni, (90)Sr, (94)Nb, (99)Tc, (129)l, cables were exposed to identical aging radiation doses at either (137)Cs and TRU lsotopes with half-lives greater than five 40 degrees C or 70 degrees C; however, the dose rate used for years. The other low-level radionuclides of interest include the aging irradiation was varied over a wide range (2-100 Gy/

(7,10)Be, (26)Al, (36)Cl, (93)Mo, (109,113m)Cd, and br). Aging was followed by exposure to simulated French LOCA (121m,126)Sn, which may be present in various types of waste conditions. Several mechanical, electrical, and physical-chemi-streams from nuclear power statioria.

cal condition monitoring techniques were used to investigate the degradation behavior of the cables. All the cables, except for NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR the French PE cable, performed acceptably during the aging ON MAIN STEAM ISOLATION VALVES AND VALVE OPERA.

1 and LOCA simulations. In general, cable degradation was high.

TORS. CLARK,R.L Oak Ridge National Laboratory. March est for the lowest dose rate, and the amount of degradation de.

1996.108pp. 9603260298. ORNL-6814. 87640:001.

creased as the dose rate was increased.

In recent years main steam isolation valve (MSIV) operating 1

problems have resulted in significant operational transients i

NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF (e.g., spurious reactor trips, steam generator dry out, excessive CONTROL ROOM HABITABILITY (HABIT). STAGE,S.A. Battelle valve seat leakage), increased cost, and decreased plant avall-Memorial institute, Pacific Northwest Laboratory. June 1996.

ability. A key ingredient to an engineering-oriented reliability im-i 173pp. 9606250169. PNL-10496. 88701:066.

provemen: effort is a thorough understanding of relevant histori-1 This report describes the computer codes for evaluation of cal experience. A detailed review of historical failure data avail-control room habitability (HABIT). HABIT is a package of corrw able through the institute of Nuclear Power Operation's Nuclear I

puter codes designed to be used for the evaluation of control Plant Reliability Data System has been conducted for several room habitability in the event of an accidental release of toxic types of MSIVs and valve operators for both boiling-water reac-chemicals or radioactive materials. Given information about the tors and pressurized-water reactors. The focus of this review is design of a nuclear power plant, a scenario for the release of on MSIV Failures modes, actuator failure modes, consequences toxic chemicals or radionuclides, and information about the air of failure on plant operations method of failure detection, and flows and protection systems,of the control room; HABIT can major stressors affecting both valves and valve operators, be used to estimate the chemical exposure or radiological dose of control room personnel. HABIT is an integrated package of NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

several programs that previously needed to be run separately CAREW,J.F.; ARONSON,A.; COKINOS,D.M.; et al. Brookhaven and required considerable user intervention. These are National Laboratory. May 1996. 71pp. 9606070090. BNL.

EXTRAN, CHEM, TACTS, FPFP-2, and CONHAB. New input NUREG-52425. 88490:283.

routines have been written for these routines using data input A detailed evaluation of the fuel burnup dependent power dis-windows. These are designed for easy use entering, reviewing tribution and the scram reactivity for the PIUS reactor design and revising the data. The programs can now be run in se-has been performed. The analyses were carried out using the Quence as an integrated package. Improvements have been CPM lattice physics and NODE.P2 core neutronics/ thermal-hy-made in the computational methods used by some of the rou-draulics codes and are based on the information provided in the

Main Citations and Abstracts 19 PIUS Preliminary Safety Information Document, t,ycle depletion NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS calca ations were performed for a set of nine representative ini-SCALING MODELS TO THE DUCTILE TO-BRITTLE TRANSI-tia' N re loadings and the three-dimensional core power distnbu.

TION. LINK,R.E. Navy, Dept. of. JOYCE,J.A. U.S. Naval Acade-tiores were determined. These calculations indicate that the my, Annapolis, MD. January 1996. 42pp. 9602220350.

PlUS radial F( a h) and total F(O) power peaking is significantly 87234:102.

stronger than indcated by the PlVS reference des #gn values.

An experimental investigation of fracture toughness in the The scram reactmty resulting from the injection of highly borat.

ductile-bntile transition range was conducted. A large number of ed pool water was calculated for a senes of tirne-dependent ASTM A533, Grade B steel, bend and tension specimens with linear ramp and square-wave pool flows. The three-dimensional varying crack lengths were tested throughout the transition distribution of the pool water throughout the core was modeled region. Cleavage fracture toughness scaling models were uti-lized to correct the data for the loss of constraint in short crack and the spatial reactmty effects of the distributed boron were determined. For pool flows that increase as a linear ramp, the specimens and tension geometries. The toughness scaling spatial reactivity effects of the distributed boron were very models were effective in reducing the scatter in the data, but tended to over. correct the results for the short crack bend small. In this case, a constant core-average boron reactivity co-specimens. A proposed ASTM Test Practice for Fracture efficient can be used to model the PlVS scram reactivity.

Toughness in the Transition Range, which employs a master NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS:

curve concept, was applied to the results. The proposed master LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM curve over predicted the fracture toughness in the mid-transition LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND and a modified master curve was developed that more accu-1995. MCCONNELLJ.W.; ROGERS R.D. Idaho National Engi, rately modeled the transition behavior of the matenal. Finally, the modified master curve and the fracture toughness scaling neering Laboratory. JASTROW,J.D.; et al, Argonne National models were combined to predict the as-measured fracture Laboratory. June 1996.121pp. 9607090148. INEL-95/0073.

toughness of the short crack bend and the tension specimens.

88956:112 H was hn mat when N scahng Ms w CW h The Field Lysimeter investigations: Low-Level Waste Data data for loss of constraint, they can also lead to non. conserva-Base Development Program, funded by the U.S. Nuclear Regu-latory Commission NRC), is (a) studying the degradation effects j

me e in EPICOR-ti organic ion-exchange resins caused by radiation, (b) examining the adequacy of test procedures recommended in NUREG/CR-6280: TECHNOLOGY, SAFETY,AND COSTS OF DE-the Branch Technical Position on Waste Form to meet the re-COMMISSIONING A REFERENCE LARGE 1RRADIATOR AND quirements of 10 CFR 61 using solidified EPICOR-Il resins, (c)

REFERENCE SEALED SOURCES.

HAFFNER,0.R.;

cbtaining performance information on solidsfied EPICOR-Il ion-VILLEGAS.A.J. Battelle Memonal Institute, Pacific Northwest exchange resins in a disposal environment, and (d) determining Laboratory. January 1996.109pp. 9602290251. 87295:001, the condition of EPICOR-il liners. Results of the final 2 (10 total)

This report contains the results of a study sponsored by the years of data acquisition from operation of the f> eld testing are U.S. Nuclear Regulatory Commission (NRC) to examine the de-presented and discussed. During the continuing field testing, commissioning of large radeoactive irradiators and their respec-both portland type 1-11 cement and Dow vinyt ester styrene tive facilities, and a broad spectrum of sealed radioactive waste forms are being tested in fysimeter arrays located at Ar-sources and their respective devices. Conceptual decommis-gonne National Laboratory-East in lilinois and at Oak Ridge Na-sioning activities are identified, and the technology, safety, and tional Laboratory. The expenmental equipment is described and costs (in earty 1993 dollars) associated with decommissioning resuits of waste form characterization using tests recommended the reference large irradiator and sealed source facilittes are by the NRC's " Technical Position on Waste Form" are present.

evaluated. The study provides bases and background data for ed. The study is designed to provide continuous data on nuclide possible future NRC rulemaking regarding decommissioning, for release and movement, as well as environmental conditions, evaluation of the reasonableness of planned decommissk.Nng over a 20-year period. At the end of the tenth year, the experi-actions, and for determining if adequate funds are reserved by the licensees for Menui,WJng of their large irradiator or ment was closed down. Examination of soil and waste forms is sealed source fachties. Another purpose of this study is to pro-planned to be conducted next and will be reported later, vide background and information to assist licensees in planning NUMEG/CR4270: ESTIMATING BOILING WATER REACTOR and carrymg out the decommissioning of their sealed radioac.

DECOMMISSIONING COSTS.A User's Manual For The BWR trve sources and respective facilites.

Cost Estimating Computer Program (CECP) Software. Final NUREG/CR4300: SCIENTIFIC DESIGN OF PURDUE UNIVERSI-Report. BIERSCHBACH,M.C Battelle Memonal Institute, Pacific TY MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY Northwest Laboratory. June 1996. 216pp. 9607150168. PNL-(PUMA) FOR GE SBWR. ISHil,M.; REVANKAR,S.T.:

10086. 89003 258.

DOWLATI,R.; et al. Purdue Univ., West Lafayette, IN. April Nuclear power plant licensees are required to submit to the 1996. 279pp. 9605130147. PU-NE 94/1. 88238:001.

U.S. Nuclear Regulatory Commission (NRC) for review decom-The scientific design of the scaled facility (PUMA) has been missioning cost estimates. This user's manual and the accom-camed out under the pr4ect " Confirmatory integral System panying Cost Estimating Computer Program (CECP) software Testing for GE SBWR Design" The design was based on the provide a cost calculating methodology to the NRC staff that three level scaling method developed for this task. The first will assist them in assessing the edequacy of the licensee sub-level of scaling is based on the integral response function. The mittals. The CECP, designed to be used on a personal comput-second level scaling is for the boundary flow of mass and er, provides eshmates for the cost of G,cesw.,4.is g BWR energy between components. The third level of scaling is fo-power stations to the point of license termination. Such cost es-cused on the key local phenomena and constitutive relations.

timates include component, piping, and equipment removal The facility has 1/4 height and 1/100 area ratio scaling. This costs; packaging costs; decontamination costs; transportation corresponds to a volume scale of 1/400 and power scaling of costs; burial costs; and manpower costs. In addition to costs, 1/200. The time will run twice as fast in the model as predcted the CECP also calculates burial volumes, person-hours, crew-by the present scaling method. The PUMA is scaled for full hours, and exposure person-hours associated with decommis-pressure and is intended to operate at and below 150 psia foi-sioning.

lowing scram. The facihty models all the major components of SBWR.

l 1

l 20 Main Citations and Abstracts NUREG/CR-6314: QUALITY ASSURANCE INSPECTIONS FOR that cause degradation and aging in large electnc motors oper-SHIPPING AND STORAGE CONTAINERS. STROMBERG,H.M.;

ating in various plant locatons and environments. The operating ROBERTS,G.D.; BRYCE,J.H. Idaho National Engineering Labo-history of these machines in nuclear plant service was studied ratory. April 1996. 77pp. 9605310158. INEL-95/0061.

by review and analysis of failure reports in the NPRDS and LER 88395:119.

databases. This was supplemented by a review of motor de-This document is a guide for conducting quality assurance in-signs, and their nuclear and balance of plant apphcations, in spections of transportaten packaging and dry spent fuel stor-order to characterize the failure mechanisms that cause degra-i age system suppliers. This document is used during an inspec-daton, aging, and failure in large electnc motors. A generic fail-I tion to determine regulatory compliance with Title 10 of the ure modes and effects analysis for large squirrel cage induction l

Code of Federal Regulations, Part 71, Subpart H; Title 10 of the motors was performed to identify the degradation and aging Code of Federal Regulatons, Part 72 Subpart G; and Title 10 mechanisms affecting various components of these large l

of the Code of Federal Regulations, Part 21 and quahty assur-motors, the failure modes that result, and their effects upon the l

ance program commitments. The guidance provides a frame-function of the motor. The effects of large motor failures upon i

work for transportation packaging and dry spent fuel storage the systems in which they are operating, and on the piant as a system inspections. Inspectors are provided with the flexibility to whole, were analyzed from failure reports in the databases. The adapt the methods and concepts to meet the inspection re-effectiveness of the industry's large motor maintenance pro-quirements for the particular facility. This guide was developed grams was assessed based upon the failure reports in the data-to provide a structured and consistent approach for inspections.

bases and reviews of plant maintenance procedures and pro-l The method separates each performance element into several grams.

areas for inspection and identifies guidelines, based on regula-tory requirements, to qualitatively evaluate each area. This doc-NUREG/CR-6337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 ument was also developed to serve as a field manual to facili-ROUND-ROBIN ANALYSES.

RAHMAN.S.;

OLSON.R.;

I tale the quality assurance inspecten activities.

ROSENFIELD,A.; et al. Battelle Memonal Institute, Columbus Laboratories. February 1996.182pp. 9602290264. BMI-2186.

NUREG/CR-6317: NUMERICAL INVESTIGATION OF 3-D CON-87295:113.

STRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND This report presents a summary of the results from three one-

[

C(T) SPECIMENS NEVALAINEN M. Technical Research Centre day international round-robin workshops which were organized i

of Finland (VTT). DODDS.R.H. lilinois, Univ. of, Urbana, IL July by Battelle in conjunction with the Second international Piping 1996. 56pp. 9608230213. 89455:100.

Integnty Research Group (IPlHG-2) Program. The objective of This investigation employs 3 D nonlinear finite element analy-these workshops was to develop a consensus in handling diffi-ses to conduct an extensive parametric evaluation of crack front cult analytical problems in leak-before-break and pipe flaw eval-stress inaxiality for deep notch SE(B) and C(T) specimens and uations. The workshops, which were held August 5,1993, shallow notch SE(B) specimens, with and without side grooves-March 4,1994, and October 21, 1994 at Columbus, Ohio, in-Crack front conditions are characterized in terms of J-Q trajec-volved various technical presentations on the related research tones and the constraint scaling model for cleavage fracture efforts by the IPIRG-2 member organizations and solutions to toughness proposed previously by Dodds and Anderson. The 3-several round-robin problems. Following review by the IPIRG-2 D computational results imply that a significantfy less stnct size /

members, four sets of round4obin problems were developed.

deformation limits indicated by prevous plane-strain computa-They involved: (1) evaluations of fracture properties and pipe tions, relative to the limits indicated by previous plane strain loads, (2) crack-opening and leak-rate evaluations, (3) dynamic l

computations, is needed to maintain small-scale yielding condL analysis of cracked pipes, and (4) fracture evaluations of tions at fracture by a stress-controlled cleavage mechanism in elbows. A total of 18 organizations from the United States, deep notch SE(B) and C(T) specimens. Additional new results Japan, Korea, and Europe solved these round-robin problems.

made available from the 3-D analyses also include revised r/-

The analysis techniques employed by the participants included i

plastic factors for use in experimental studies to convert meas-ooth finite element and engineering methods. Based on the re-i ured work quantities to thickness average and maximum (local) suits from these analyses, several important observations were J-values over the crack front.

made concerning the predictive capability of the current frac.

NUREG/CR-6332: MICROSTRUCTURAL CHARACTERIZATION ture-mechanics and thermal-hydraulics models for thee : plica-

)

OF SELECTED AEA/UCSB MODEL FECUMN ALLOYS.

tons in nuclear piping and piping welds.

l RICE,P.M.; STOLLER,R.E. Oak Ridge National Laboratory. June i

1996.63pp.9607090195. ORNL/TM-12980. 86958:266' NUREWCR-632 RESMON & ME DRECT NAIN-MENT HEATING ISSUE FOR ALL WESTINGHOUSE PUNTS l

A set of 22 model femtsc alloys was purchased as part of a WITH LARGE DRY CONTAtNMENTS OR SUBATMOSPHERIC collaborative research progam by the AEA Harwell Laboratory and the Urwversity of California at Santa Barbara. Nine cf these CONTAINMENTS. PILCH.M.M.; ALLEN.M.D.; KLAMERUS E.W.

Sandia National Laboratories. February 1996. 241pp.

l alloys were selected by the Oak Ridge National Laboratory for 9603260307. SAND 95-2381. 87624:001.

I use in a series of ion irradiation experiments investigating dis-This report uses the scenanos described in NUREG/CR-6075 persed barrier harderung These nine alloys contain varying amounts of copper, manganese, titanium, carbon, and nitrogen.

and NUREG/CR-6075 Supplement 1, to address the direct The alloys have been charactertzed by transmisson electron contenment heating (DCH) issue for al) Westinghouse plants microscopy in the as-received condition to provide a baseline with large dry or suuatmosphenc containments. DCH is consid-for companson with the irradiated specimens. A description of ered resolved if the conditional containment failure probability the microstructural observatons rs provided for future reference.

(CCFP) is less than 0.1. Loads versus strergh evaluatons of This summary focuses on the type and size distnbutions of the the CCFP were performed for each plant using plant-specific in-ec tes ent; grain size gnd dislocation measurements formation. The DCH issue is considered resolved for a plant if a screening phase results in a CCFP less than 0.01, which is more stringent than the overall success enterion. If the screen-NUREG/CR-6336: AGING ASSESSMENT OF LARGE ELECTRIC ing phase CCFP for a plant is greater than 0.01, then refined MOTORS IN NUCLEAR POWER PLANTS. VILLARAN,M.;

containment loads evaluatons must be performed and/or the SUBUDHl.M. Brookhaven Nationa' Laboratory. March 1996, probability of high pressure at vessel breach must be analyzed.

136pp.9603260290. BNL-NUREG 52460. 87640:106.

These analyses could be used separately or could be integrated Large electric motors serve as the prime movers to dnve high together to re-calculate the CCFP for an indrvidual plant to capacity pumps, fans, compressors, and generators in a variety reduce the CCFP to meet the overall success cnteren of less

(

of nuclear plant systems. This study examined the stressors than 0.1. The CCFPs for all of the Westinghouse plants with dry

Main Citations and Abstracts 21 containments were less than 0.01 at the screening phase, and ing procedures for evaluation of the effects of microbiologically thus, the DCH lasue is resolved for these plants based on con-influenced chemical attack on cement-solidified LLW. The pro.

cedures that have been developed in this work are presented tainment lods done. No additional analyses are required.

and discussed. Groups of microorganisms indigenous to LLW NUREG/CR-63N AGING ASSESSMENT OF WESTINGHOUSE disposal sites were employed that can metabolically convert or-PWR AND GENERAL ELECTRIQ BWR CONTAINMENT ISOLA-gans and inorganc substrates mto orgas and nhal ah TlON FUNCTIONS. LEE.B.S.; TRAVIS,R.; GROVE.E.; et al.

Such acids aggressively react with cement and can ultimately Brookhaven Natonal Laboratory. March 1996. 154pp.

lead to structural failure. Results on the application of mecha-960402032*. BNL NUREG-52462. 87715:001.

nisms inherent in microbially influenced degradation of cement-A study was performed to asses 9 the effects of aging on the based material are the focus of this final report. Data-validated Containment isolation (Cl) functions of Westinghouse Pressur-evidence of the potential for microbially influenced deterioration ized Water Reactors and General Electric Boiling Water Reac-of cement-solidified LLW and subsequent release of radionu-tors. This study is part of the Nuclear Plant Aging Research clides developed dunng this study are presented.

(NPAR) program, sponsored by the U.S. Nuclear Regulatory Commission. The objectives of this program are to provide an NUREG/CR-6344: REAL-TIME 3-D SAFT-UT SYSTEM EVALUA.

understanding of the aging progress and how it affects plant TION AND VALIDATION. DOCTOR,S.R.; SCHUSTER,G.J.;

safety so that it can be properly manageo. This is one of a REID,L.D.; et al. Battelle Memorial Institute, Pacific Northwest number of studies performed under the NPAR program which Laboratory. September 1996. 277pp. 9612240090. PNNL-provide a technical basis for the identification and evaluation of 10571. 91198:001.

degradation caused by age. The failure data from national data-SAFT-UT technology is shown to provide significant enhance-bases, Nuclear Plant Reliability Data System (NPRDS) and Li-ments to the inspection of materials used in U.S. nuclear power censee Event Reports (LERs), as well as plant specific data plants. This report provides guidelines for the implementation of were reviewed and analyzed to understand the effects of aging SAFT UT technology and shows the results from its application.

on the Cl functions. This study provided information on the ef-An overview of the development of SAFT-UT is provided so that fects of aging on component failure frequency, failure modes, the reader may become familiar with the technology. Then the and failure causes. Current inspection, surveillance, and moni-basic fundamentals are presented with an extensive list of refer-toring practices were also reviewed.

ences. A comprehensive operating procedure, which is used in NUREG/CR-6340: AGING ASSESSMENT OF SURGE PROTEC-conjunction with the SAFT-UT field system developed by Pacif>c TiVE DEVICES IN NUCLEAR POWER PLANTS. DAVIS,J.F.;

Northwest National Laboratory (PNL), provides the recipe for SUBUDHI,M. Brookhaven National Laboratory. CARROLL.D.P.

both SAFT data acquisition and analysis. The specification for the hardware implementaton is provided for the SAFT-UT Florida, Univ. of, Gainesvine, FL January 1996. 179pp.

9603040082. BNL-NUREG-52463. 87317:001.

system along with a d6scription of the subsequent develop-ments and improvements. One development of technical inter-A study has been performed that assesses the effects of est is the SAFT real-time processor. Performance of the reak l

aging on the performance and availability of surge protective time processor is impressive and comparison is made of this devices (SPDs), commonly called surge arresters and surge suppressors, used in electrical power and control systems in dedicated parallel processor to a conventional computer and to U.S. commercial nuclear power plants. This study is one of a the newer high-speed computer architectures designed for number of studies performed under the Nuclear Plant Aging Re-image processing. Descriptions of other improvements, includ-search (NPAR) program. One of the many purposes of that pro ing a robotic scanner, are provided.

gram is to provide a technical basis for the identification and NUREG/CR-6345: RADIATION DOSE ESTIMATES FOR RADIO-evaluation of degradation caused by age. Although surge pro.

PHARMACEUTICALS.

STABIN,M.G.;

STUBBS,J.B.;

tective devices have not been classified as safety-related, they TOOHEY,R.E. Oak Ridge Associated Universites. April 1996.

i are risk important because they can minimize the initiating event 92pp. 9605290091. 88375:133.

frequencies associated with loss of offsite power (LOOP) and Tables of radiation dose estimates based on the Cristy-Ecker.

I reactor trip. Conversely, their failure due to age, or other man adult male phantom are provided for a number of radio-causes, might increase the initiating event frequencies. Because pharmaceuticals commonly used in nuclear medicine. Radiation of their importance, especially those in (lightning) high flash dose estimates are listed for all major source organs, and sev-density regions to the U.S., the proper application and coordina_

eral other organs of interest. The dose estimates were calculat-tion of high voltage and low voltage SPDs are important in en_

ed using the MIRD Technique as implemented in the MIR.

suring that overvoltage transients will not increase plant risk.

DOSE 3 computer code, developed by the Oak Ridge institute NUREG/CR-6341: MICROBIAL DEGRADATION OF LOW LEVEL for Science and Education, Radiation internal Dose information l

RADIOACTIVE WASTE. Final Report.

ROGERS,R.D.;

Center. In this code, residence times for source organs are l

HAMILTON,M.A.; VEEH.R.H.; et al. Idaho National Engineering used with decay data from the MIRD Radionuclide Data and Laboratory. June 1996.116pp. 9607090197. INEL-95/0215 Decay Schemes to produce estimates of radiation dose to The u lear Regulatory Commission stipulates in 10 CFR 61 kre age that disposed low-level radioactive waste (LLW) be stabilized.

To provide guidance to disposal vendors and nuclear station NUREO/CR-6346: HYDROLOGIC EVALUATION METHODOLO-waste generators for implementing those requirements, the GY 6 OR ESTIMATING WATER MOVEMENT THROUGH THE NRC developed the Technical Position on Waste Form, Revi-UNS, fURATED ZONE AT COMMERCIAL LOW-LEVEL RADIO-sion 1. That document details a specified set of recommended ACTii 'E WASTE DISPOSAL SITES.

MEYER,P.D.;

testing procedures and enteria, including several tests for deter-ROCKMOLD,M.L; NICHOLS,W.E.; et al. Battelle Memorial Insti-mining the biodegradation properties of waste forms. Informa-tute, Pacific Northmt Laboratory. January 1996. 134pp.

tion has been presented by a number of researchers, which in-96030103.8. PNL-In843. 87311:068.

dicated that those tests may be inappropriate for examining mi-This repet ioentifiet key technical issues related to hydrolog-crobia: degradation of cement. solidified LLW. Cement has been ic assessmeat of water ?ow in the unsaturated zone at low-level widely used to solidify LLW; however, the resulting waste forms radioactive waste (LLW).1:sposal f acilities. In addition, a meth-are sometimes susceptible to failure due to the actions of waste odology for incorporating those issues in the performance as-constituents, stress, and environment. The purpose of this re-sessment of proposed LLW disposal facilities is identified and search program was to develop modified microbial degradation evaluated. The issues discussed fall into four areas: estimating test procedures that would be more appropriate than the exist-the water balance at a site (i.e., infdtration, runoff, water stor-i

i 22 Main Citations and Abstracts i

l age, evapotranspirabon, and recharge); analyzing the hydrologic NUREG/CR 6357: EVALUATION AND FIELD VAllDATION OF

)

performance of engineered components of a facihty; evaluatng EDDY CURRENT ARRAY PROBES FOR STEAM GENERATOR the application of models to the predicton of facihty perform-TUBE INSPECTION. DODO.C.V.; PATE.J R. Oak Ridge National 1

l ance; and estimating the uncertainty in predicted facility per-Laboratory. July 1996. 86pp. 9608210247. ORNL/TM-13213.

I formance. To illustrate the application of the methodology, two 89424:189.

j examples are presented. The first example is of a below ground The objective of the improved Eddy-Current ISI for Steam vauft located in a humid erwironment. The second example Generator Tubing program is to uograde and vahdate eddy-cur.

looks at a shallow land burial facility located in an and environ-rent inspections, including probes, instrumentation, and data ment. The examples utshze actual site-specific data and realist c processing techniques for inservice inspection of new, used, 1

facihty designs. The two examples illustrate the issues unique to and repaired steam generator tubes; to improve defect detec-humid and arid sites as well as the issues common to all LLW tion, classification and charactenzation as affected by diameter sites. Strategies for addressing the analytical difficultes ansing and thickness variabons, denting, probe wobble, tube sheet, in any complex hydrologic evaluation of the unsaturated zone tube supports, copper and sludge deposits, even when defect are demonstrated' types and other variables occur in combination; to transfer this

)

advanced technology to NRC's mobile NDE laboratory and 1

NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALY-staff. This report describes the design of specialized high-speed SIS (ATHEANA). Technical Basis And Methodology Description.

16-coil eddy-current array probes. Both pancake and rejection COOPER,S.E. Science Applications intomational Corp. (formerfy coils are cmsded Test resuus frm inspectons using the Science Applications, Inc.). RAMEY SMITH,A. Dwision of Sys-wWng steam generators are gum Computer pro-tems Technology (Post 941217). WREATHALLJ.; et al. Affili-grams devel ped f r pr be calculations are also supplied.

J ation Not Assigned. May 1996.111pp. 9607090121. BNL-NUREG/CR4360:

SUMMARY

OF AIR PERMEABILITY DATA NUREG-52467, 88956:001.

FROM SINGLE-HOLE INJECTION TESTS IN UNSATURATED Probabihstic risk assessment (PRA) has become an important FRACTURED TUFFS AT THE APACHE LEAP RESEARCH

. tool in the nuclear power industry, both for the Nuclear Regula-SITE: RESULTS OF STEADY-STATE TEST INTERPRETATION.

j tory Commission (NRC) and the operating utilstes. Human rel6 GUZMAN,A G.; GEDDIS,A.M.; HENRICH,M.J.; et al. Arizona, ability analysis (HRA) is a entical element of PRA; however, limi.

Univ. of, Tucson, AZ. March 1996, 175pp. 9604230343.

tations in the analysis of human actions in PRAs have long 87997:011.

been recognized as a constraint when using PRA. A multidisch

.This document summartres air permeability estmetes ob-plinary HRA framework has been developed with the objective tained from single hole pneumatic injection tests in unsaturated of providing a structured approach for analyzing operating expe-fractured tuffs at the Covered Borehole Site within the larger rience and understanding nuclear plant safety, human error, and Apache Leap Research Site. Only permeabtisty estmatos ob-the undertying factors that affect them. The concepts of the tained from a steady state interpretation of relatwely stable framework have matured into a rudimentary working HRA pressure and flow rate data are included. Tests were conducted n e es WW at M Mus M h Wn% aN method. A trial application of the method has demonstrated that it is possible to identify potentially significant human failure one vertical borehole. Five of the boreholes are 30 m long, one events from actual operating experience which are not generalty has length of 45 m. Over 180 borehole segments were tested between packers set 1 rn apart. Additional tests were conduct-

)

included in current PRAs, as well as to identify associated per-ed in segments of lengths 0.5,2.0 and 3.0 m in one borehole, formance shaping factors and plant conditions that have an ob-and 2.0 m in another borehole, bringing the total numter of servable impact on the frequency of core damage. A general tests to over 270. Tests were conducted by maintaining a con-process was developed, albeit in preliminary form, that address-stant injection rate until air pressure became relatwely stable es the iteratwo steps of defining human failure events and estk and remained so for some time. The injection rate was then irk j

mating their probabilities using search schemes. Additionally, a cremented by a constant value and the procedure repeated.

knowledge-base was developed which describes the links be-Three or more such incremental steps were conducted in each l

tween performance shaping factors and resulting unsafe ac-borehole segment while recording the air injection rate, pres.

tions.

sure, temperature, and relatwo humidity. A description of field operating procedures used to insure compliance with OA/OC NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED requirements is included.

RULE ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-ING AND RELATED DOCUMENTS. PAGE G.; CAPLIN,J.;

NUREG/CR-6365: STEAM GENERATOR TUBE FAILURES.

SMITH D.; et al. Advanced Systems Technology, Inc. March MACDONALD,P.E.; SHAH,V.N.; WARD.L.W. Idaho National En-1996.166pp. 9604020352. 87712:160.

gineering Laboratory. April 1996. 303pp. 9607100298. INEL 95/

0383 The Nuclear Regulatory Commission (NRC) is conductng an r

w nd mmary of the available informahon on steam enhanced participatory rulemaking to establish radiological ente-ria for the decommissioning of NRC licensed facilities. As a part generator tubing failures and the impact of these failures on of this action, the Commission published in the Federal Register tant safety is presented. The following topics are covered; p;essunzed water reactor (PWR), Canadian deuterium uranium (59 FR 43200), on August 22,1994, a proposed rule on radio-(CANDU) reactor, and Russian water moderated, watercooled logical criteria for decommissioning, solicitng comments both energy reactor (WER) steam generator degradation, PWR on the rule as proposed and on certain specific items as identi-steam generator tube rupturos, the thermal-hydrauhc response fled in its supplementary statement of considerations. A draft of a PWR plant with a fautted steam generator, the risk signifi-Generic Envronmental Impact Statement (GEIS) In support of cance of steam generator tube rupture accidents, tubing inspec-the rule, also published in August 1994 as NUREG-1496, alo g tion requirements and fitness-for-service criteria in vanous coun-wtth its Appendix A (NUREG 1501), were also made available tries, and defect detecton rehability. Steam generator tube for comment. A staff working draft on regulatory guidance damage is caused by many devarse degradation mechanisms, (NUREG 1500) was also made available. This report summa-some of which are difficult to detect and predict. The frequency j

rized the 1,309 comments on the proposed rule and supple-of steam generator tube ruptures can be significantly reduced 1

mentary items and the 311 comments on the GEIS as excerpt-through appropnate and timely inspections and repairs or re-1 ed from 101 docketed letters received as sohcited in the Feder-moval from service. However, a continuing issue has been ex-

)

al Register notice. Comments from two NRC/ Agreement-States actly what constitutes an appropnate and tamely inspection and meebngs are also summarized.

which degraded tubes are still fit for service. There have been 1

Main Citations and Abstracts 23 many different approaches to this problem throughout the world.

NUREG/CR-6374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR Although steam generator tube ruptures are small contnbutors RADIOLABELED ANTIBODIES AND RELATED ISSUES.

to the total core damage frequency calculated in probabihstic KAURIN.D.G.; CARSTEN,A.L; et al. Brookhaven National Labo-risk assessments, they are nsk sigriificant because the radionu-ratory. BARBER,D.E. Minnesota, Univ. of, Minneapolis, MN.

j clides are likely to bypass the reactor containment building.

August 1996. 176pp. 9609100277. BNL-NUREG-52476.

89609:061.

NUREG/CR-6366: POLYRES: A POLYGON-BASED RICHARDS Radiolabeled antibodies (RABs) are being developed and j

EQUATION SOLVER. HILLS.R.G. New Mexico State Univ., Las used in medical imaging and therapy in rapidly increasing num-Crucos, NM. MEYER,P.D.; ROCKHOLD,M.L. Battelle Memorial bers. There are concems about the radiation exposure of care-Institute, Pacific Northwest Laboratory. December 1995. 68pp.

givers and the general public from treated patents. The magni-9605220418. PNL 10709. 88314:235-tude of this hazard is closely related to the RABs' whole-body

)

This document desenbes the theory, implementation, and use effective half-life (T(e)). Data on whole-body effective half-lives j

of a software package designed to solve the transient, two-di-were calculated from external dose rates obtained from attend-mensional, Richards equation for water flow in unsaturated-ing physicians and radiation safety officers at participating insti-saturated soils. This package was specifically designed to tutions. Calculations of T(e)s were made using exponential re-model complex geometries with minimal input from the user.

gression analyses of data from patents receiving single and The spatial vanation of the hydraulic properties can be defined multiple administrations. These data were analyzed on the basis across individual polygon-shaped subdomains, called objects.

of age, sex, isotope label, radiation energy, antibody type, dis.

These objects combine to form a polygon-shaped model ease treated, method of administration, and number of adminis-domain. Each object can have its own distribution of hydraulic trations. The effective half-life in the blood did not correlate with parameters. The resulting model domain and polygon-shaped the T(e). The values of T(e) varied by a factor of two for pa-internal objects are mapped onto a rectangular, finite volume, tients taking the same RAB. A single exponential clearance computational grid by a preprocessor. This allows the user to rate, compared with a bi-exponential clearance rate, provides an i

specify model geometry independently of the underlying grid adequate fit for 95% of the data sets tested.

and greatty simplifies user input for complex geometnes. In ad-dation, this approach significantly reduces the computational re.

NUREG/CR-6375: STRAIN RATE AND INERTIAL EFFECTS ON quirements since complex geometnes are actually modeled on IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECl-a rectangular gnd. This results in well-structured, finite differ-MENTS. VARGAS,P.M.; DODDS,R.H. Illinois, Univ. of, Urbana, ence-like systems of equations that require minimal storage and IL. June 1996. 27pp. 9608060180. 89258:203, are very efficient to solve. The documentation for this software When the severity of impact loads is sufficient to produce package includes a user's manual, a detailed description of the large inelastic deformations, the assessment of crack tip condi-undertying theory, and a detailed discussion of program flow.

tions must include the effects of plasticity, strain rate and sner-Several example problems are presented that show the use and tia. This work examines the interaction of impact loading, inelas-features of the software package. The water flow predictions for tic material deformation and rate sensitivity with the goal of im-several of these example problems are compared to those of proving the interpretation of ductile fracture toughness values another algonthm (Kirkland et al.,1992) to test for prediction measured under dynamic loading. Three-dimensional, nonlinear equivalency. The computer code desenbed in this document is dynamic analyses are performed for SE(B) fracture specimens available from the Energy Science and Technology Software (a/W = 0.5,0.15,0.0725) subjected to impact loading. Loading Center, P.O. Box 1020. Oak Ridge, TN 37831-1020.

rates obtained in conventional drop tower tests (impact load-line velocities of = 6 m/sec)are applied in the analyses. Strains at NUREG/CR-6367: F.YPERIMENTAL STUDY OF HEAD LOSS key locations on the specimens and the support reactions (ap-AND FILTRATIO3 WI LOCA Ogr]RIS. RAO.D.V.; SOUTO F.J.

plied load) are extracted from the analyses to assess the accu-Science & Engnwg AssociaQ, Inc. February 1996.153pp.

racy of static formulas commonly used to estimate applied J 9603190128. SEK95-554-06A:8. 87520:130.

values. Inertial effects on the applied J are quantified by exam-A senes of controlled experiments were conducted to obtain ining the acceleration component of J evaluated through a head loss and filtration characteristics of debris beds formed of domain integral procedure.

NUKON(TM) fibrous fragments, and obtain data to validate the semi-theoretical head loss model developed in NUREG/CR-NUREG/CR-6383: CORROSION FATIGUE OF ALLOYS 600 AND 6224. A thermally insulated closed-loop test set-up was used to 690 IN SIMULATED LWR ENVIRONMENTS. RUTHER,W.E.;

conduct expenments using beds formed of fibers only and fibers SOPPET,W.K.; KASSNER,T.F. Argonne National Laboratory, intermixed with particulate debris. A total of three particulate April 1996. 56pp. 9604230394. ANL-95/37. 87993:276.

i mixes were used to simutate the particulate debns. The head Crack growth data were obtained on fracture-mechanics loss data were obtained for theoretical fiber bed thicknesses of specimens of Alloy 600 and 690 to investigate environmentally 1

0.125 inch to 4.0 inches; approach velocities of 0.15 to 1.5 ft/s; assisted cracking (EAC) in simulated boiling water reactor and temperatures of 75 degrees F and 125 degrees F; and sludge-pressurized water reactor environments at 289 and 320 degrees to-fiber nominal concentration ration of 0 to 60. Concentration C. Preliminary information was obtair,ed on the effect of temper-measurements obtained dunng the first flushing cycle were ature, load ratio, stress intensity K, and dissolved-oxygen and -

used to estimate the filtration efficiencies of the debris beds.

hydrogen concentrations of the water on EAC. Specimens of For test conditions where the beds are fairly uniform, the head Type 316NG and sensitized Type 304 stainless steel (SS) were loss data were predictable within an acceptable accuracy range included in several of the experiments to assess the behavior of I

by the semi theoretical model. The model was equally applica-these materials and Alloy 600 under the same water chemistry l

ble for both pure fiber beds and the mixed beds. Typicalry the and loading conditions. The experimental data are compared l

model over-predicted the head losses for very thin beds and for with predictions from an Argonne National Laboratory (ANL) thin beds at high sludge-to-fiber mass ratios. This is attnbutable model for crack growth rates (CGRs) of SSs in water and the to the non-uniformity of such debris beds. In this range the cor.

ASME Code Section XI correlation for CGRs in air at the relation can be interpreted to provide upper bound estimates of K(max) and load-ratio values in the various tests. That data for j

head loss.

all of the matenals were bounded by ANL model p'edictions and the ASME Section XI " air line."

l 1

l l

24 Main Citations and Abstracts l

NUREG/CR-6384 V01: LITERATURE REVIEW OF ENVIRON-show that for excavations subjected to repetitive seismic mo-MENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC tions, accumulation of shear displacement along the joints is the CABLES. Summary Of Past Work. SUBUDHI,M. Brookhaven Na-primary mode of deformation for the rock mass. However, the tional Laboratory. April 1996. 300pp. 9605130112. BNL-currently available seismic design procedure for underground NUREG-52480. 88219:001.

excavations is based on the probable peak particle motion con-This report summarizes the findings from a review of pub-cept and does not explicitly take into account of either the time lished documents daaling with research on the environmental history of individual events or the effects of repetitive seismic l

quahfication of safety-related electric cables used in nuclear events. An adequate seismic design methodology is desirable.

power plants. Simulations of accelerated aging and accident The results of this research project will be used to: conduct pre.

conditions are important considerations in qualifying the cables.

licensing reviews, provide guidance to DOE, develop CDMs, Significant research in these two areas has been performed in support IPA, and provide basis for developing seismic design the United States and abroad. The results from studies in methodology.

France, Germany, and Japan are described in this report. In recent years, the development of methods to monitor the condi-NUREG/CR4392: THE EFFECTS OF AGING ON COMPRES-tion of cables has received special attention. Tests involving SIVE STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE chemical and physical examination of cable's insulation and FORMS. MCCONNELL J.W.; NEILSON,R.M. Idaho National En-

}acket materials, and electrical measurements of the insulation gineering Laboratory. June 1996. 47pp. 9607090141. INEL-95/

properties of cables are discussed. Although there have been 0506. 88956.233.

significant advances in many areas, there is no single method The Field Lysimeter investigations: Low-Level Waste Data which can provide the necessary information about the condi-Base Development Program, funded by the U.S. Nuclear Regu-tion of a cable currently in service. However, it is possible that latory Commission (NRC), is (a) studying the degradation effects further research may identsfy a combination of several methods in organic ion-exchange resins caused by radiation, (b) examin-that can adequately characterize the cable's condition.

ing the adequacy of test procedures recommended in the NUREG/CR4364 V02: LITERATURE REVIEW OF ENVIRON.

Branch Technical Position on Waste Form to meet the require.

MENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC ments of,10 CFR 61 using solidified ion-exchange resins, (c) ot>

CABLES. Literature Analysis And Appendices. LOFARO,R.;

taming pedsmance informaton on sohd6ed ion-exchange BOWERMAN,B.; CARBONARO,J.; et al. Brookhaven National resins in a disposal environment, and (d) determining the condi-Laboratory. April 1996. 146pp. 9605130115. BNL-NUREG.

tion of liners used to dispose ion exchange resins. Compressive 52480. 88265:001.

tests were performed periodically over a 12-year period as part In support of the U.S. NRC Environmental Qualification (EO) of the Technical Position testing. Results of that compressive Research Program, a literature review was performed to identify testing are presented and discussed. During the study, both past relevant work that could be used to help fully or partially pwtland type 1-11 cement and Dow vinyt ester-styrene waste resolve issues of interest related to the qualification of low-volt.

form samples were tested. This testing was designed to exam-age electric cable. A summary of the literature reviewed is doc.

ine the effects of aging caused by self-irradiation on the com-umented in Volume I of this report. In this, Volume 2 of the pressive strength of the waste forms. Also presented is a brief report, dossiers are presented which document the issues se.

summary of the results of waste form characterization, which lected for investigation in this program, along with recommenda.

had been conducted in 1986, using tests recommended in the tions for future work to resolve the issues, when necessary. The Technical Position on Waste Form. The aging test results are dossiers are based on an analysis of the literature reviewed, as compared to the results of those eariier tests.

well as expert opinions. This analysis includes a cntical eview NUREG/CR-6396: EXAMPLES. CLARIFICATIONS, AND GUID-of the information available from past and ongoing work in thir-ANCE ON PREPARING REQUESTS FOR RELIEF FROM teen specific areas related to EO. The analysis for each area PUMP AND VALVE INSERVICE TESTING REQUIREMENTS RANSOM,C.B.; HARTLEY,R.S. Idaho National Engineering Lat$

con particu a tv. e its t ra presented, along with recommendations for future work. The oratory. February 1996.186pp. 9603010300. INEL-95/0512.

0 M

analysis mented in the form of a dossier for each of the S report, the Idaho National Engineering Laboratory re-viewers discuss issues related to requests for relief from the NUREG/CR-6388: SEISMIC RESPONSE OF ROCK JOINTS AND American Society of Mechanical Engineers code requirements JOINTED ROCK MASS.

GHOSH,A.;

HSIUNG S.M.;

for inservice testing (IST) of safety-related pumps and valves at CHOWDHURY,A.H. Center for Nuclear Waste Regulatory Analy-commercial nuclear power p! ants. This report compiles informa-ses. June 1996. 120pp. 9608060191. CNWRA 95-013.

tion and examples that may be useful to licensees in developing 89266:191.

relief requests submitted to U.S. Nuclear Regulatory Commis-Two key technical uncertainties (KTU) that can potentially sion (NRC) for their consideration and provides insights and rec-pose a high risk of noncompliance wrth the performance objec-ommendations on related IST lasues. The report also gives spe-tives of 10 CFR Part 60 are the prediction of (i) thermal-me-cific guidance on relief requests acceptable and not acceptable chanical effects on stability of emplacement drifts and the engi-to the NRC and advises licensees in the use of this information neered barrier system (EBS), and (ii) thermal-mechanical-hydro-for application at their facilities.

logical effects on the host rock surrounding the EBS. This final report summanzes the research activities concerned with the re-NUREG/CR-6401: FAULTING IN THE YUCCA MOUNTAIN petitive seismic load aspect of both these KTUs. This research REGION.Cntical Review And Analyses of Tectonic Data From project has the dual focus of (i) understanding the key param.

The Central Basin And Range. FERRILL.D.A.; STlREWALT,G.L; ewe affecting repository performance under repeated seismic HENDERSON,D.B.; et al. Center for Nuclear Waste Regulatory loading, and (ii) evaluating current capabilities for calculating Analyses. March 1996.108pp. 9606030250. CNWRA 95-017.

such effects. Laioratory experiments on Apache Leap tuff joints 88421:231.

using cyclic pseudostailc and dynamec loads indicate that the Yucca Mountain, Nevada, has been proposed as the potential shear strength in tre reverse direction of shearing is less than site for a high-level waste (HLW) repository. The tectonic setting that in the forward direction. But the reverse shear strength pre-of Yucca Mountain presents several potential hazarJs for a pro-dcted by UDEC (versons 1.82 and 1.83) is found to be incork posed repository, such as potential for earthquak. Mismicity, sistent with these findings. Thus, a new joint model is desirable.

fault disruption, basaltic volcanism magma channeling along Field expenments at Lucky Fnday Mine, scale-model experi-pre-existing faults, and faults and fractures that may serve as ments conducted at CNWRA, and information in the literature barriers or conduits for ground water flow. Characterization of

Main Citations and Abstracts 25 geologic structures and tectonic processes will be necessary to NUREG/CR-6411: A GEOSTATISTICAL METHODOLOGY TO assess compliance with regulatory requirements for the pro-ASSESS THE ACCURACY OF UNSATURATED FLOW posed HLW repository. In this repo t, we specifically investigate MODELS. SMOOT,J.L; WILLIAMS,R.E. Battelle Memorial Insti-fault slip, seismicity, contemporary stain, and fault-slip potential tute, Pacife Northwest Laboratory. April 1996. 70pp.

in the Yucca Mountain region with regard to Key Technical Un-9607090193. PNL-10866. 88958:200.

certainties outlined in the License Application Review Plan (Sec-The Pacific Northwest National Laboratory (PNNL) has devel-tions 3.2.1.5 through 3.2.1.9 and 3.2.2.8). These investigations oped a Hydrologic Evaluation Methodology (HEM) to assist the center on (i) altemative methods of determining the slip history U.S. Nuclear Regulatory Commission in evaluating the potential of the Bare Mountain Fault, (ii) cluster analysis of historic earth-that infiltrating meteoric water will produce leachate at commer-quakes, (iii) crustal strain determinations from Global Positioning cial low-level radioactive waste disposal sites. Two key issues System measurements, and (iv) three-dimensional slip-tendency are raised in the HEM: 1) evaluation of mathematical models analysis. The goal of this work is to assess uncertainties associ-that predict facility performance, and 2) estimation of the uncer-ated with neotectonic data sets critical to the Nuclear Regula-tainty associated with these mathematical model predictions.

tory Commission and the Center for Nuclear Waste Regulatory The technical objective of this research is to adapt geostatisti-Analyses' ability to provide prelicensing guidance and perform cal tools commonly used for model parameter estimation to the license application review with respect to the proposed HLW re-problem of estimating the spatial distnbution of the dependent pository at Yucca Mountain-vanable to be calculated by the model. To fulfill this objective, a database describing the spatiotemporaf movement of water in-NUREG/CR 6406: ENVIRONMENTAL TESTING OF AN EXPERI.

jected into unsaturated sediments at the Hanford Site in Wash-MENTAL DIGITAL SAFETY CHANNEL KORSAH,K.;

WILSON,T.L; et al. Oak Ridge Nat#onal Laboratory, ington State was used to develop a new method for evaluating mathematical model predictions. Measured water content data TANAKA,T.J. Sandia National Laboratories. September 1996.

were interpolated geostatisically to a 16 x 16 x 36 grid at sever-146pp. 9612030282. ORNUTM-13122. 91000:001, al time intervals. Then a mathematical model was used to pre-This document presents the results of environmental stress tests performed on an experimental digital safety channel dict water content at the same grid locations at the selected (EDSC) assembled at the Oak Ridge National Laboratory times. Node-by-node comparison of the mathematical model (ORNL) as part of the NRC-sponsored "Quahfication of Ad_

predictions with the geostatistically interpolated values was con-vanced Instrumentation and Controls (l&C) System" program.

ducted. The method facilitates a complete accounting and cate-The objective of this study is to investigate failure modes and gonzation of model error at every node. The comparison sug-vulnerabihties of microprocessor-based technologies when sub.

gests that model resuits generally are within measurement error. The worst model error occurs in # lenses and is in jected to environmental stressors. The study contributes to the technical basis for environmental qualification of safety-related excess of measurement error, digital 18C systems for nuclear power plants. The EDSC em-NUREG/CR-6413: ANALYSIS OF THE IRRADIATION DATA FOR ploys technologies and digital subsystems representative of A302B AND A533B CORRELATION MONITOR MATERIALS.

those proposed for use in advanced light-water reactors WANG J.A. Oak Ridge National Laboratory. April 1996. 318pp.

(ALWRs) or for retrofits in existing plants. It was subjected to 9605220308. ORNL/TM 13133. 88320:029.

selected stressors that are a potential risk to digital equipment The results of Charpy V-notch impact tests for A3028 and in a mild environment. The selected stressors; were electromag-A5338-1 Correlation Monitor Materials (CMM) listed in the sur-netic and radio-frequency interference (EMI/RFI), temperature, vetilance power reactor data base (PR-EDB) and material test humidity, and smoke exposure. The stressors were applied over reactor data base (TR-EDB) are analyzed. The shift of the tran-ranges that were considerably higher than what the channel is sition temperature at 30 ft-lb (T(30)) is considered as the pri-likely to experience in a normal nuclear power plant enviror).

mary measure of radiation embrittlement in this report. The hy-rnent. Stressor-induced errors were logged so that failure modes that are characteristic of the technologies employed perbolic tangent fitting rreodel and uncertainty of the fitting pa-rameters for Charpy impact tests are presented in this report.

could be identified.

NUREQ/CR4407: CLASSIFICATION OF TRANSPORTATION at 30 ft-lb MT(30)) generally fo'llow the predictions provided by PACKAGING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS ACCORDING TO IMPORTANCE TO SAFETY apsule temperatures is a likely explanation for large deviations MCCONNELL,J.W.; AYERS.A.L; TYACKE,M.J. Idaho Nationaj fr m R.G.1.99 predictions. Deviations from the R.G.1.99 pre.

l Engineering Laboratory. February 1996. 59pp. 9603190098' dictions are correlated to similar deviations for the accompany-l INEL-95/0551. 87522:099.

ing materials an the same capsules, but large random fluctua-This report provides a graded approach for classification of ns n

se @an am WMnah Sgnskant sw6.nts used in transportation packaging and dry spent fuel scatter is noted in the surveillance data, some of which may be storage systems. This approach provides a method for identify-a t

s Wn one sWne sd to anom or in-ing the classification of components according to importance to herent in Charpy V-notch testing. In general, the embnttlement safety within transportation packagings and dry spent fuel stor-behavior of both the A302B and A533B-1 plate matenals is age systems. Record retention requirements are discussed to si a e s Mece 6 a hence<a2 eHect in the M identify the documentation necessary to validate that the indi-data irradiated in test reactors; thus its implication on power re-vidual components tvere fabricated in accordance with their as-actor surveillance programs deserves special attention.

signed classification. A review of the existing regulations per-l

)

taining to transportation packagings and dry storage systems NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADA.

was performed to identify current requirements. The general TION ANALYSIS. VESELY,W.E. Science Applications interna-types of transportation packagings and dry storage systems tional Corp.

(formerly Science Applications, Inc.).

were identified. Discussions were held with suppliers and fabri-SAMANTA,P.K. Brookhaven National Laboratory. February cators of packagings and storage systems to determine current 1996.47pp.9603260303. BNL-NUREG 52488. 87624:242.

practices. The methodology used in this report is based on Reg-Reliability degradation analysis is the analysis of the occur.

ulatory Guide 7.10. Estabushing Quality Assurance Programs for rences of degradations and the times of maintenance to deter-i l

Packaging Used in the Transport of Radioactive Matenal. This mine their reliability and nsk implications. A program is present-report also includes a list of genenc components for each cf the ed for applying rehability degradation analyses to maintenance general types of transportation packagings and spent fuel stor-data collected at nuclear power plants. As a specific part of the age systems. The safety importance of each component is dis-program, time trending of maintenance data is illustrated. Main-cussed, and a classification category is assigned.

tenance data on residual heat removal (RHR) pumps and serv-l

26 Main Citations cnd Abstracts ice water (SW) pumps at selected boiling water reactor (BWR) and modeling assumptions. The important parameters in each plants are evaluated to show how trends in maintenance data, of these categories are discussed in the report. An additional which generally do not involve failures, can be used to under-objective of this study was to identfy BWR and pressurtzed stand effectiveness of maintenance. These trends also are water reactor (PWR) transients in which there is significant translated to specific impacts on pump unavailability and on energy deposition. This determined which BWR transients were core-damage frequency (assuming that the trends in failure rate to be calculated as part of this study and which might be calcu-are the same as those observed for degradation rate). The lated if analysis were to be done for PWRs.

second application shows the use of reliability degradation anal-ysis to quantitatively evaluate the effect of maintenance, i.e., the NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER quantitative change in component unavailability when no main PLANT REINFORCED CONCRETE STRUCTURES. NAUS.D.J.;

tenance is performed. Assessment of these impacts are impor.

OLAND C.B.

Oak Ridge National Laboratory, tant since they measure the reliability and nsk impacts of main.

ELLINGWOOD B.R. Johns Hopkins Univ., Baltimore, MD. March tenance and can be fed back to the maintenance p/ogram to 1996. M0pp.9604230378. ORNL/TM-13148. 87974:001.

i improve its effectiveness.

The Structural Aging Program provides the U.S. Nuclear Reg-NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON acceptance criteria for continued service assessments of i

BREATHING-ZONE AND AREA AIR SAMPLES-safety-related nuclear power plant concrete structures. The pro-METZGER,R.L; JESSOP.B.H.; MCDOWELL.B.L Radiation gram was organized under four task areas Program Manage.

Safety Engineering, Inc. February 1996. 55pp. 9603180378.

ment, Materials Property Data Base, Structural Component As-87500:248.

l sessment/ Repair Technology, and Quantitative Methodology for l

A solubility testing method for several common actinides has Continued Service Determinations. Under these tasks, over 90 l

been developed with suffictent sensitivity to allow profiles to be papers and reports were prepared addressing pertinent aspects determined from routine breathing zone and area air samples in associated with aging management of nuclear power plant rein-the workplace. Air samples are covered with a clean filter to forced concrete structures. Contained in this report is a summa-form a filter sample-filter sandwich which is immersed in an ex*

ry of program results in the form of information related to lon-l tr'. cellular lung serum simulant solution. The sample is moved to gevity of nuclear power plant reinforced concrete structures, a I

a fresh beaker of the lung fluid simulant each day for one week, data base presenting data and information on the time variation cnd then weekly until the end of the 28-day test period. The of concrete materials under the influence of environmental soak solutions are wet ashed with nitric acid and hydrogen per-stressors and aging factors, in-service inspection and condition oxide to destroy the organic components of the lung simulant asset.sments techniques, repair materials and methods, evalua-prior to the extraction of the nJclides of interest directly into an tion of nuclear power plant reinforced concrete structures and a Extractive scintillator for subsequent counting on a photon-elec-reliability-based methodology for current and future condition tron rejecting alpha liquid scintillation (PEARLS) spectrometer, assessments. Recommendations for future activities are also Solvent extraction methods utiltzing the extractive scintillators provided.

have been developed for the isotopes of uranium, plutonium, and curium. The procedures normally produce an isotopic re-NUREG/CR-6425: IMPACT OF STRUCTURAL AGING ON SEIS-covery greater than 95% and have been used to develop solu-MIC RISK ASSESSMENT OF REINFORCED CONCRETE bility profiles for air samples with 40 pCi or less of U308. Pro-STRUCTURES IN NUCLEAR POWER PLANTS.

l files developed for U308 samples show good agreement with in ELLINGWOOD,B.R.; SONG,J. Johns Hopkins Univ., Baltimore, l

vitro and in vivo tests performed by other investigators on sam-MD.

Oak Ridge National Laboratory. March 1996. 81pp.

pies from the same uranium mills.

9604230399. ORNL/TM 13149. 87971:225.

l NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR The Structural Aging Program is addressing the potential for COMMERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN RE-degradation of concrete structural components and systems in ACTOR APPLICATIONS. PRECKSHOT,G.G.; SCOTT,J.A. Law-nuclear power plants over time due to aging and aggressive en-rence Livermore National Laboratory. March 1996. 107pp.

vironmental stressors. Structures are passive under normal op-9604150345. UCRL-ID-122526. 87867:179.

erating conditions but play a key role in mitigating design-basis This paper proposes a process for acceptance of commercial events, particularly those arising from external challenges such l

off-the-shelf- (COTS) software products for use in reactor sys, as earthquakes, extreme winds, fire, and floods. Structures are tems important to safety. An initial set of four criteria estab-plant-specific and unique, often are difficult to inspect, and are l

lishes COTS software product identification and its safety cate.

virtually impossible to replace. The importance of structural fail-l gory. Based on safety category, three sets of additional cnteria, ures in accident mitigation is amplified because such failures graded in rigor, are applied to approve (or disapprove) the prod-may lead to common-cause failures of other components. Struc-uct. These critoria fall roughly into three areas: product assur-tural condition assessment and service life prediction must i

ance, verification of safety function and safety impact, and ex.

focus on a few critical components and systems within the amination of usage experience of the COTS product in circum.

plant. Components and systems that are dominant contributors I

stances similar to the proposed application. A report addressing to risk and that require particular attention can be identified I

the testing of existing software is included as an appendix.

through the mathematical formalism of a probabilistic risk as-l sessment, or PRA. To illustrate, the role of structural degrada-NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH tion due to aging on plant risk is examined through the frame-BURNUP CORES. DIAMOND,D.J.; NEYMOTIN,L; KOHUT,P.

work of a Level 1 seismic PRA of a nuclear power plant. Plausi-Brookhaven National Laboratory. February 1996. 78pp.

ble mechanisms of structural degradation are found to increase 9603260310. BNL-NUREG-52491. 87640:242.

the core damage probability by approximately a factor of two.

A study has been undertaken to determine the fuel enthalpy during a rod drop accident (RDA) and dunng two thermal-hy.

NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRAC-draulic transients in a boiling water reactor (BWR). The objec-TURE TOUGHNESS AND CHARPY-lMPACT STRENGTH OF tive was to understand the consequences to high bumup fuel STAINLESS STEEL PIPE WELDS.

GAVENDA.D.J.;

c.nd the sources of uncertainty in the RDA calculations. The MICHAUD,W.F.; GALVIN,T.M.; et al. Argonne National Labora-cnalysis was done with RAMONA-48, a computer code that tory. May 1998. 86pp. 9605310163. ANL-95/47. 88394:253.

models the neutron kinetics throughout the core along with the The degradation of fracture toughness tensile, and Charpy-thermal-hydraulics in the core, vessel, and steamline. The re-impact properties of Type 308 stainless steel (SS) pipe welds suits showed that the calculated maximum fuel enthalpy in high due to thermal aging has been characterized at room tempera-burnup fuel will be affected by core design, initial conditions, ture and 290 degrees C. Thermal aging of SS welds results in

l l

Main Citations and Abstracts 27 moderate decreases in Charpy-impact strength and fracture over to recirculation should be required to install an automatic

(

toughness. For the various welds in this study, upper-shelf system. Risk estimates are obtained by reevaluating the contri-l energy decreated by 50-80 J/cm(2). The decrease in fracture butions to core damage frequencies (CDFs) associated with fail-toughness J R curve or J(IC) is relatively small. Thermal aging ures of manual and semiautomatic switchover at a representa-l had little or no effect on the tensile strength of the welds. Frac-tive PWR. This study considers each separate instruction of the ture properties of SS welds are controlled by the distribution corresponding emergency operating procedures (EOPs), the and morphology of second-phase particles. Failure occurs by mechanism for each control, and the relationship of each con-the formation and growth of m!crovoids near hard inclusions.

trol to its neighbors. Important contributions to CDF include Such processes are relatively insensitive to thermal aging. The human errors that result in completely coupled failure of both j

l ferrite phase has little or no effect on the fracture properties of trains and failure to enter the required EOP. This detailed study l

the welds. Differences in fracture resistance of the welds arise finds that changeover to a semiautomatic system is not justified from differences in the density and size of inclusions. The me-on the basis of cost-benefit analysis: going from a manual to a chanical-property data from the present study are consistent semiautomatic system reduces the CDF by 1.7x10-5 per reac-with results from other investigations. The existing data have tor year, but the probability that the net cost associated with the been used to establish minimum expected fracture properties modification being less than $1,000 per person-rem is about for SS welds.

20% without license renewal. Scoping analyses, using optimistic NUREG/CR-6429: THE ROLE OF ORGANIC COMPLEXANTS assumptions, were performed for a changeover to a semiauto-AND MICROPARTICULATES IN THE FACIUTATED TRANS-matic system with automatic actuation and to a fully automatic PORT OF RADIONUCLIDES. SCHILK.A.J.; ROBERTSON,D.E.;

system; in these cases the probability of having a net cost ABEL,K.H.; et al. Batteile Memorial Institute, Pacific Northwest being less than $1400/persm-rem is about 50% without li-j Laboratory. December 1996.109pp. 9701130193. PNL-10897.

conse renewal and over 95% with license renewal.

91397:238.

NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECO-This progress report describes the results of ongoing radio-NOMIC INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR logical and geochemicalinvestigations of the mechanisms of ra.

POWER PLANT OPERATIONS AND MAINTENANCE COSTS.

dionuclide transport in groundwater at two low-level waste

'(LLW) disposal sites within the waste management area of the KAVANAUGH,D.C.; MONROE,W.K. Battelle Memorial institute, Chalk River Laboratories (CRL), Ontario, Canada. These Pacific Northwest Laboratory. WOOD,R.S. Office of Nuclear Re-actor Regulation (Post 941001). February 1996. 47pp.

sites,the Chemical Pit liquid disposal facility and the Waste Man-9603190137. PNL-10934. 87510:172.

agement Area C solid LLW disposal site, have provided valua-ble 30- to 40-year old field locations for charactertzing the mi-This study presents an analysis of the determinants of non-gration of radionuclides and evaluating a number of recent site fuel Operations and Maintenance expenses (O&M) for the performance objectives for LLW disposal facilities. These stud-period 1986 to 1990. Since tt e determinants of O&M outlays les have focused on identifying the physico-chemical species of are likely to be many and varied, the potential linkages, both mobile radionuclides in groundwater at these field locations and direct and indirect, to plant safety can be substantial. This study characterizing their behavior in the sut> surface environment.

develops a framework to analyze the elements that affect these Field and laboratory studies have shown that the mobile radio-expenditures to provide a basis for understanding these link.

nuclide species, including (55)Fe, (60)Co, (106)Ru, (125)Sb, and ages.

(239,240)Pu, are generally anionic in nature, being sequestered by naturally occurring and/or man-made complexing materials, NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC including fulvic and humic substances. lon chromatographic and AND RADIO-FREQUENCY INTERFERENCE LEVELS IN NU-ultrafiltration separations of coctaminated groundwater have CLEAR POWER PLANTS. KERCEL,S.W.; MOORE,M.R.;

identified a number of individval mobile chemical species of BLAKEMAN E.D.; et al. Oak Ridge National Laboratory. Novem-(60)Co and (106)Ru, as wer as organo-metallic macromole-ber 1996.111pp. 9701060156. ORNL/TM-13171. 01280:149.

I cules, indicating the presence of a complex mixture of these so-This document reports the results of a survey of ambient questered radionuclides being transported in the groundwater.

electromagnetic conditions in representative nuclear power plants. The U.S. Nuclear Rogulatory Commission (NRC) Office NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.

of Nuclear Regulatory Research engaged the Oak Ridge Na-LAWRENCE,J.D. Lawrence Livermore National Laboratory. Feb-tional Laboratory (ORNL) to perform these rneasurements to l

ruary 1996. 91pp. 9602290270. UCRL-ID-122514. 87296:001.

characterize the electromagnetic interference (EMI) and radio-Techniques for analyzing the safety and reliability of analog-kequency intorference (RFI) levels that can be expected in nu-based electronic protection systems that serve to mitigate ha2-clear poww plant ehmts. Ms say is me &st of Rs ards in process control systems have been developed over kind, being based on long-term unattended observations. The many years, and are reasonably well understood. An example is data presented in this report were measured at eight different the protection system in a nuclear power plant. The extension nuclear units and required 14 months to collect. A representa-of these techniques to systems which include digital computers tive sampling of power plant conditions (reactor type, operating is not well developed, and there is little consensus among soft-mode, sne locahon) mmitored ww extended obsewabon pe6 ware engineering experts and safety experts on how to analyze ods (up to 5 weeks) were selected to moro completely deter-such systems. One possible technique is to extend hazard anal-nune me charactensuc electromagneSc envirmet for Nclear ysis to include digital computer-based systems. Software is fre-power plants. Radiated electric fields were measured over the quently overlooked during system hazard analyses, but this is frequency range of 5 MHz to 8 GHz Radiated magnetic fields unacceptable when the software is in control of a potentially and ceducted EM events wwe measured ww me frequecy hazardous operation. In such cases, hazard analysis should be extended to fully cover the software. A method for performing range of 305 Hz to 5 MHz. Highest strength observations of the electromagnetic ambient environment across all measurement software hazard analysis is proposed in this paper.

conditions at each site provide frequency dependent profiles for NUREQ/CR-6432: ESTIMATED NET VALUE AND UNCERTAIN-EMI/RFI levels in nuclear power plants.

TY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

WALSH B.; BRIDEAU,J.; COMES.L; et al. Science & Engineer-IJUREG/CR-6438: THE EFFECT OF CYCLIC AND DYNAMIC ing Associates, Inc. February 1996. 125pp. 9605130079.

LOADS ON CARBON STEEL PIPE. RUDLAND,D.L.;

SEASF-DR 94-001. 88220:001, SCOTT,P.M.; WILKOWSKI,G.M. Battelle Memorial Institute, Co-A central question for resolution of GSI-24 is whether or not lumbus Laboratories. February 1996.102pp. 9603100145. BMI-PWRs that currently rely on a manual system for ECCS switch-2188. 87511:187.

28 M:In Cit:tions cnd Abstracts This report presents the results of four if.2-mm (6-inch) diam-In response to interest shown by the Nuclear Energy Agency eter, unpressurized, circumferential through-wall-cracked, dy.

(NEA), Principal Working Group i (PWG-1) of the Committee on namic pipe experiments fabricated from STS410 carbon steel the Safety of Nuclear installations (CSNI) conducted a generic pipe manufactured in Japan. For three of these experiments, study on the effects of aging of active components in nuclear the through-wall crack was in the base metal. The displacement power plants. (This focus on active components is consistent histories applied to these experiments were a quasi-static mon-with PWG 1's mandate; passive components are primarily within otonic, dynamic monotonic, and dynamic, cyclic (R = -1) histo-the mandate of PWG-3.) Representatives from France, Sweden, ry. The through-wall crack for the third expenment was in a Finland, Japan, the United States, and the United Kingdom par-tungsten-inert-gas weld, fabricated in Japan, joining two lengths ticipated in the study by submitting reports documentng aging of STS410 pipe. The displacement history for this experiment studies performed in their countnes. This report consists of was the same history applied to the dynamic, cyclic base metal summaries of those reports, along with a comparison of the var-experiment. The test temperature for each experiment was 300 lous statistical analysis methods used in the studies. The stud-C (572 F). The objective of these expenments was to compare les indicate that with some exceptions, active components gen-a Japanese carbon steel pipe material with United States pipe erally do not present a sigriificant aging problem in nuclear material, to ascertain whether this Japanese steel was as sensi-power plants. Design enteria and effectrve preventative mainte-tive to dynamic and cyclic effects as United States carbon steel nance programs, including timely replacement of components, pipe, in support of these pipe experiments, quasi-static and dy-are effective in mitigating potential aging problems. However, namic, tensile and fracture toughness tests were conducted. An aging studies (such as qualitative and statistical analyses of fail-analysis effort was performed that involved comparing experi-ure modes and maintenance data) are an important part of ef.

mental crack initiation and maximum moments with predictions forts to identify and solve potential aging problems. Solving based on available fracture prediction models, and calculating these problems typically includes such strategies as replacing J-R curves for the pipe experiments using the "-factor method.

Suspect components with improved components, and imple-NUREG/CR-6439: DESIGN OF THE IPIRG-2 SIMULATED SEIS-menting improved maintenance programs.

MIC FORCING FUNCTION.

OLSON,R.;

SCOTT,P.M.;

NUREG/CR-6443: DETERMINISTIC AND PROBABILISTIC EVAL-WILKOWSKI,G.M. Battelle Memorial Institute, Columbus Labora-UATIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAM.

tories. February 1996. 86pp. 96022902'78. BMI 2186.

ETERS IN LEAK-BEFORE-BREAK AND IN SERVICE FLAW 87290:092.

EVALUATIONS. GHADIAll,N.; RAHMAN,S.; CHOI,Y.H. Battelle A series of pipe system experiments was conducted in IPIRG-Memorial Institute, Columbus Laboratories. June 1996.134pp.

2 that used a realistic seismic forcing function. Because the 9607120198. BMI-2191. 88980:141.

seismic forcing function was more complex than the single-fre-This report presents new results from deterministic and prob.

quency increasing-amphtude sinusoidal forcing function used in abilistic analyses to evaluate the significance of a number of the IPIRG-1 pipe system experiments, considerable effort went technical aspects that may affect LBB or in-service flaw evalua-into designing the function. This report documents the design tions. In most cases there are both deterministic and probabilis-process for the seismic forcing function used in the IPIRG-2 tic results. The deterministic analyses were conducted inde-pipe system experiments.

pendentty of the probabilistic analyses, which offered the oppor-NUREG/CR-6440: THE EFFECTS OF CYCLIC AND DYNAMIC tunity to validate conclusions from each of these independent LOADING ON THE FRACTURE RESISTANCE OF NUCLEAR studies. The technical aspects evaluated relative to LBB uncer-PIPING STEELS. Technical ReportOctober 1992 April 1996.

tainties were: (1) evaluation of different crack morphology de-RUDLAND,D.L; BRUST,F.W.; WtLKOWSKI,G.M. Battelle Me.

fault values, (2) evaluation of COD dependent and independent morial institute, Columbus Laboratories. December 1996.200pp.

crack morphology models for tight crack leak-rate analyses, (3) 9701160171, BMI-2190. 91456:002.

changes of normal operating and N+SSE stress levels on con-This report presents the results of the material property evag.

ditional failure probability, (4) dynamic and cyclic loads history uation efforts performed wrthin Task 3 of the iPIRG-2 Program, effects on load-carrying capacity of through-wall-cracked pipe, Several related investigations were conducted. (1) Quasi-static, (5) evaluation of the effect of off-centered cracks, (6) evaluation cyclic-load compact tension specimen experiments were con-of the effect of restraint of pressure induced bending, and (7) ducted using parameters similar to those used in IPIRG-1 ex.

evaluation of the effect of residual stresses on leak rate analy-periments on 6-inch nominal diameter through-wall-cracked ses. Uncertainty analyses conducted relative to in-service flaw pipes. These experiments were conducted on a TP304 base evaluations were: (1) dynamic and cyclic load history effects on metal, an A106 Grade B base metal, and their respective sub.

load-carrying capacity of surface-cracked pipe,'and (2) effect of merged-arc welds. The results showed that when using a con.

uncertainty in UT flaw sizing. The relative ranking of importance stant cyclic displacement increment, the compact tension ex.

is given for the significance of each technical aspect investigat-periments could predict the through-wall-cracked pipe crack ini.

ed.

tiation toughness, but a reproduce the pipe cychdifferent control procedure is needed to NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFEREN-e crack growth in the compact tension TIALLY SURFACE-CRACKED ELBOWS.

KILINSKI,T.;

tests. (2) Analyses conducted showed that for 6-inch diameter MOHAN.R.; RUDLAND,D.L: et al. Battelle Memorial Institute, pipe, the quasi-static, monotonic J-R curve can be used in Columbus Laboratories. December 1996.183pp. 9701160168.

making cyclic pipe moment predictions; however, sensitivity BMI-2192. 91457:001.

analyses suggest that the maximum moments decrease slightly This report presents the results from Task 2 of the Second from cyclic toughness degradation as the pipe diameter in-International Piping Integnty Research Group (IPIRG-2) pro-creases. (3) Dynamic stress-strain and compact tension tests gram. The focus of the Task 2 work was directed towards fur-were conducted to expand on the existing dynamic database.

thering the understanding of the fracture behavior of long-radius Results from dynamic moment predictions suggest that the dy-elbows. This was accomplished through a combined analytical namic compact tension J-R and the quasi-static stress-strain and experimental program. J-estimation schemes were devel-curves are the appropriate matenal properties to use in makmg oped for both axial and circumferential surface cracks in dynamic pipe moment predictions.

elbows. Large-scale, quasi-static and dynamic, pipe-system, NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CER-elbow fracture experiments under combined pressure and bend-TAIN SAFETY-RELATED COMPONENTS. MAGLEBY,H.L.;

ing loads were performed on elbows containing an internal sur-ATWOOD,C.L; MACDONALD,P.E.; et al. Idaho National Engi-face crack at the extrados. In conjunction with the elbow experi-neering Laboratory. January 1996. 74pp. 9603180353. INEL-95/

ments, material property data were developed for the A106-90 0654. 87511:281, carbon steel and WP304L stainless steel elbow materials inves-

M;in Citations cnd Abstracts 29 This report describes development of a significant new tigated. A comparison of the expenmental data with the maxi.

rnethod for monitoring radioactive surface contamination. A floor mum stress predictions using existing straight pipe fracture pre-rnonitor prototype has been designed which uses position sensi-diction analysis methods, and elbow fracture prediction methods developed in this program was performed. This analysis was di-tive proportional counter based radiation detectors. The system rected at addressing the concerns regarding the validity of using includes a novel operator interface consisting of an enhanced analysis predictions developed for straight pipe to predict the reality display providing the operator with 3 dimensional con-tracture stresses of cracked elbows. Finally, a simplified fitting tours of contamination and background subtracted stereo flaw acceptance criteria incorporating ASME B(2) stress indices

" clicks". The pruess software saves electronic files of survey and straight pipe, circumferential-crack analysis was developed.

data at very high rates along with time stamped video recording and provides completely documented surveys in a visualization NUREG/CR-6445: DEVELOPMENT OF A J-ESTIMATION oriented data management system. The data management SCHEME FOR INTERNAL CIRCUMFERENTIAL AND AXIAL system allows simple re-assembly of strips of data that are SURFACE CRACKS IN ELBOWS. MOHAN,R.; BRUST,F.W.;

taken with a linear PSPC and allows visualization and treatment GHADIAll,N.; et al. Battelle Memortal institute, Columbus Lab-of the data using algorithms developed for processing images oratories. June 1996. 68pp. 9607090154. BMI-2193. 88957:252.

from earth resource satellites. This report includes a brief histo-This report summarizes efforts to develop elastic and elastic-ry of the development path for the floor monitor, a discussion of i

plastic fracture mechanics analyses for internal surface cracks posrtion sensitive proportional cot nter technology, and details in elbows. The analyses involved development of a GE/EPRI ng N pm Wars post procenor and hardwart type J-estimation scheme from a matrix of finite element analy-The last chapter discusses the field tests that were conducted ses. The following parameters were covered; 90-degree long-at five sites and an application of the data management system radius elbows, various R(m)/t ratios, and combined pressure g

and in-plane bending. For the combined pressure and bending analyses, the hoop stress was fixed to correspond to an aver-NUREG/CR-6455: DATA ANALYSIS FOR STEAM GENERATOR age S(m) value for typical U.S. nuclear piping materials. Further TUBING SAMPLES. DODD.C.V. Oak Ridge National Laboratory.

factors included in the analyses were vanous strain-hardening July 1996. 64PP. 9608210230. ORNL/TM-13206. 89423:282.

exponents and a/t values; however, the circumferential cracked The objective of the improved Eddy-Current ISI for Steam elbow was limited to one crack length, and the axial cracked Generators program is to upgrade and validate eddy-current in-elbow was limited to one crack length on the elbow flank.

These analyses were implemented into a computer code called spectons, including probes, instrumentation, and data process-IP2 ELBOW. The results from the computer code calculations ing techniques for inservice inspection of new, used, and re-showed that the moment values at crack initiation were 1.5 to 2 paired steam generator tubes; to improve defect detection, clas-sification and charactertration as affected by diameter and times lower for the axially cracked elbow than for the circumfer.

entially cracked elbow. The moment values for pressurized thickness variations, denting, probe wobble, tube sheet, tube straight pipe were somewhat lower than for circumferentially supports, copper and sludge deposits, even when defect types cracked elbows for R(m)/t of 10, but were 1.5 greater for R(m)/

and other variables occur in combination; to transfer this ad-vanced technology to NRC's mobile NDE laboratory and staff.

i t of 20.

This report provides a desenption of the application of ad-NUREG/CR-6448 V01: EVALUATION OF NATIONAL SEISMO-vanced eddy-current neural r.etwork analysis methods for the GRAPH NETWORK DETECTION CAPABILITIES. Annual detection and evaluation of common steam generator tubing Report July 1994 - July 1995.

MCLAUGHLIN,K.L; flaws including axial and circumferential outer-diameter stress-BENNETT.T.J. S-Cubed. March 1996. 58pp. 9604150331. SSS corrosion cracking and intergranular attack. The report de-TR-95-15216. 87867:286.

scribes the training of the neural networks on tubing samples This first annual report presents detection thresholds, detec-with known defects and (ne subsequent evaluation results for tion probabilities, and location error ellipse projections for the unknown samples. Evaluations were done in the presence of ar-United States National Seismic Network (USNSN) with and with*

tifacts. Computer programs are given in the appendix.

out cooperative stations in the eastern United States. Network simulation methods are used with spectral noise levels at sta-NUREG/CR-6457: RAPID ESTIMATE OF SOLID VOLUME IN tions to simulate the processes of excitation, propagation, de-LARGE TUFF CORES USING A GAS PYCNOMETER.

tection, and processing of seismic phases. The USNSN alone GEDDIS,A.M.; GUZMAN,A.G.; BASSETT,R.L Arizona, Univ. of, should be capable of, detecting 4 or more P waves for shallow Tucson, AZ. September 1996. 81pp. 9612030279. 90992:158.

crustal earthquakes in nearty all of the eastern and central A thermally insulated, ngid-volume gas pycrometer system United Staton at the ma3nitude 3.8 level. When cooperative sta-has been developed. The pycnometer chambers have been ma-tions are added, the network should be capable of detecting 4 chined from solid PVC cylinders. Two chambers confine d7 or more P waves from events 0.2 to 0.3 magnitude units lower.

high-pun.ty helium at different pressures. A thick-walled design The planned expm of the USNSN and cooperative stations ensures minsmal heat exchange with the surrounding environ-should improve detection levels by an additional 0.2 to 0.3 mag-ment and a constant volume system, while expansion takes nitudes units in any areas. Location uncertainties for the p ace between the chambers. The internal energy of the gas is USNSU in be significantly improved by addition of real-time assumed constant over the expansion. The ideal gas law is cooperaw stations. Median error ellipses for magnitude 4.5 used to estimate the volume of solid material sealed in one of earthquakes depend strongfy on location, but uncertainties the chambers. Temperature is monitored continuously and in-should be less than 100 km(2) in the central United States and degrade to 200 km(2) or more off-shore and south and north of corporated into the calculation of solid volume. Temperature the intemational boundaries. Close cooperation with the Canadi-variation between measurements is less than 0.1 degrees C.

an National Network should substantially improve detection The data are used to compute grain density for oven-dried thresholds and location uncertainties along the Canadian Apache Leap tuff core samples. The measured volume of solid

border, and the sample bulk volume are used to estimate porosity and bulk density, intrinsic permeability was estimated from the po-NUREG/CR-6450: CHARACTERIZATION OF CONTAMINATION rosity and measured pore surface area and is compared to in.

THROUGH THE USE OF POSITION SENSITIVE DETECTORS situ measurements by the air permeability method. The gas pyc-AND DIGITAL IMAGE PROCESSING.

SHONKA.J.J.;

nometer accommodates large core samples (0.25 m length x DEBORD,D.M4 BENNETT,T.E.; et al. Shonka Research Associ.

0.11 1 m diameter) and can measure solid volume greater than ates, Inc. June 1996. 46pp. 9609200298. 89726:188.

220 cm (3) with less than 1 % error.

30 Main Citations and Abstrccts i

l l

NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR experiments will be used to devel

't ted APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYS-long-term monitoring of the unsatu t one at wa e d TERESIS. RHODES,C.R.; WILSON.LG.; RASMUSSEN,T.C.; et sites. The data will be used to test fie!d scale flow and transport U

o Tucson, AZ. September 1996. 72pp.

models. This report describes the design of the expenment and l

Laboratory methods were use to define matrix hydraulic prop.

l erties for low-permeability Apache Leap Tuff core segments.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LAN-Moisture content /matric potential relationships, including hyster-GUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY esis, and measured hydraulic conduct!vity data were determined SYSTEMS. Final Report. HECHT,H.; HECHT M.; GRAFF S.; et at a constant laboratory temperature of 20 C. To investigate the al. SoHaR, Inc. June 1996. 400pp. 9608060265. 89259:001.

effects of temperature on those relationships, additional reten-Guidelines for the programming and auditing of software writ-l tion data were obtained at 5 C and 45 C. Measured retention ten in high level languages for safety systems are presented.

l data at all temperatures were applied to the van Gonuchten The guidelines are derived from a framework of issues signifi-

)

model RETC which performs curve-fitting and calculation of the cant to software safety which was gathered from relevant l

flow parameter hydraulic conductivity. Although data at 5 C standards and research literature. Language-specific adapta-I proved to be inconclusive, increassng the temperature from 20 tions of these guidelines are provided for the following high to 45 C produced a shift of the moisture characteristic curve level languages: Ada, C/C+ +, Programmable Logic Controller i

toward a higher potential for a given water saturation. Model (PLC) Ladder Logic, international Electrotechnical Commission calculated hydraulic conductivity also increased as temperature (IEC) Standard 11313 Sequential Function Charts, Pascal, and increased, with respect to water saturation. The temperature de-PL/M. Appendices to the report include a tabular summary of pendent change in the viscosity of water proved inadequate to the guidelines and additional information on selected languages.

l explain the increases of hydrauhc conductivity with temperature.

NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF LARGE-SCALE INTERNATIONAL REFERENCE EXPERI-ANALYSIS OF CONTROL SOFTWARE IN ADVANCED REAC-MENTS (FALSIRE II). BASS,0.R.; PUGH.C.E.; KEENEY,J.; et al.

TORS. GUARRO S.; YAU,M.; MOTAMED,M. ASCA, Inc. April 144pp. W 5130069.88226 2.

Oak Ridge National Laboratory. November 1996. 176pp.

9612030256. ORNL/TM-13207. 90999:001.

Software based control systems have gained a pervasive A summary of Phase 11 of the Project for Fracture Analysis of presence in a wWe vanety of applications, including nuclear Large Scale International Reference Experiments (FALSIRE) is power plant control and protection systems which are within the presented. Project FALSIRE was created by the Fracture As-ov6rsight and licensing responsibility of the U.S. Nuclear Regu.

sessment Group (FAG) of the Organization for Economic Coop-latory Commission. While the cost effectiveness and flexibility of eration and Development / Nuclear Energy Agency's (OECD/

software based plant process control is widely recognized, it is NEA's) Committee on the Safety of Nuclear Insta!!ations (CSNI) very difficult to achieve high levels of dependability and safety Principal Working Group No. 3 (PWG-3). The CSNI/ FAG was assurance for the functions performed by process control soft-formed to evaluate fracture prediction capabilities currently used ware, due to the very flexibility and potential complexity of the l

in safety assessments of nuclear components. Members were software itself. The development of tools to model, analyze and from laboratories and research organizations in Western test software design and implementations in the context of the Europe, Japan, and the United States. The CSNI/ FAG Initiated system that the software is designed to control can greatly i

On international project (FALSIRE 1) in 1988 to assess various assist the, task of providing higher levels of assurance than fracture methodologies through interpretive analyses of six those obtainable by software testing alone. This report presents large-scale fracture experiments. These experiments were con-and discusses the development of the Dynamic flowgraph meth-

)

ducted by research organizations in Europe, Japan, and the odology (DFM) and its application in the dependability and as-United States. Followi g the successful completion of FALSIRE surance analysis of software-based control systems. The fea-l in 1992, several participating organizations indicated a desire tures of the methodology and full-scale examples of application

)

to proceed wtth further evaluation of fracture analysis methods to both genene process and nuclear power plant control sys-in a Phase 11 program. FALSIRE 11 included seven reference tems are presented and discussed in detail. The features of a cleavage fracture experiments that focused primarily on behav-workstation software tool developed to assist users in the appip ior of relatrvely shallow cracks in the transition temperature cetion of DFM are also described.

'89"*

NUREG/CR 6466: GROUND MOTION INPUT IN SEISMIC EVAL-NUREG/CR-6462: FIELD TESTING PLAN FOR UNSATURATED UATION STUDIES.lmpacts Of Artficial Time History input On j

2ONE MONITORING AND FIELD STUDIES. YOUNG,M.H.;

In-Structure Demand Sp6ctra. SEWELL.R.T.: WU.S.C. Risk En-1 WlERENGA P.J.; WARRICK,A.W.; et al. Artzona, Univ. of, gineering. Inc. Juty 1996. 315pp. 9608210251. 89421:001.

I Tucson, AZ. October 1996. 63pp. 9611190243, 90824:258.

This report documents research pertaining to conservatism The U.S. Nuclear Regulatory Commission has requested de-and variability in seismic risk estimates. Specifically, it examines velopment of these field testing plans for evaluating subsurface whether or not artificial motions produce unrealisbc evaluation i

monitoring systems for low-level radioactive waste disposal demands, i.e., demands significantly inconsistent with those ex-sites (LLW) and for monitoring at decommissioned facilities des-pected from real earthquakes motions. To study these issues, 1

ignated under the " Site Decommissioning Management Plan" two types of artificial motions are considered; (a) motions with l

(SDMP). The tests are conducted on a 50 m by 50 m plot on smooth response spectra, and (b) motions with realistic vari-the University of Artzona's Maricopa Agricultural Center. Within ations in spectral amplitude across vibration frequency. For both the 50 m by 50 m plot one finds: 1) an instrumented buried types of artficial motion, time histones are generated to match trench,2) monitoring islands similar to those proposed for the target spectral shapes. For comparison, empirical motions rep-Ward Valley, Califomia LLW Facility,3) deep borehole monitor-resentative of those that might result from strong earthquakes ing sites, 4) gaseous transport monitoring, and 5) locations for in the Eastem U.S. are also considered. The study findings sug-testing non-invasive geophysical measurement techniques. The gest that artficial motions resuttng from typical simulation ap-earious subplot areas are instrumented with commercially avail-proaches (aimed at matching a given target spectrum) are gen-able instruments such as neutron probes, time domain reflec-erally adequate and appropriate in representing the peak-re-tometry probes, tensiometers, psychrometers, heat dissipation sponse demands that may be induced in linear structures and j

sensors, thermocouples, solution samplers, and cross-hole geo-equipment responding to real earthquake motions. Also, given physics electrodes. Measurement depths vary from ground sur.

similar input Fourier energies at high-frequencies, levels of input face to 15 m. The data from the controlled flow and transport Fourier energy at low frequencies observed for artficial motions l

I

Main Citations cnd Abstracts 31 are substantially similar to those levels noted in real earthquake cation of its original FFD rule and the revisions to that rule (pre-motions. In addition, the study reveals specific problems resutt-sented in earlier NUREG/CRs). It also includes chapters that ing from the application of Westem U.S. type motions for seis-address issues about which there is growing concern and/or mm evaluation of Eastem U.S. nuclear power plants.

about which there have been substantial changes since NUREG/CR-5784 was published. Although this report is intend-NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTER-ed to support the NRC's rulemaking on fitness for duty, the con-IZATION ON CONSERVATISM AND VARIABILITY IN SEISMIC clusions of the authors are their own and do not necessarily RISK ESTIMATES. SEWELL,R.T.; TORO,G.R.; MCGUIRE R.K.

represent the opinions of the NRC.

Risk Engineering, Inc. July 1996. 151pp. 9608210260.

89423:001.

NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSER-This study evaluates the impact of alternative methods in VATIONS OVER THE EASTERN UNITED STATES STRAIN treatment and charactertzation of earthquake ground motions MONITORING NETWORK. STRANGE,W.E. Commerce, Dept.

on estimates of seismic risk and its uncertainty. The objective is of, National Oceanic & Atmospheric Administration. June 1996.

to formulate specific procedures and characterizations that may 33pp. 9607090248. 88957:315.

lead to less biased and more precise estimates of risk. This in the period March-May,1990, a 45 station geodetic net-report focuses on sources of conservatism and uncertainty in work, originally established in November-December,1987, was risk that may be introduced by simplif' cations that are made at reobserved using global positioning system (GPS) technology.

the interface of seismic hazard and fragilrty assessments, par-This network, known as the Eastern U.S. Strain Network, was ticularty the use of a fixed spectral shape for all magnitudes and established for the purpose of determining strain and deforma-the anchoring of this shape to PGA. Results indicato significant tion in the central and eastem United States. This 1990 reob-conservatism in the use of standard review spectra at eastem servation was the first of a series of reobservations scheduled U.S. Nuclear plant sites and a strong dependence of seismic to take place over a decade in order to place meaningful con-fragility on earthquake magnitude when PGA is used as the straints on the small differential movements involved.

ground-motion characterization. This study concludes that a single, composite-magnitude spectrum of the appropriate shape NUREG/CR4476: CIRCUIT BRIDGING OF COMPONENTS BY can generally be used to characterize ground motion for fragility SMOKE. TANAKA.T.J.; NOWLEN S.P.; ANDERSON.D.J. Sandia assessment without introducing significant bias or uncertainty in National Laboratories. October 1996. 205pp. 9612120081.

seismic nsk estimates. Results also show that the inelastic or SAND 96-2633. 91074:007, elastic spectral acceleration are superior to PGA as spectral arf Smoke can adversely affect digital electronics; in the short l

chors, but they bnng only a modest benefit in uncertainty reduc-term, it can lead to circuit bridging and in the long term to corro-tion because uncertainty in the risk is dominated by the large sion of metal parts. This report is a summary of the work to i

uncertainty in the hazard.

date and component-level tests by Sandia National Laboratories for the Nuclear Regulatory Commission to determine the impact NUREG/CR-6468: GROUND MOTION INPUT IN SEISMIC EVAL-of smoke on digital instrumentation and control equipment. The UATION STUDIES.lmpacts On Risk Assessment Of Uniform Hazard Spectra. WU.S.C.; SEWELL,R.T. Risk Engineering, Inc.

component tests focused on short-term effects such as c,ircuit bridging in typical components and the factors that can influ-July 1996.130pp. 9608210262. 89423:152.

ence how much the smoke will affect them. These factors in-This report documents research on the subject of conserv.

l clude the component technology and packaging, physical board atistn and variability in seismic risk estimates. Particularly, it ex.

amines the effects of the uniform hazard spectrum (UHS) for protection, and environmental conditions such as the amount of i

smoke, temperature of bum, and humidity level. The likelihood deriving probabilistic estimates of risk and in-structure demand levels, as compared to the more-exact use of realistic time his, of circuit bridging was tested by measuring leakage currents tory inputs (of given probability) that depend explicitly on magng, and comerting those currents to resistance in ohms. Hermeti-cally sealed ceramic packages were more resistant to smoke tude and distance. The approach differs significantly from the conventional procedure in its exhaustive treatment of the than plastic packages. Coating the boards with an acrylic spray ground-motion threat, and in its more detailed assessment of provided some protection against circuit bridging. The smoke component responses to that tnreat. It is found that the approxi-generation factors that affect the resistance the most are hu-mate uniform hazard irFstructure spectrum (UH-ISS) obtained midity, fuel level, and burn temperature. The use of CO(2) as a fire suppressant, the presence of galvanic metal, and the pres-I based on UHS appear to be very close to the more-exact re-sults directly computed from scenario earthquakes. The conclu-ence of PVC did not significantly affect the outcome of these l

sion does not depend on site configurations and structural char.

results.

acteristics. In addition, UH-ISS has composite shapes and may NUREG/CR-6443: GUIDE TO VERIFICATION AND VALIDATION not correspond to the characteristics possessed in a single OF THE SCALE-4 CRITICALITY SAFETY SOFTWARE j

earthquake. The shape is largety affected by the structural pre EMMETT,M.B.; JORDAN,W.C. Oak Ridge National Laboratory' erty in most cases and can be denved approximately from the December 1996. 121pp. 9701130200. ORNL/TM-12834' l

corresponding UHS. Motions with smooth spectra, however, will 91393:171 l

Whenever a decision is made to newly install the SCALE nu-mo ns gged a

s. As e it clear wry safey sonwam on a computw system, the usw l

analysis may underestimate the real demands in non-linear should run a set of verification and validation (V&V) test cases structural analyses, to demonstrate that the software is property installed and func.

NUREG/CR 6470: FITNESS FOR DUTY IN THE NUCLEAR IN-tioning correctly. This report is intended to serve as a guide for l

DUSTRY: UPDATE OF THE TECHNICAL ISSUES 1996.

this V&V hr that it specifies test cases to run and gives expect-DURBIN,N.; GRANT,T.: BITTNER,A.; et al. Battelle Seattle Re-ed results. The report describes the V&V that has been per-search Centerc May 1996. 272pp. 9605220322. BSRC 700/96/

formed for the nuclear criticality safety software in a version of 004. 88319:001.

SCALE-4. The verification problems specified by the code de-This report provides an update of information on the technical velopers have been run, and the results compare fa.orably with issues surrounding the creation, implementation, and mainte-those in the SCALE 4.2 baseline. The results reported in this i

nance of fitness-for-duty (FFD) policies and programs. It has document are from the SCALE 4.2P version which was run on I

been prepared as a resource for Nuclear Regulatory Commis-an IBM RS/6000 Workstation. These results verify that the sion (NRC) and nuclear power plant personnel who deal with SCALE-4 nuclear criticality safety software has been correctly j

FFD programs. It contains a general overview and update on installed and is functioning property. A validation has been per-the technical issues that the NRC considered prior to the publi-formed for KENO V.a utilizing the CSAS25 criticality sequence I

l l

l 32 Miln Citations cnd Abstracts I

and the SCALE 27-group cross-section library for (233)U, sents summaries of the information contained in specific reports (235)U, and (239)Pu fissile systems in a broad range of geome-and publications, all of which are fully identfied as to title, au-tries and fissile fuel forms. The experimental models used for thors, report number, or journal reference, date of publication' the validation were taken from three previous validations of and FIN number under which the work was performed.

KENO V.a. A statistical analysis of the calculated results was used to determine the average calculational bias and a subcriti.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC cal k(eff) criteria for each class of systems validated. Included in AGING LESSONS LEARNED (GALL). Main Report And Appen-the statistical analysis is a means of estimating the margin of dix A. KASZA,K.E.; DIERCKS,D.R.; HOLLAND,J.W.; et al. Ar-subenticality in k(eff). This validation demonstrates that KENO gonne National Laboratory. December 1996. 443pp.

l V.a and the 27-group library may be used for nuclear enbcality 9701130206. ANL-96/13. 91394:001.

safety computatens provided the system being analyzed falls Argonne Nabonal Laboratory and Idaho National Engineering within the range of the expenments used in the validation.

Laboratory in support of the License Renewal Project Director-NUREG/CR4484: GUIDE TO VERIFICATION AND VALIDATION ate of the U.S. Nuclear Regulatory Commission (NRC) per.

formed a comprehensive review of literature pertaining to nucle-OF THE SCALE-4 RADIATION SHIELDING SOFTWARE.

ar power plant aging effects. This generic aging lessons learned BROADHEAD,0.L; EMMETT M.B.; TANG J.S. Oak Ridge Na-(GALL) effort was a systematic review of plant aging information tional Laboratory. December 1996. 55pp. 9701130196. ORNL/

TM-13277. 91400:234.

in order to assess materials and component aging issues relat-Whenever a decision is made to newly install the SCALE radi-ed to continued operation and license renewal of operating re-actors. Literature on mechanical, structural, thermal-hydraulic ation shielding software on a computer system, the user should and electrical components and systems reviewed consisted of i

run a set of verification and validation (V8V) test cases to dem-163 Nuclear Plant Aging Research Reports, 31 NRC Generic l

l onstrate that the software is property installed and functioning Letters,265 Information Notices,82 Licensee Event reports,5 l

l correctly. This report is intended to serve as a guide for this Bulletins, and 10 Nuclear Management and Resources Council V&V in that it specifies test cases to run and gives expected Industry Reports. The results of these reviews were systema-i results. The report describes the V&V that has been performed tized using a standardized GALL tabular format and standard-for the radiation shielding software in a version of SCALE-4.

tzed definitions of aging related degradation mechanisms and This report provides documentation of sample problems which effects. A computertzed data base has also been developed for are recommended for use in the V&V of the SCALE-4 system all review tables and can be used to search for information on for all releases. The results reported in this document are from structures, components, and relevant aging effects. A survey of the SCALE-4.2P version which was run on an IBM RS/6000 the GALL tables reveals that all significant component and work station. These results verify that the SCALE-4 radiation structure aging issues are currently being addressed by the reg-j shielding software has been correctly installed and is function-ulatory process. However, aging of what are termed passive ing property. A set of problems for use by other shielding codes components and structures has been highlighted for continued (e.g., MCNP, TWOTRAN, MORSE) performing similar V&V are scrutiny.

l discussed. A validation has been pwbM for XSDRNPM and MORSE-SGC utilizing SAS1 and SAS4 shielding sequences and NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC the SCALE 2718 group (27N-18 COUPLE) cross-section library AGING LESSONS LEARNED (GALL). Appendix B. KASZA,K.E.;

for typical nuclear reactor spent fuel sources and a variety of DIERCKS D.R.; HOLLAND,J.W.; et al. Argonne National Labora-transport package geometries. The expenmental models used tory. December 1996. 278pp. 9701130171. ANL-96/13.

for the validation were taken from two previous applications of 91395:080.

the SASI and SAS4 methods.

See NUREG/CR4490,V01 abstract.

NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING l

PACKAGES USED TO TRANSPORT VARIOUS CONTENTS.

AGAINST FAILURE BY BRITTLE FRACTURE. Category ll And l

ANDERSON B.L; CARLSON.R.W.; FISCHER,LE. Lawrence ill Femtic Steel Shipping Containers With Wall Thickness Great-l Livermore National Laboratory. November 1996. 65pp.

er Than Four inches. SCHWARTZ,M.W.; FISCHER,LE. Law-l 9612030267. UCRL-ID-124822. 90980:159.

rence Livermore National Laboratory. August 1996. 26pp.

l This report presents sample calculations and examples of 9609030358. UCRL-ID-124583. 89546:334.

l leakage rates for various contents in Type B packages. Sam.

This report provides criteria for selecting ferritic steels that pies of acceptance standard leakage rates are developed for would prevent brittle fracture in Category 11 and lll shipping con-i l

specific contents types at normal transport conditons and at hy.

tainers with wall thickness greater than four inches. These l

pothetical accident conditions. The leakage rates are expressed methods are extensions of those previously used for Category II l

cs allowable standard leakage rates. The types of contents con-and lit containers with wall thickness less than four inches and sidered include: (1) powders, (2) liquids, (3) irradiated fuel rods,,

Category I containers with wall thickness greater than four (4) gases, and (5) solids.

inches.

NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVI.

NUREG/CR4492: BLT-MS (BREACH LEACH. AND TRANS-TIES AT BROOKHAVEN NATIONAL LABORATORY.

PORT-MULTIPLE SPECIES) DATA INPUT GUIDE.A Computer COWGILL.M.G.; CZAJKOWSKI.C.J.; FRANZ,E.M. Brookhaven Model For Simulating Release Of Contaminant From Subsur-National Laboratory. October 1996.119pp. 9611190248. BNL-face Low-Levef~ Waste Disposal Facility. SULLIVAN,T.M.;

NUREG-52508. 90824.139.

KINSEY,R.R.; et al.

Brookhaven National Laboratory.

Brookhaven National Laboratory has for many years conduct-MACKINNON,R.J. Ecodynamics Research Associates, Inc... No-ed examinations related to the failures of nuclear materials and vember 1996. 184pp. 9612110212. BNL-NUREG-52509.

l components. These examinations include the confirmation of 91064:001.

I root cause analyses, the determination of the causes of failure, The BLT-MS computer code has been developed, implement-identificaticn of the species that accelerate corrosion, and com-ed, and tested. BLT-MS is a two-dimensional finite element parison of the results of nondestructive examinations with those computer code capable of simulating the time evolution of com obtained by destructive examination. The results of those ex.

centration resulting frorn the time-dependent release and trans-cminations, which had previously appeared in various formats port of aqueous phase species in a subsurface soil system.

(formal and informal reports, journal articles, etc,), have boen BLT MS contains models to simulate the processes (water flow, collected together and summarized in the present report. The container degradation, waste form performance, transport, and report is divided into sections according to the general subject radioactiv9 production and tiecay) most relevant to estimating matter (for example, corrosion, fatigue, etc.). Each section pre-the release and transport of contaminants from a subsurface

Main Citations and Abstracts 33 disposal system. Water flow is simulated through tabular input the following sections representing different aspects of nuclear or auxiliary files. Container degradation considers localized fail-plant ownership: Nuclear power plant percentage ownership or-ure due to pitting corrosion and general failure due to uniform dered by plant name; Nuclear power plant percentage owner-surface degradation processes. Waste form performance con-ship ordered by utility name; Utility / company relationships or-siders release to be limited by one of our mechanism: rinse with dered by parent / holding company; Utility / company relationships partitioning, diffusion, untform surface degradation, or solubility.

ordered by subsidiary; Nuclear power plants listed by operator, Radioactive production and decay in the wastn form are simu-Nuclear power plant operators listed by plant name; Nuclear lated. Transport considers the processes of advection, disper-power plants listed by state.

sion, diffusion, radioactive production and decay, reversible linear sorption, and sources (waste forms releases). To improve NUREG/GR 0015: BULK TEMPERATURE MEASUREMENT IN the usefulness of BLT-MS a pre-processor, BLTMSIN, which as-THERMALLY STRIPED PIPE FLOWS.

LEMURE,N.;

sists in the creation of bput files, and a post-processor, OLVERA.J.R.; RUGGLES.A.E. Tennessee, Univ. of, Knoxville, BLTPLOT, which provides a visual display of the data have TN. December 1995.130pp. 9608050231. 89250:144.

been developed. This document reviews the models implement-The bulk temperature measurement of pipe flows with thermal ed in BLT-MS and serves as a guide to creating input files for striping is explored. An expenment is conducted to examine the BLT-MS.

feasibility of using temperature measurements on the external surface of the pipe to estimate the bulk temperature of the flow.

NUREG/CR-6494: CONTINUOUS ANALYSIS FOR VANADIUM IN Simple mixing models are used to characterize the development LOMI DECONTAMINATION.

KOTTLE,S.;

STOWE,R.A.;

of the temperature profile in the flow. Simple averaging tech-BISHOP,J.V. Omni Tech International, Ltd. December 1996.

niques and Backward Propagating Neural Net are used to pre-38pp. 9612240085. 91197:244.

dict bulk temperattre from the extemal temperature measure-This report covers research into methods for real-tirne, on-line ments. Accurate bulk temperatures can be predicted. However, analysis of vanadium ion concentration during LOMI chemical some temperature distributions in the flow effectively mask the decontamination of piping in nuclear power plants. An on-line bulk temperature from the wall and cause significant error in the colorimeter was developed which periormed very well in labora-bulk temperature predicted using this technique.

tory simulations, but was subject to excessive interference by colored materials in the field. A titnmetric method was investi-NUREG/lA Ot29 P01: AN ASSESSMENT OF THE CORCON.

gated using ferric lon with potentiometric electrodes to follow MOD 3 CODE.Part 1: Thermal-Hydraulic Calculations.

the course of the reaction. By proper choice of reagents it was STRIZHOV,V.; KANUKOVA,V.; VINOGRADOVA,T.; et al.

specific to vanadous ion and free from interference. An auto-Russia. September 1996. 201pp. 112040179. 91006:001.

matic instrument was developed, tested under simulated LOMI This report deals with the subject of CORCON. Mod 3 code conditions, and successfully evaluated in the field during a validation (thermal-hydraulics modeling capability only) based on LOMI chemical decontamination.

MCCI experiments conducted under different programs in the NUREG/CR-6495: CASE STUDY OF LIQUEFACTION INDUCED past decade. Thermal. hydraulic calculations (i.e., concrete abla-BY THE 1944 MASSENA, NEW YORK - CORNWALL, ONTAR.

tion, mest temperature, melt energy, concrete temperature, and 10 EARTHOUAKE. TUTTLE,M.P. Lamont-Doherty Earth Observ.

condensable and norkcondensible gas generation) were per-atory. September 1996. 33pp. 9612040122. 91006:317.

formed with the code, and compared with the data from 15 ex-Despite surveying with ground-penetration radar and trench-periments, coducted at different scales using both simulant (me-ing at four different locations, no earthquake-induced sand dikes tallic and oxidic) and prototypic melt materials, us,ng different i

were observed at the site where three sand fissurss were docu.

concrete types, and with and without an overlying water pool, mented by Berkey (1945) following the 1944 Massena, New Sensitrvity studies were performed in a few cases involving, for York-Cornwall, Ontario, earthquake. The site was found to be example, heat transfer from melt to concrete, condensed phase very disturbed by human activity, especially road building related chemistry, etc. Further, special analysis was performed using to the construction of the St. Lawrence-Franklin D. Roosevelt the ACE L8 experimental data to illustrate the differences be-Power Project. Sand diapirs and dewatering structures were ob-tween the experimental and the reactor conditions, and to dem-served in two of the trenches. These features may be related to onstrate that with proper corrections made to the code, the cal-incipient liquefaction but their origin is equivocal. The epicentral culated results were in better agreement with the experimental location of the 1944 earthquake probably occurred within 10 km data. Generally, in the case of dry cavity and metallic melts, of the site; therefore, the epicentral distance of this site of lique-CORCON-Mod 3 thermal-hydraulic calculations were in good faction is within the expected range even for westem earth-agreement with the test data. For oxicic melts in a dry cavity, uncertainties in heat transfer models played an important role quakes of siCar magnitude. A nearshore sandy facies of a gle-ciolacustrine deposit is thought to be 1he mtterial that liquefied for two melt configurations - a stratifkx1 geometry with segregat-during the 1944 event A geotechnical investigation that would ed metal and oxide layers, and a heterogeneous mixture. Some havo assessed the liquefaction potential of subsurface material discrepancies in the gas release data were,noted in a few at the site was canceled due to downsizing at Ontario Hydro, cases. These discrepancies were attributed, in part, to con-Until a geotechnical investigation is conducted, additional densed phase chemical reactions modeling and,,n part, to ex-i trenching seems unwarranted. Poor cutbank exposures limited perimental uncertainties. In the case of wet cavity, good agree-ment was found between the experimental data and code cal-search for liquefaction features in the Massena crea.

culations except, again, for the gas release data. With proper NUREG/CR-6500: OWNERS OF NUCLEAR POWER PLANTS.-

corrections made to the code to account for correct condensed HUDSON,C.R.; WHITE,V.S. Oak Ridge National Laboratory. No-phase chemistry and with corrections made to the input data to vember 1996. 61pp. 9611260261. ORNL/TM-13297. 90920:241.

account for expenmental uncertainties, better agreement be-Commercial nuclear power plants in this country can be tween code calculations and experimental data was noted.

owned by a number of separate entities, each with varying own-ership portions. Each of these owners may, in turn, have a NUREG/lA-0130: ASSESSMENT OF RELAPS/ MOD 3.1 WITH parent / subsidiary relationship to other companies, in addstion, THE LSTF SB-SG-06 EXPERIMENT SIMULATING A STEAM the operator of the plant may be a different entity as well. This GENERATOR TUBE RUPTURE TRANSIENT. SEUL,K.W.;

report provides a compilation on the owners / operators for all BANG,Y.S.;' LEE,S.; et al. Korea institute of Nuclear Safety.

commercial power reactors in the United States. While the utility September 1996.112pp. 9612040171. CAMP 002. 91006:206.

industry is currently experiencing changes in organizational The objective of the present work is to identify the predictabil-structure which may affect nuclear plant ownership, the data in ity of RELAPS/ MOD 3.1 regarding Mermal-hydraulic behavior this report is current as of July 1996. The report is dnnded into duty a steam generator tube rupture (SGTR). To evaluate the

34 Main Citations and Abstracts computed results, LSTF SB-SG-06 test data simulating the PCTs were calculated for 2793 data points. The deviations are SGTR that occurred at the Mihama Unit 2 in 1991 are used.

shown to be normally distributed, and used to quantify statisti-Also, some sensitivity studies of the code change in RELAPS, cally the PCT uncertainty of the code. The upper limit of PCT the break simulation model, and the break valve discharge coef-uncertainty at 95% confidence level is evaluateo to be about ficient are performed. The calculation resutts indicate that the 99K.

RELAPS/ MOD 3.1 code predicted well the sequence of events and the major phenomena during the transient, such as the NUREG/lA-0133: DEVELOPMENT,lMPLEMENTATION, AND AS-asymmetric loop behavior, reactor coolant system (RCS) cool.

SESSMENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-down and heat transfer by natural circulation, the primary and ANNULAR FILM-BOILING IN A TWO-FLUID MODEL DE secondary system depressurization Dy the pressurizer auxiliary CACHARD,F. Paul Scherrer institute. October 1996. 103pp.

spray and the steam dump using the intact loop steam geners-9611190277, CAMP 004. 90823:249.

tor (SG) relief valve, and so on. However, there are some differ-Inverted-Annular Film-Boiling (IAFB) is one of the post-burn-ences from the experimental data in the number of the relief out heat transfer modes taking place dunng the reflooding valve cycling in the affected SG, and the flow regime of the hot phase of the loss-of-coolant accident, when the liquids at the leg with the pressurtzer, and the break flow rates. Finally, the quench front is subcooled. Under IAFB conditx)ns, a continuous calculation also indicates that the coolant in the core could liquid core is separated from the wall by a superheated vapour remain in a subcooled state as a result of the heat transfer film. A key issue in IAFB modefing is to predict how the heat caused by the natural circulation flow even if the reactor coolant flux reaching the vapour-liquid interface is split into a liquid heat-pumps (RCPs) turned off and that the affected SG could be ing term and a vaporization term. In the model proposed, con-properly isolated to minimize the radiological release after the vective liquid heating is related to the liquid velocity relative to SGTR.

the interface and not the absolute liquid velocity, as in previous models.

NUREG/lA-0131: ASSESSMENT OF RELAPS/ MOD 3 USING BETHSY 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARA-NUREG/lA-0134: ASSESSMENT OF RELAPS/ MOD 3.1 FOR TlVE TEST, CHUNG,Y J.; JEONG.J4; KIM,D-S.; et al. Korea GRAVITY-DRIVEN INJECTION EXPERIMENT IN THE CORE Atomic Energy Research Institute. October 1996. 138pp.

MAKEUP TANK OF THE CARR PASSIVE REACTOR (CP-9611190262. CAMP 003. 90824:001, 1300). LEE,S.; NO,H.C. Korea Advanced Institute of Science This report presents the results of the RELAPS/ MOD 3 Ver-and Technology. BANG,Y.S.; et al. Korea Institute of Nuclear sion 7j assessment on BETHSY 6.2 TC test corresponding to a Safety. October 1996. 150pp. 9611180277, CAMP 005.

six inch cold leg break LOCA of the Pressurizer Water Reactor 90820:001 (PWR). The pnmary objective of the test was to provide refer-The objective of the present work is to improve the analysis ence data of two facilities of different scales (BETHSY and capability of RELAP5/ MOD 3.1 on the direct contact condensa.

LSTF facilities). The present calculation aims at analysis of tion in the core makeup tank (CMT) of passive high-pressure in-RELAPS/ MOD 3 capability on the small break LOCA simutabon.

jection system (PHIS) in the CARR Passive Reactor (CP 1300).

The results of calculabon have shown that the RELAPS/ MOD 3 The gravity-driven injection experiment is conducted by using a reasonably predicts occurrences as well as trends of the major small scale test facility to identify the parameters having signifi-phenomena such as pnmary pressure, timing of loop seal clear.

cant effects on the gravity-driven injection and the major con-ing, liquid hold up, etc. However, some differences also have densation modes. The condensation modes are divided into been found in the predictions of loop seal clearing, collapsed three modes: sonic jet, subsonic

and steam cavity, core water level after loop seal clearing, and accunn.ilator injec.

RELAP5/ MOD 3.1 is chosen to evalui Me code predictability tion behaviors. For understanding of discrepancies in the sam on the direct contact condensation in tne CMT. It is found that predictions, several sensitivity calculations have been perfM as well. These include the changes of two-phase discharge co-the predictions of MOD 3.1 are in better agreement with the ex-erimental data than those of MOD 3.0. From the nodalization efficients at the break junction and some corrections of the in-terphsse drag term. As a result, change of a single parameter dhM e,N M M h W W has not improved the overall predictions and it has been found ment with the experimental data than the multi-node models.

that the interphase drag model still has large uncertainties.

RELAPS/ MOD 3.1 identifies the flow regime of the test section as vertical stratification. However, the flow regime observed in NUREG/lA-0132: IMPROVEMENTS TO THE RELAPS/ MOD 3 RE-the expenment is the subsonic jet with the bubble having the FLOOD MODEL AND UNCERTAINTY OUANTIFICATION OF vertical cone shape. To accurately predict the direct contact REFLOOD PAK CLAD TEMPERATURE. CHUNG,B.D.; LEE,Y.J.;

condensation in the CMT with RELAPS/ MOD 3.1, it is essential PARK,C.E.; et al. Korea Atomic Energy Research Institute. Oc-that a new set of the interfacial heat transfer coefficients and a tober 1996.106pp. 9611190273. CAMP 001. 90623:001.

new flow regime map for direct contact in the CMT be devel-Assessment of the original RELAPS/ MOD 3.1 code against oped.

the FLECHT SEASET senes of expenment has identified some weaknesses of the reflood model, such as the lack of quench-NUREG/lA-0135: POST-TEST ANALYSIS OF PPER-ONE PO-IC-ing temperature model, the shortcoming of Chen transition boil-2 EXPERIMENT BY RELAPL MOD 3 CODES. BOVALINI,R.;

ing model, and the incorrect prediction of droplet size and inter-AURIA,F.D.; GALASSI,G.M.; et al. Universita' Degli Studi Di facial heat transfer. Also high pressure spikes during the reflood Pisa, Pisa, Itaty. November 1996. 200pp. 96t2110160.

calculation resutted in the high steam flow oscillation and liquid CAMP 006. 91065:001.

canyover. An effort has been made to improve the code with RELAPS/ MOD 3.1 was applied to the PO-lC-2 experiment per-respect to the above weakness and the nee.essary model for formed in PIPER-ONE facility, which has been rnodified to re-wall heat transfer package and numerical scheme had been produce typical isolation condenser thermal-hydraulic condi-modified. Some important FLECHT-SEASET experiment were tions. RELAPS is a well known code widely used at the Univer-assessed using the improved version and standard version. The sity of Pisa dunng the past seven years. RELAPS/ MOD 3.1 was result from the improved version of RELAPS/ MOD 3.1 shows the latest version of the code made available by the Idaho Na-the weaknesses of RELAPS/ MOD 3.1 was much improved when tional Engineenng Laboratory at the time of the reported study.

compared to the standard MOD 3.1 code. The prediction of void PIPER-ONE is an experimental facility simulating a General profile and cladding temperature agreed better with test data Electric BWR-6 with volume and height scaling ratios of 1/2200 especially for the gravity feed test. The scatter diagram of peak and 1./1, respectrvely. In the frame of the p,esent activity a cladding temperatures (PCTs) is made from the comparison of once-through heat exchanger immersed in a pool of ambient all the calculated PCTs and the corresponding experimental temperature water, installed approximately 10 m above the values. The deviation between experimental and calculated core, was utihzed to reproduce qualitatively the phenomenolo-l

~

Main Citations and Abstracts 35 gies expected for the Isolation Condenser in the simplified BWR countered in the analysis of the PO-SD-8 experiment. A very (SBWR). The PO-tC-2 expenment is the flood up of the PO-SD-wide anatysis is presented hereafter including the use of differ.

8 and has been dessned to solve some of the problems en- -

ent code versions, l

l t

I l

L

Secondary Report Number Index l

This index lists, in alphabetical order, the performing organization-issued report codes for the i

NRC contractor and international agreement reports in this compilation. Each code is cross-

)

referenced to the NUREG number for the report and to the 10-digit NRC Document Control l

System accession number.

SECONOARY REPORT NUMSER REPORT NUMOER SECONDARY REPORT NUMBER REPORT NUMOER 04-4448-010 NUREG/CR4074 V02 ORNL 6814 NUREG/CR4246 i

l ANL-95/37 NUREG/CR4383 ORNUTM-11568 NUREG/CP-5591 V06 N2 i

l ANL 95/41 NUREG/CR-4667 V20 OANUTM-12834 NUREG/CR4483 ANL 95/47 NUREG/CR4428 ORNUTM-12980 NUREG/CR4332 ANL-96/1 NUREG/CR-4667 V21 ORNUTM-13122 NUREG/CR4406 ANL-96/13 NUREG/CR4400 V02 ORNUTM-13133 NUREG/CR-6413 ANL-96/13 NUREG/CR4490 V01 ORNUTM-13148 NUREG/CR4424 ORNL/TM 13149 NUREG/CR4425 BMI-2186 NUREG/CR4337 U

h hC BMI 2186 NUREG/CR4439 g

5 BMI-2188 NUREG/CR4438 ORNL/TM-13206 NUREG/CR4455 l

BMI-2190 NUREG/CR4440 ORNUTM-13207 NUREG/CR4460 l

BMI-2191 NUREG/CR4443 ORNUTM-13212 NUREG/CR4163 BMi-2192 NUREG/CR4444 ORNL/TM-13213 NUREG/CR4357 BMF2193 NUREG/CR4445 ORNUTM-13244 NUREG/CR-5442 BNL-NUREG 52425 NUREG/CR4253 ORNUTM-13277 NUREG/CR4484 BNL NUREG-52460 NUREG/CR4336 ORNUTM-13297 NUREG/CP4500 l

BNL-NUREG-52462 NUREG/CR4339 ORNUTM-9593 NUREG/CR-4219 V11 N2 i

BNL-NUREG 52463 NUREG/CR4340 ORNL/TM-9593 NUREG/CR-4219 V12 N1 BNL-NUREG-52467 NUREG/CR4350 PNL 10086 NUREG/CR4270 BNL-NUREG-52476 NUREG/CR4374 PNL 10496 NUREG/CR4210 BNL-NUREG-52480 NUREG/CR4384 V01 PNL 10709 NUREG/CR4306 l

BNL-NUREG-52480 NUREG/CR4384 V02 PNL 10843 NUREG/CR4346 BNL-NUREG-52488 NUREG/CR4415 PNL-10866 NUREG/CR4411 l

BNL-NUREG 52491 NUREG/CR4422 PNL 10897 NUREG/CR4429 BNL-NUREG 52508 NUREG/CR4489 PNL 10934 NUREG/CR4435 i

BNL NUREG42509 NUREG/CR4492 PNL 11202 NUREG/CR-5758 V06 I

BSRC-700/96/004 NUREG/CR4470 PNL-4221 NUREG/CR 2850 Vid j

BSRC-700/96/012 NUREG/CR-5758 V06 PNL-4297 NUREG/CR-2800 SOS i

CAMP 001 NUREG/lA 0132 PNL-7445 NUREG/CR-5631 A02 CAMP 002 NUREG/lA 0130 PNL4462 NUREG/CR-5973 R03 CAMP 003 NUREG/lA4131 PNL4856 NUREG/CR4124 PNL4919 NUREG/CR-5985 S01 CAMP 004 NUREG/lA 0133 PN CR CAMP 005 NUREG/lA-0134 p

CR V01 CAMP 006 NUREG/lA 0135 PNL 9975 NUREG/CR4174 V02 CNWRA 95-013 NUREG/CR-6388 PNNL 10475 NUREG/CR-5068 CNWRA 95-017 NUREG/CR4401 PNNL-10571 NUREG/CR4344 i

I FEMA-REP 1 NUREG 0654 R1 S2 DFC PNNL 11134 NUREG/CR4470 FEMA-REP 1 NUREG 0654 R1 S3 DFC PNNL 9433 NUREG/CR 6227 INEL-94/0278 NUREG/CR-5229 V0B PU-NE 94/1 NUREG/CR4309 l

INEL-95/0061 NUREG/CR4314 SAND 94-0407 NUREG/CR4189 INEL 95/0073 NUREG/CR4256 V03 SAND 94 0485 NUREG/CR4202 i

INEL-95/0174 NUREG/CR-5535 V07 R1 SAND 95-2381 NUREG/CR4338 INEL 95/0215 NUREG/CR4341 SAND 96-2633 NUREG/CR4476 i

INEL-95/0383 NUREG/CR4365 SEA 95-2755010A1 NUREG/CR-5595 ROI i

INEL-95/0506 NUREG/CR4392 SEA 95-554 06A.8 NUREG/CR-6367 INEL-95/0512 NUREG/CR4396 SEASF-DR-94-001 NUREG/CR4432 l

lNEL 95/0551 NUREG/CR4407 SSS TR-95-15216 NUREG/CR4448 V01 INEL 95/0573 NUREG/CR-5753 UCAL-ID 122514 NUREG/CR4430 INEL-95/0654 NUREG/CR4442 UCRL-ID 122526 NUREG/CR4421 IPSN 94 03 NUREG/CR4202 UCRL-ID-124583 NUREG/CR4491 NEA/CSNI/R(95)9 NUREG/CR4442 UCRL-ID 124822 NUREG/CR4487 i

37 L---

l Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.

AABERG.R.L BADELLI,L NUREG/CR.2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE SBWR.

ABEL,K.H.

i NUREG/CR-6429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi.

BAOCHi,0-CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA.

NUREG-1540: BWR STEEL CONTAINMENT CORROSION.

l DIONUCLIDES.

J BAJWA C.S.

AHN,T.M.

NUREG4552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR NUREG 1564: LONG-TERM KINETIC EFFECTS AND COLLOID FORMA.

POWER PLANTS.

TIONS IN DISSOLUTION OF LWR SPENT FUEL NUREG-1565: DRY OXIDATION AND FRACTURE OF LWR SPENT OAKER.D.A.

NUR RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology AKSENOV,E.

And Data Base.

NUREG/lA 0129 POI: AN ASSESSMENT OF THE CORCON-MOD 3 NUREG/CR-2850 V14. DOSE COMMITMENTS DUE TO RADIOACTIVE CODE.Part 1: Thermal-Hydraulic Calculatons.

RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

ALLEN M D BANG,Y.S.

NUREG/bR-6338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG/!A-0130: ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE SB-SG 06 EXPERIMENT SIMULATING A STEAM GENERATOR TUBE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

E NURE / 0131 A S MENT OF RELAP5/ MOD 3 USING BETHSY ANDERSON.B.L 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

^

USED T A SPORT VAR S TE TS CLAD TEMPERATURE.

ANDERSON,C.M NUREG/lA-0134: ASSESSMENT OF RELAPS/ MOD 3.1 FOR GRAVITY.

NUREG/CR-6527: PERFORMANCE DEMONSTRATION TESTS FOR DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.

THE CARR PASSIVE REACTOR (CP 1300).

NURE /

76: CIRCUIT BRIDGING OF COMPONENTS BY SMOKE.

D BELED AN BOD E D E SSUES ANGEL.LJ.

NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-BARCHI T'1415 NUREG-V08 NO2: OFFICE OF THE INSPECTOR TRASONIC INSERVICE INSPECTION SYSTEM.

GENERALSemiannual Report To Congress. October 1,1995 March ARONSON,A.

NU EG 15 V09 N01: OFFICE OF THE INSPECTOR 44 BLT-M R CHL AND SPORT.MUL-SemaM RepM h WessM t M - @@

0, M TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat-ing Release Of Contarrunant From Subsurface Low-Level Waste Dis-BARRIERE,M.T.

posal Facility NUREG/CR-8350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS ARREDONDO,S.A.

(A HEANA)Thl Bae W Memodology Wton.

NUREG 1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-BASS.B.R.

RIALS LICENSES. Program-Specific Guidance About Portable Gauge NUREG/CR 6460: CSNI PROJECT FOR FRACTURE ANALYSES OF Licenses. Draft Report For Comment.

LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL.

l ATTAL,M.

NUREG/CR4202: LONG-TERM AGING AND LOSSOF-COOLANT AC-BASSETT,R.L CtDENT (LOCA) TESTING Oc ELECTRICAL CABLES.U.S1 French Co-NUREG/CR.6457: RAPID ESTIMATE OF SOLIO VOLUME IN LARGE operative Research Program.

TUFF CORES USING A GAS PYCNOMETER.

NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR ATWOOD,C.L APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

l NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN SAFETY-RELATED COMPONENTS.

BASU S.

NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN AURIA.F.D.

ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE NUREG/tA-0135: POST. TEST ANALYSIS OF PIPER ONE PO IC 2 EX-CURRENT UNDERSTANDING OF BROADER FUEL COOLANT PERIMENT BY RELAPS/ MOD 3 CODES.

INTERACTION ISSUES. Report Of The Second Steam Explosen Review Group Workshop.

NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-BAUM.J.W.

ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF LIVES FOR RA.

CORDING TO IMPORTANCE TO SAFETY.

DIOLMLLED ANTIBODIES AND RELATED ISSUES.

39

Main Citations and Abstracts 35 gies expected for the isolation Condenser in the simplified BWR countered in the analysis of the PO-SD-8 experiment A very (SBWR). The PO-IC-2 experiment is the flood up of the PO SD-wide analysis is presented hereafter including the use of differ.

8 and has been designed to solve some of the problems en- -

ent code versions.

i 4

2 i

f

i 1

Secondary Report Number index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY REPORT NUMBER REPORT NUMt *R SECONDARY REPORT NUGASER REPORT NUGASER 04-4448 010 NUREG/CR4074 V02 ORNL4814 NUREG/CR4246 ANL-95/37 NUREG/CR4383 ORNUT411568 NUREG/CR-5591 V06 N2 ANL-95/41 NUREG/CR 4667 V20 ORNUT412834 NUREG/CR4483 ANL-95/47 NUREG/CR4428 ORNUT412980 NUREG/CR4332 ANL-96/1 NUREG/CR 4667 V21 ORNUTE13122 NUREG/CR4406 ANL-96/13 NUREG/CR4490 V02 ORNUTM-13133 NUREG/CR4413 ORNUTM 13148 NUREG/CR4424 j

ANL 96/13 NUREG/CR4490 V01 h$

2 BMI-2186 NUREG/CR4337 BMI-2186 NUREG/CR4439 ORNUTM-13187 NUREG/CP-0151 BMI-2188 NUREG/CR4438 ORNUTM-13206 NUREG/CR4455 BMI 2190 NUREG/CR4440 ORNUTM-13207 NUREG/CR4480 BMI-2191 NUREG/CR4443 ORNUTM-13212 NUREG/CR4163 BMI-2192 NUREG/CR4444 ORNUTM-13213 NUREG/CR4357 BMI-2193 NUREG/CR4445 ORNUTM-13244 NUREG/CR-5442 BNL-NUREG-52425 NUREG/CR4253 ORNUTE13277 NUREG/CR4484 BNL NUREG-52460 NUREG/CR4336 ORNUTM-13297 NUREG/CR-6500 BNL NUREG -52462 NUREG/CR4339 ORNUTM-9593 NUREG/CR 4219 V11 N2 BNL NUREG-52463 NUREG/CR4340 ORNL/T49593 NUREG/CR-4219 V12 N1 BNL-NUREG-52467 NUREG/CR4350 PNL 10086 NUREG/CR4270 BNL NUREG-52476 NUREG/CR4374 PNL 10496 NUREG/CR4210 BNL NUREG-52480 NUREG/CR4384 V01 PNL 10709 NUREG/CR4366 BNL-NUREG 52480 NUREG/CR4384 V02 PNL 10843 NUREG/CR4346 BNL NUREG-52488 NUREG/CR4415 PNL 10866 NUREG/CR4411 BNL NUREG-52491 NUREG/CR4422 PNL-10897 NUREG/CR4429 BNL-NUREG-52508 NUREG/CR4489 PNL 10934 NUREG/CR4435 BNL-NUREG 52509 NUREG/CR4492 PNL 11202 NUREG/CR-5758 V06 BSRC 700/96/004 NUREG/CR4470 PNL-4221 NUREG/CR-2850 V14 BSRC 700/96/012 NUREG/CR-5758 V06 PNL 4 N7 NUREG/CR 2800 SOS CAMP 001 NUREG/lA-0132 PNL-7446 NUREG/CR-5631 R02 CAMP 002 NUREG/lA-0130 PNL4462 NUREG/CR-5973 R03 Pf;L4856 NUREG/CR4124 CAMP 003 NUREG/lA-0131 PNL 8919 NUREG/CR 5985 S01 CAMP 004 NUREG/lA4133 CAMP 005 NUREG/lA 0134 5

U V01 CAMP 006 NUREG/lA-0135 PNL 9975 NUREG/CR4174 V02 CNWRA 95 013 NUREG/CR4388 PNNL 10475 NUREG/CR-5068 CNWRA 95-017 NUREG/CR4401 PNNL 10571 NUREG/CR4344 FEMA-REP-1 NUREG-0654 R1 S2 DFC PNNL-11134 NUREG/CR4470 FEMA-REP-1 NUREG4654 R1 S3 DFC PNNL-9433 NUREG/CR4227 INEL-94/0278 NUREG/CR-5229 V08 PU-NE 94/1 NUREG/CR4309 INEL-95/0061 NUREG/CR4314 SAND 94-0407 NUREG/CR4189 INEL 95/0073 NUREG/CR4256 V03 SAND 94-0485 NUREG/CR4202 INEL-95/0174 NUREG/CR-5535 V07 R1 SAND 95-2381 NUREG/CR4338 INEL 95/0215 NUREG/CR4341 SAND 96-2633 NUREG/CR4476 INEL-95/0383 NUREG/CR4365 SEA 95-2755010A1 NUREG/CR-5595 ROI INEL 95/0506 NUREG/CR4392 SEA 95-554 06A.8 NUREG/CR4367 INEL-95/0512 NUREG/CR4396 SEASF-DR-94-001 NUREG/CR4432 INEL-95/0551 NUREG/CR-6407 SSS-TR-95-15216 NUREG/CR4448 V01 INEL-95/0573 NUREG/CR-5753 UCAL-ID-122514 NUREG/CR4430 INEL 95/0654 NUREG/CR4442 UCAL ID 122526 NUREG/CR4421 IPSN 9443 NUREG/CR4202 UCRL-ID 124583 NUREG/CR4491 NEA/CSNt/R(95)9 NUREG/CR4442 UCRL-ID 124822 NUREG/CR4487 t

l 37 l

a a.aeA6-as amM-Mmama aeAea A 4,.s4 2,u4

&4m.L--4 ka>

nm-L.cA-a.

&sa-a_s4Km n,m W N 6 Mg. A, e5 AM&44.,4,,,a-._,,m --

n--mA A _p 4 e m, e

il e

i i

s a

f e

I i

i i

I

1 i

l Personal Author index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of l

the report (s) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.

l AABERG,R.L BABELL1,1.

NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE

SBWR, ABEL.K.H.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Ml.

BAOCHi,G.

CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA..

NUREG-1540: BWR STEEL CONTAINMENT CORROSION.

DIONUCLIDES.

AHN T.M.

NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR j

NUREG-1564. LONG-TERM KINETIC EFFECTS AND COLLOID FORMA.

POWER PLANTS.

i TlONS IN DISSOLUTION OF LWR SPENT FUEL NUREG-1565: DRY OXIDATION AND FRACTURE OF LWR SPENT 8AKER NUREG CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOACTIVE l

RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology l

AKSENOV,E.

And Data Base.

NUREG/lA-0129 P01: AN ASSESSMENT OF THE CORCON-MOD 3 NURFG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE l

CODE.Part 1: Thermal-Hydraulic Calculations.

RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

ALLEN.M D.

BANG,Y.S.

NUREG/lA 0130: ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF NUREG/CR4338. RESOLUTION OF THE DIRECT CONTAINMENT HEATING ISSUE FOR ALL WESTINGHOUSE P' ANTS WITH LARGE SB-SG-06 EXPERIMENT SIMULATING A STEAM GENERATOR TUDE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

NURE A 131 A SMENT OF RELAP5/ MOD 3 USING BETHSY ANDERSON.B L 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

A N

3RE M NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES

^

O USED TO TRANSPORT VARIOUS CONTENTS.

CLAD TEMPERATURE.

NUREG/lA-0134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY-ANDERSON C.M DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR

^

b

^

l EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.

BARBER,0.E.

ANDERSON,DJ NUREG/CR 6476: CIRCUIT BRIDGING OF COMPONENTS BY SMOKE DIOLABELED ANTIBODIES AND RELATED ISSUES.

ANGEL,LJ.

BARCHl,T.

NUREG/CR-5905 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-NUREG-1415 V08 NO2: OFFICE OF THE INSPECTOR l

TRASONIC INSERVICE INSPECTION SYSTEM.

i GENERAL. Semiannual Report To Congress, October 1,1995. March 31 1996 I

ARONSON,A.

NUR'EG-14'15 V09 N01: OFFICE OF THE INSPECTOR i

U 4 :

T-M R CHL CH AND N PORT-MUL-996' TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat.

ing Release Of Contaminant From Subsurface Low-Level Waste Dis.

BARRIERE,M.T.

posal Facility.

NUREG/CR.6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS ARREDOND M (ATHEANA). Technical Basis And Methodology Desenption.

l NUREG-1558 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-BASS,B.R.

RIALS LICENSES Program. Specific Guidance About Portable Gaugo NUREG/CR 6480: CSNI PROJECT FOR FRACTURE ANALYSES OF Licenses. Draft Report For Comment LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-ATTAL,M.

NUREG/C46202: LONG TERM AGING AND LOSS-OF-COOLANT AC-BASSETT,R.L CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./ French Co-NUREG/CR4457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE operative Research Program.

TUFF CORES USING A GAS PYCNOMETER.

J NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR ATWOOD,C.L APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN SAFETY-RELATED COMPONENTS.

BABU.S.

NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN AURIA.F.D.

ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE NUREG/lA-0135: POST-TEST ANALYSIS OF PlPER ONE POIC-2 EX-CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT PERIMENT BY RELAP5/ MOD 3 CODES.

INTERACTION ISSUES. Report Of The Second Steam Explosion Review Group Workshop.

NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG.

BAUM,J.W.

ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-NUREG/CR4374. WHOLE-BODY EFFECTIVE HALF-LIVES FOR RA.

CORDING TO IMPORTANCE TO SAFETY.

DIOLABELED ANTIBODIES AND RELATED ISSUES.

39

l l

40 Personal Author Index BAXTERB.

DOYALINI,R.

NUREG/CR4470- FITNESS FOR DUTY IN THE NUCEAR INDUSTRY:

NUREG/lA 0135: POST. TEST ANALYSIS OF PIPER ONE PO-IC-2 EX-UPDATE OF THE TECHNICAL ISSUES 1996.

PERIMENT BY RELAP5/ MOD 3 CODES.

BENAC,D.J.

DOWERMAN.B.

NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL SAFETY TESTING.Techrwcal Report On The Findmgs Of Task 4 inves.

QUAUFICATION OF SAFETY-RELATED ELECTRIC CABLES.Uterature t gation of Failed Nitinol Brachytherapy Wire.

An@s And Appendices.

DENNETT T,,.,E,,.

g T R$ UGH THE USE OF P$SI IObENSIYTVE DETE_,,,,,,,,, _,,

AN NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN q

DIGITAL IMAGE PROCESSING.

SAFETY-RELATED COMPONENTS.

DENNETT.T.J.

BRICHOUX,J.

i NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH NUREG/CR-5758 V00: FITNESS FOR DUTY IN THE NUCLEAR POWER NETWORK DETECTION CAPABluTIES Annual Report, July 1994 July INDUSTRY. Annual Summary Of Program Performance Reports CY 1995.

1995.

BERTODANO.M.L BRIDEAU,J.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE AUTOMATING ECCS SWITCHOVER AT PWRS.

SBWR, DHATTACHARVA,8.

BROADHEAD,8.L NUREG/CR 5442: RELIABluTY BASED CONDITION ASSESSMENT OF NUREG/CR4484: GUIDE TO VERIFICATION AND VALIDATION OF STEEL CONTAINMENTS AND UNERS.

THE SCALE-4 RADIATION SHIELDING SOFTWARE.

BIERSCHBACH.M.C BROWN,K.D.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-FOR THE REFERENCE BOILING WATER REACTOR POWER RIALS LICENSING PROCESS REDESIGN.

STATION Effects Of Current Regulatory And Other Considerations On NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOUDAT.

The F6nancial Assurance Requirements Of The Deu..

v.,ng Rule ING AND UPDATING MATERIALS UCENSING GUIDANCE. Draft And....

Report For Comment.

NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING l

FOR THE

REFERENCE BOluNG WATER REACTOR POWER BRUMMETT,E.

j STATION. Effects Of Current Regulatory And Other Consideratens On NUREG-1532: DRAFT TECHNICAL EVALUATON REPORT FOR THE J

The Financial Assurance Requirements Of The Decommissionmg Rule PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-And....

PORATION MOAB MILLSource Maternal Ucense No. SUA-017, Docket NUREG/CR.6270: ESTIMATING BOlWNG WATER REACTOR DEN No. 40-3453.(Atlas Corporation)

MISSIONING COSTS.A User's Manual For The BWR Cost Estimating Computer Program (CECP) Software. Final Report.

BRUST,F.W.

NUREG/CR4440: THE EFFECTS OF CYCUC AND DYNAMIC LOADING BINDER.J.L ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING STEELS. Technical Report October 1992 April 1996.

LESSONS LEARNED (GALL) Main Report And Appendix A NUREG/CR4490 V02: NUCLEAR POWER PLANS GENERIC AGING NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY LESSONS LEARNED (GALL). Appendix B.

SURFACE. CRACKED EL50WS.

NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR BISHOP.J.V.

INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN NUREG/CR4494: CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI ELBOWS.

DECONTAMINATON.

BRYCE.J.H.

DITTNER,A.

NUREG/CR4314: OUAUTY ASSURANCE INSPECTONS FOR SHIP-NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

PING AND STORAGE CONTAINERS.

UPDATE OF THE TECHNICAL ISSUES 1996.

HARD,M.

BLAKEMAN,E D NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND RADIO-FREOUENCY INTERFERENCE LEVELS IN NUCLEAR POWER SAFETY TESTING.Techrucal Report On The Findinos Of Task 4 inves-PLANTS.

tigation of Falled Nrtnol Brachytherapy Wire.

BLASING,T.J.

BURKE,W.F.

NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE COMMISSIONING OF THE SHIELDALLOY METALLURGICAL TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS CORPORATON. CAMBRIDGE,OHlO. FACluTY. Docket No. 404948,U.

STEEL PIPE WELDS.

conse No. SMB-1507.

BURSON,S.B.

BLASING,T.S-NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-NATURAL PROCESSES IN REACTOR CONTAINMENTS.

ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE ATLAS SITE,MOAB, UTAH. Source Maternal Ucense No. SUA-CAMPBELL,J.A.

917, Docket No. 40-3453. (Attes Corporation)

NUREG/CR4124: CHARACTER 12ATON OF RADIONUCLlDE.CHELAT-ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE.

CONTAWNATON WASTE. uerature RW NU E'G/CR4350: A TECHNIOUE FOR HUMAN ERROR ANALYSIS (ATHEANA). Technical Base And Methodology Descnption.

CANTRELL,K.J.

BOHLANDER.K.L NUREG/CR4124: CHARACTERIZATION OF RADIONUCUDE CHELAT.

NUREG/CR 5:173 R03: CODES AND STANDARDS AND OTHER GUID.

ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE.

ANCE CITED IN REGULATORY DOCUMENTS.

CONTAMINATON WASTE. Uterature Review.

BOLTON H.

CAPUN.J.

NUREG/CR4124: CHARACTERIZATON OF RADIONUCUDE-CHELAT-NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED CONTAMINATION WASTE. Literatura Review.

DOCUMENTS.

Personal Author Index 41 COumS.D.J.

CARooNARO.J.

NUREG/CR4384 V02-UTERATURE REVIEW OF ENVIRONMENTAL NUREG-1556 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE.

OUAUFICATION OF SAFETY RELATED ELECTRIC CABLES.Lhereture RlALS UCENSES. Program-Spectlic Guusance About Portable Gauge Ucenses. Draft Report For Comment.

Analyms And Appendices CAREW,Jr.

COuES,L NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

CARFAGO.S.

NUREG/CR-6384 V02: UTERATURE REVIEW OF ENVIRONMENTAL CONGEL,F.

OUALIFICATION OF SAFETY RELATED ELECTRIC CABLES.uterature NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL-Analyse And Appendicos.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER CARUNJ PLANTS.Crttena For Protective Action Rm amendations For Severe NUREG/CR4202: LONG-TERM AGING AND LOSS-OF COOLANT AC.

Accidents. Draft Report For CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./ French Co.

operatNo Reneerch Program.

CONNERY,SA NUREG-1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR 1995.

CARLSON,R.W.

NUREG/CR4467: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES USED TO TRANSPORT VARIOUS CONTENTS.

EG CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-CROPARTICULATES IN THE FACIUTATED TRANSPORT OF RA-CARROLL.D.P.

NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-DIONUCUDES.

VICES IN NUCLEAR POWER PLANTS.

COOPER,LY.

NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

CARSTEN.A.L NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-UVES FOR RA-ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING DIOLABELED ANTIBODIES AND RL.ATED ISSUES.

THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER PLANT APPLICATONS.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING COOPER S.E.

LESSONS LEARNED (GALL). Main R And Apperds A.

NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR4490 V02: NUCLEAR ER PLANI GENERIC AGING (ATHEANA).Techrucal Basis And Methodology Desenption.

LESSONS LEARNED (GALL). Appendm B.

CORWIN,WA CHOi,YX NUREG/CR 5591 V06 N2: HEAVY SECTON STEEL IRRADIATION NUREG/CR4443: DETERMINISTIC AND PROBABluSTIC EVALUA-PROGRAMSenuannual Progress Report For April Through September TiONS FOR UNCERTAINTY IN PlPE FRACTURE PARAMETERS IN 1995.

LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATONS.

COWOILL.EG.

CHOPRA,0.K.

NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT NUREG 1557:

SUMMARY

OF TECHNICAL INFORMATION AND BROOKHAVEN NATIONAL LABORATORY, AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENOVAL CURTIS A.H.

NUREG/CR-4667 V20 ENVIRONMENTALLY ASSISTED CRAC!GNG IN NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-UGHT WATER REACTORS. Semiannual Report,0ctober 1994 March COMMISSIONING OF THE SHIELDALLOY METALLURGICAL NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN CORPORATION, CAMBRIDGE, OHIO, FACluTY. Docket No. 404948,U-1995.

UGHT WATER REACTORS. Semiannual Report. April 1995. December cense No. SMB-1507, 1995.

NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE CZAJKOWSKI,C.L TOUGHNESS AND CHARPY lMPACT STRENGTH OF STAINLESS NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT BROOKHAVEN NATIONAL LABORATORY.

STEEL PIPE WELDS.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING DAUNG,P.E LESSONS LEARNED (GALL). Main Report And Appendix A.

NUREG/CR4490 V02: NUCLEAR POWER PLANI GENERIC AGING NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT LESSONS LEARNED (GALL). Appendix B.

SAFETY ISSUE PRIORITIZATON INFORMATION DEVELOPMENT.

CHOWDHURY,A.H.

DARBY,J.

NUREG/CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-NUREG/CR4432 ESTIMATED NET VALUE AND UNCERTAINTY FOR ED ROCK MASS.

AUTOMATING ECCS SWITCHOVER AT PWRS.

CHUNG B.D-DAVIS,JI.

NUREG/lA-0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-MODEL AND UNCERTAINTY OUANTIFICATION OF REFLOOD PAK VICES IN NUCLEAR POWER PLANTS.

CLAD TEMPERATURE.

DE CACHARDf.

CHWG H.E NUREG/LA 0133: DEVELOPMENT,lMPLEMENTATION, AND ASSESS-NUREG/CR-4667 V20- ENVIRONMENTALLY ASSISTED CRACKING IN MENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-ANNULAR UGHT WATER REACTORS. Semiannual Report, October 1994 March FILM-BOlVNG IN A TWO-FLUID MODEL 1995.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN DE90RD.D.E.

UGHT WATER REACTORS. Semlannual Report. April 1995 December NUREG/CR4450: CHARACTERIZATON OF CONTAMINATION 1995.

THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESS:NG.

CHUNG,Y4 NUREG/lA 0131: ASSESSMENT OF RELAP5/ MOD 3 USING BETHSY DE 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST, NU

BRANCH TECHNICAL POSITION ON THE USE OF EXPERT EUCITATON IN THE HIGH-LEVEL RADIOACTIVE WASTE CLARK,R.L NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON PROGRAM.

MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.

NUREG/CR4422: POWER EXCURSON ANALYSIS FOR HIGH COKINOS D.E NUREG/CR4253: PlUS CORE PERFORMANCE ANALYSIS.

BURNUP CORES.

I

I l

i l

42 Personal Author index

)

D454AS40,A.

NUREG/CR4424. REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR REINFORCED CONCRETE STRUCTURES.

AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC.

NUREG/CR-6425: IMPACT OF STRUCTURAL AGING ON SEISMIC l

TONS.

RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUCLEAR POWER PLANTS.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING ELLIOT,8.J.

NU E CH 90 V U LEAR P NElilC AGING LESSONS LEARNED (GALL). Appendix B.

EMMETT,M.S.

l DIVADEENAM,M.

NUREG/CR4483: GUOE TO VERIFICATION AND VALIDATION OF l

NUREG/CR4492: BLT-MS (BREACH. LEACH, AND TRANSPORT-MUL-THE SCALE 4 CRITICALITY SAFETY SOFTWARE.

i TIPLE SPECIES) DATA INPUT GUOE.A Computer Model For Simulat-NUREG/CR4484: GUIDE TO VERIFICATON AND VALICATON OF ing Release Of Contaminant From Subsurface Low-Level Waste Dis-THE SCALE-4 RADIATION SHIELDING SOFTWARE.

poeal Facety.

EMRITA DOCTOR,S.R.

NUREG 0933 S20: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.

NUREG-0933 S21: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

NUREG/CR4344: REAL TIME 3-D SAFT-UT SYSTEM EVALUATION AND VAUDATION.

ERDEMIR,A.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING I

DDDD.C.V.

LESSONS LEARNED (GALL). Main Report And Appendix A.

NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITION NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

LESSONS LEARNED (GALL). Appendix B.

NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY.

CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-EWING,P.D.

i I

SPECTION.

NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR TUBING SAMPLES.

RADIO-FREOUENCY INTERFERENCE LEVELS IN NUCLEAR POWER PLANTS.

j DODDSAH.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT FADDEN,M.A.

EFFECTS ON BRITTLE FRACTURE IN SE(B) AND Cm SPECIMENS.

NUREG 0525 V02 R04: SAFEGUARDS

SUMMARY

EVENT LIST I

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT (SSEL). January 1,1990 Through December 31,1995.

1 LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

FELMY,A.R.

DOWLATIA NUREG/CR4124; CHARACTER 12ATON OF RADIONUCUDE CHELAT.

)

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE CONTAMINATON WASTE. Uteraturn Review.

SBWR.

1 FERRILL.D.A.

1 DUMBINA NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN I

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER REGION Critical Review And Analyses of Tectonic Data From The INDUSTRY. Annual Summary Of Program Performance Reports CY Central Basin And Range.

1995.

NUREG/CR4470; FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

FIELD,L UPDATE OF THE TECHNICAL ISSUES 1996.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

EASTERLY,C.E.

ATE & THE TECHNCAL ISSUES M96.

i NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

FISCHER,LE.

l ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES l

ATLAS SITE MOAB, UTAH. Source Matenal License No. SUA-USED TO TRANSPORT VARIOUS CONTENTS.

N G

3:

EN RON PACT STATEMENT DE.

NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST COMMISSONING OF THE SHIELDALLOY METALLURGICAL FAILURE BY BRITTLE FRACTURE. Category ll And til Femtsc Steel l

CORPORATON. CAMBRIDGE, OHIO, FACIUTY. Docket No. 40-8948,U-Shipping Containers With Wall Thickness Greater Than Four Inches.

I conee No. SMB-1507.

FLEMING,M.

]

EDDELMON.G.K.

NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

SURFACE CRACKED ELBOWS.

ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE URE 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

917 ktN 0 34 tlas AL lbPACT STATEMENT DE.

ED TO RECLAMATION OF THE URANIUM MILL TAluNG'. AT THE a

NUREG-1543: DRAFT ENV!RON COMMISSONING OF THE SHIELDALLOY METALLURGICAL ATLAS SITE,MOAB, UTAH. Source Material Ucense No. SUA-CORPORATION. CAMBRIDGE, OHIO, FACILITY. Docket No. 40-8948,U.

917. Docket No. 40-3453. (Atlas Corporation) conee No. SMB 1507.

NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE

/

PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-ED00N J.L.

PORATON MOAB MILL. Source Material Ucense No. SUA-917, Docket NUREG/CR 5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN No. 40-345MAuss Corporation) i SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN FORSLUND,C.

SAFETY-RELATED COMPONENTS.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING UPDATE OF THE TECHNICAL ISSUES 1996.

LESSONS LEARNED (GALL). Main Report And ex A.

NUREG/CR4490 V02: NUCLEAR POWER P GENERIC AGING FOX,E.F.

LESSONS LEARNED (GALL). Appendix B.

NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-d EISEMBERGAA.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG 1563: BRANCH TECHNICAL POSITON ON THE USE OF PREPAREDNESS IN SUPPORT OF NUCLEAR POWER EXPERT EUC!TATION IN THE HIGH-LEVEL RADIOACTIVE WASTE PLANTS.Critena For Emergency Planning in An Early Site Permit PROGRAM.

Application. Draft Report For Comment

/

ELLINGWOOD,B.R.

FRANZ,E.M.

NUREG/CR4442: RELIABluTY BASED CONDITION ASSESSMENT OF NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT STEEL CONTAINMENTS AND UNCRS.

BROOKHAVEN NATIONAL LABORATORY.

i I

Personal Author index 43 PREDRfCM90N.J.K ORANT.T.

NUREG/CR4124: CHARACTERIZATION OF RADIONUCLIOE CHELAT-NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

ING AGENT COMPLEXES FOUND IN LOW LEVEL RADIOACTIVE DE-UPDATE OF THE TECHNICAL ISSUES 1996.

CONTAMINATION WASTE. Uterature Rev6ew.

GREEN,W.

nas amas a u NUREG/CR-6463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES NUREG/lA 0135: POST TEST ANALYSIS OF PIPER ONE PO-C-2 EX-FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final PERIMENT BY RELAP5/ MOD 3 CODES.

Report.

GALVIN,T.M.

GRODIN,M NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE NUREGd415 V08 N02-OFFCE OF THE INSPECTOR SS A CHARPY lMPACT STRENGTH OF STAINLESS GENERALSemiennual Report To Congrees October 1,1995 - March 31.1996.

NUREG 1415 V09 N01: OFFICE OF THE INSPECTOR SAMBERONI,D.

NUMEG 1214 R14: HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

GENERALSermannual Report To Congrees, April 1,1996 September C ASSESSMENT OF UCENSEE PERFORMANCE.

30,1996.

i GARVER M.

GROVE,E.

NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION INFORMA.

NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR TlON DIGEST,1996 Edition.

AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-TIONS.

GAUSSENS,0.

NUREG/CR4202: LONG TERM AGING AND LOSS OF-COOLANT AC.

ONUSER,E.E.

CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./ French Co-NUREG/CR-4667 V21: ENVIRONMENTALLY ASS 6STED CRACKING IN operative Research Program.

UGHT WATER REACTORS. Sermannual Report, April 1995 - December 1995.

GAUTHIER G.

NUREG/CR4202: LONG-TERM AGING AND LOSS-OF COOLANT AC-OUARRO.S.

CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./ French Co.

NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS operative Research Program-OF CONTROL SOFTWARE IN ADVANCED REACTORS.

I GAVENDA,D.J.

GUTTMANN,H.

NUREG/CR-4667 V20 ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR LIGHT WATER REACTORS. Semiannual Report, October 1994 - March AUTOMATING ECCS SWITCHOVER AT PWRS.

1995.

NOREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE GUZMEG.

TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL STEEL PIPE WELDS.

EXPERIMENTS.Resulte And Leesons Learned.

NUREG/CR4360:

SUMMARY

OF AIR PERMEABluTY DATA FROM asnnsa a u SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREG/CR4360:

SUMMARY

OF AIR PERMEABluTY DATA FROM SINGLE HOLE INJECTION TESTS IN UNSATURATED FRACTURED TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF STEADY-STATE TEST INTERPRETATION.

NUREG/CR 6457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE STEADY-STATE TEST INTERPRETATION.

NUREG/CR4457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE TUFF CORES USING A GAS PYCNOMETEH.

TUFF CORES USING A GAS PYCNOMETER.

g,,

GEE,0,W.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Ml.

NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED DIONUCUDES.

ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-POSAL SITES.

HACKETT,E M.

NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT.

OHADIAU,N.

NUREG/CR4443: DETERMINISTC AND PROBABluSTC EVALUA-HAFFNER,D.R.

TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN NUREG/CR4280: TECHNOLOGY, SAFETY.AND COSTS OF DECOM-LEAK BEFORE BREAK AND IN-SERVICE FLAW EVALUATIONS.

MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-NUREG/CR4444 FRACTURE BEHAVIOR OF CIRCUMFERENTIAU.Y ENCE SEALED SOURCES.

SURFACE CRACKED ELBOWS.

NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR HAGAN,C.W.

)

INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

ELBOWS COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION, CAMBRIDGE,OHlo, FACluTY.Ducket No. 40-8948,U-cenee No. SW 507.

)

E /CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-ED ROCK MASS.

HAGEMEYEd,D.

NUREG-0713 V16: OCCUPATIONAL RADIATCN EXPOSURE AT COM-ONISSERG,T.

MERICAL NUCLEAR POWER REACTORS AND OTHER NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE FACILITIES.1994. Twenty Seventh Annual Report.

CURRENT UNDERSTANDING OF BROADER FUEL COOLANT b'***

N RE /CR4344: REAL. TIME 3-D SAFT-UT SYSTEM EVALUATION g

w AND VAUDATION.

as yannet,J.

00 FICA ION OF ETY LATED ELECT C LE er tur R

CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-ACTIVE WASTE. Final Report I

Analyse And Appendices..

ORAFF,S.

HAN,J.T.

NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERS11Y FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final MULTl-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE Report.

SBWR.

)

l 44 Personal Author Index HARRIS,R.V.

HSIUNG,8.M.

NUREG/CR-5965 S01: REVIEW OF P-SCAN COMPUTER. BASED UL-NUREG/CR4366: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT.

TRASONIC INSERVICE INSPECTION SYSTEM.

ED ROCK MASS.

\\

HART =LD.R A.

Hu.ER,o.

NUREG-0020 V20 UCENSED OPERATING REACTORS STATUS SUM-NUREG 1415 V06 NO2: OFFICE OF THE INSPECTOR MARY REPORT. Data As Of Decernber 31,1995.(Gray Book 1)

GENERALSermannual Report To Congress October 1,1995 - March HARTLEY,RA 31 1996 NUREG/CR4396: EXAMPLES, CLARIFICATIONS, AND GUIDANCE ON NUREG.1415 V09 Not-OFFICE OF THE INSPECTOR PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-GENERALSermannual Report To Congrees. April 1,1996 September SERVICE TESTING REQUIREMENTS.

30,1996' HARTWIG P.G.

NUREG/CR-6429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-NUREG'/CR4500: OWNERS OF NUCLEAR POWER PLANTS.

CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA.

j DIONUCUDES.

HUGHESJX i

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN HAUTH,J.

UGHT WATER REACTORS. Sermannual Report, April 1995 - December NUREG/CR4470; FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY; N

UPDATE OF THE TECHNICAL ISSUES 1996.

HulJ.E.

psaas on,p,G, NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.

l NUREG/CR-5066: PIPING INSPECTION ROUND ROBIN.

CUDE BURDENS TO PRENATAL RADIATION DOSES.

NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR i

EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.

19RAHIM,A.

I NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE HECHT H.

PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR.

)

l NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES PORATION MOAB MILLSource Material Ucense No. SUA-917, Docket FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final No. 40 3453.(Atlas Corporation)

ISHil,M.

HECHT,M.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG/CR4463; REVIEW GUIDEUNES ON SOFTWARE LANGUAGES MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE l

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final SBWR.

Report HENDERSON,DA JASTROW,J.D.

NUREG/CR-5229 V06: FIELD LYSIMETER INVESTIGATIONS: LOW-l NUREG/CR-6401: FAULTING IN THE YUCCA MOUNTAIN LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR REGION. Critical Review And Analyses of Tectome Data From The Central Basm And Range.

FISCAL YEAR 1995. Annual Report.

l NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NRG 4 360:

SUMMARY

OF AIR PERMEABILITY DATA FROM TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED JEONG,J4 TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF STEADY-STATE TEST INTERPRETATION.

NUREG/lA-0131: ASSESSMENT OF RELAPS/ MOD 3 USING BETHSY 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST, HEPLER,M.

JESSOP,B R I

NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL-UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON BREATH-ING-ZONE AND AREA AIR SAMPLES.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS. Criteria For Protecttve Action Recornmendatione For Severe JOHNSON.R.E.

Accidents. Draft Report For-NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE HILLS,R.G.

VESSEL SUPPORTS.

NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA*

TION SOLVER.

JOHNSON.R.0, NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-HILTON,LD.

ED TO RECLAMATION OF THE URA*'UM MILL TAluNGS AT THE NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW.

ATLAS SITE,MOAB, UTAH. Source daterlal Ucense No. SUA.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER 917, Docket No. 40-3453. (Anas Corporation) t TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

JOHNSONJ, Hites,A.G.

NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE NUREG/CR-4667 V20 ENVIRONMENTALLY ASSISTED CRACKING IN PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-UGHT WATER REACTORS. Sarmannual Report. October 1994 March PORATION MOAB MILLSource Matenal Ucense No. SUA 917, Docket i

1995.

Nc. 40-3453.(Atlas Corporation)

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN UG T WATER REACTORS. Sermannual Report, April 1995 December D

THE SCALE 4 CRITICALITY SAFETY SOFTWARE.

HOFMANN,LL NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE JOY,DA MONITORING AND FIELD STUDIES.

NUREG-0430 V15: UCENSED FUEL FACluTY STATUS REPORT. inventory Difference Data. July 1,1994 - June 30,1995.(Gray HOLLAND,J.W.

Book 11).

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING i

LESSONS LEARNED (GALL). Main Report And Appendix A.

JDYCE.J.A-t NUREG/CR4490 V02: NUCLEAR POWER PLAm GENERIC AGING NUREG/CR4279: APPUCATION OF FRACTURE TOUGHNESS SCAL-(

LESSONS LEARNED (GALL). Appendix B.

ING MODELS TO THE DUCTILE.TO-BRITTLE TRANSITION.

HOPPER A.

JUSTUS.P.

l NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE SURFACE. CRACKED ELBOWS.

PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-i t

Personal Author Index 45 PORATION MOAB MILLSource Material License No. SUA-917, Docket NUREG/lA4134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY.

No. 40-3453.(Atlas Corporat on)

DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF i

THE CARR PASSIVE REACTOR (CP-1300).

J WTM NUREG 0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-KIMME 8 UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER UPDATE OF THE TECHNICAL ISSUES 1996' PLANTS.Crtteria For Emergency Piarnno in An Early Site Permit NU 0654

. CR R F'OR PREPARATION AND EVAL-UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-PREPAREDNESS IN SUPPORT OF NUCLEAR POWER CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-PLANTS.Crttene For Protective Action Recommendations For Severe DIONUCLlDES.

Accidents. Draft Report For.

KINSEY,R.R.

KANUKOVA,V.

NUREG/CR-6492: BLT MS (BREACH, LEACH, AND TRANSPORT MUL-NUREG/lA-0129 P01: AM ASSESSMENT OF THE CORCON-MOD 3 TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Sanulat-CODE.Part 1: Thermal-Hydraulic Calculations.

ing Release Of Contaminant From Subsurface Low Level Waste Dis-p sal Facility.

KASSNEST.F.

NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN KLAMERUS.E.W.

LIGHT WATER REACTORS. Semiannual Report. October 1994 March NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG/CR 4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE LIGHT WATER REACTORS. Semiannual Report, April 1995. December DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS 1995 NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN KNOODSMA,R.L S.MULATED LWR ENVIRONMENTS.

NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE KASTUR1,$.

ATLAS SITE,MOAB UTAH. Source Material Lscense No. SUA-NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL 917, Docket No. 40 3453. (Atlas Corporabon)

OUALIFICATION OF SAFETY RELATED ELECTHIC CABLES. Literature Analysis And Appendices.

KOCH,5.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMSFinal CR4490 V01: NUCLEAR POWER PUNT GENERIC AGING Repod LESSONS LEARNED (GALL). Main Report And AJpendix A.

NUREG/CR4490 V02: NUCLEAR POWER PLANI GENERIC AGING LESSONS LEARNED (GALL). Appendix B.

EG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH KAURIN.D.G.

BURNUP CORES.

NUREG/CR-6374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR RA.

DIOLABELED ANTIBODIES AND RELATED ISSUES.

MONZEK,G.J.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING KAVANAUGH.D.C.

FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-STATION. Effects Of Current Regulatory And Other Considerations On CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT The Financia; Assurance Requirements Of The Co.....

ang Rule OPERATIONS AND MAINTENANCE COSTS.

And-KEENEY,J.

NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISS:WNG NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF FOR THE REFERENCE BOILING WATER REACTOR POWER LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL.

STATION. Effects Of Current Regulatory And Other Consideratsons On SIRE 11).

The Financial Assurance Requirements Of The Decommissioning Rule And..

KENNEDY,J.E.

NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-KORSAH,K.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL NUREG/CR4408: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL CORPORATION.CAMORiDGE. OHIO, FACILITY. Docket No. 404948.Li-DIGITAL SAFETY CHANNEL conse No. SMB-1507.

KOTRA.J.P.

KERCEL,5.W.

NUPEG 1563: BRANCH TECHNICAL POSITION ON THE USE OF NUREG/CR-6436: SURVEY OF AMBIENT ELECTROM&GNEfiO AND EXPERT ELICITATION IN THE HIGH-LEVEL RADIOACTIVE WASTE i

RADIO. FREQUENCY INTERFERENCE LEVELS IN NUCLEAR PO NER PROGRAM.

PLANTS.

KOTTLE,S.

KlWNSKI,T.

NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY NUREG/CR4494: COfCNUOUS ANALYSIS FOR VANADIUM IN LOMI SURFACE-CRACKED ELBOWS.

DECONTAMINATION.

KILLEY,W.D.

KRUPKA,K.M.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Ml-NUREG/CR-6124: CHAAACTER12ATION OF RADIONUCLIDE-CHELAT-CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-ING AGENT CCMPLEXES FOUND IN LOW LEVEL RADIOACTIVE DE.

DIONUCLIDES.

CONTAMINATION WASTE. Uterature Review.

j KIM,D 8-KUO P.T.

f NUREG/lA 0131: ASSESSMENT OF RELAP5/ MOD 3 USING BETHSY NUREG 1568: LICENSE RENEWAL DEMONSTRATION PROGRAM-.

6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

NRC OBSERVATIONS AND LESSONS LEARNED.

KIM H.J'G/lA4130 ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF NZ,RA NURE SS-SG-06 EXPER! MENT SIMULATING A STEAM GENERATOR TUBE NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR j

RUPTURE TRANSIENT.

EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.

NUREG/lA 0131: ASSESSMENT OF RELAPS/ MOD 3 USING BETHSY 6.2TC 6-INCH COLD LEG SIDE BREAK.C.T. APARATIVE TEST.

LARSON,l.L NUREG/lA-0132: IMPROVEME.NTS TO THE hC. LAPS / MOD 3 REFLOOD NUREG/CR4229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.

MODEL AND UNCERTAINTY OUANT,FICATION OF REFLOOD PAK LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FO.R CLAD TEMPERATURE.

FISCAL YEAR 1995. Annual Report.

7

.[

d

46 Personal Author index LAYENDER J.C.

LOFAROA NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT NUREG/CR-6384 V02: LITERATURE REVIEW OF ENVIRONMENTAL SAFETY ISSUE PRORITIZATION INFORMATION DEVELOPMENT.

QUALIFICATON OF SAFETY-RELATED ELECTRIC CABLES.uterature LAWRENCE,J.D.

NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.

LOPEZ,5.

NUREG/CR-5595 R01: FORECAST: REGULATORY EFFECTS COST LAYTON,M.

ANALYSIS SOFTWARE MANUAL Vernon 4.1.

NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR.

LUCKAS,W.J.

PORATON MOAB MILL. Source Matenal Ucense No. SUA-917, Docket NUREG/CR4350 A TECHNIQUE FOR HUMAN ERROR ANALYSIS No. 40-3453.(Atlas Corporation)

(ATHEANA). Technical Basis And Methodology Desenpton.

LEE.A.D.

MA,D.C.

NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT.

NUREG 1557:

SUMMARY

OF TECHNICAL INFORMt TON AND AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES LEE.5-COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENEWAL NUREG/CR4384 V02: U"RATURE REVIEW OF ENVIRONMENTAL NUREG/CR 6490 V01: NUCLEAR POWER PLANT GENERIC AGING QUAUFICATION OF SA iTY-RELATED ELECTRIC CABLES.uterature LESSONS LEARNED (GALL). Main Report And Appendix A.

Analysis And Appendics,,

NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING LESSONS LEARNED (GALL). Appendix 8.

LEE.B.S.

NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR MACAULAY,J.

AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC.

NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

TlONS.

UPDATE OF THE TECHNICAL ISSUES 1996.

LEE M.P.

MACDONALD,P.E.

NUREG 1563: BRANCH TECHNICAL POSITON ON THE USE OF NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN EXPERT EUCITATION IN THE HIGH-LEVEL RADIOACTIVE WASTE SAFETY-RELATED COMoONENTS.

PROGRAM.

MACKINNONAJ.

ME.S.

NUREG/CR4492: BLT-MS (BREACH, LEACH, AND TRANSPORT-MUL-NUREG-1557:

SUMMARY

OF TECHNICAL INFORMATION AND TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat.

AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES ing Release Of Contaminant From Subsurface Low-Level Waste Dis-COUNCIL INDUSTRY REPORTS ADDRESSING UCENSE RENEWAL NUREG/lA 0130: ASSESSMENT OF RELAPS/ MOD 3.1 WITH THE LSTF posalFac W SB SG 06 EXPERIMENT SIMULATING A STEAM GENERATOR TUBE MADERA J.R.

NURE / A 134 A MENT OF RELAP5/ MOD 3.1 FOR GRAVITY' RlA L NS G SS R SIG '

1 DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF j

THE CARR PASSIVE REACTOR (CP 1300)-

MAGLEBY,H.L.

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN NUR G/lA 0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD MCDEL AND UNCERTAINTY QUANTIFICATION OF REFLOOD PAK MAT 8ON,E.R.

CLAD TEMPERATURE.

NUREG-1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-RIALS UCENSES.PrograrrhSpecrhc Guidance About Portable Gauge UAE'G/lA-0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD MODEL AND UNCERTAINTY QUANTIFICATION OF RLFLOOD PAK MATTIE,J.F.

CLAD TEMPERATURE.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA.

MMUREA DIONUCUDES.

NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER-MALLY STRIPED PIPE FLOWS.

MATZNERA NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-MPEL,E.A.

CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-DIONUCUDES.

CROPARTICULATES IN THE FACIUTATED TRANSPORT OF RA.

DIONUCUDES.

MAZZINI.M.

NUREG/lA-0135: POST. TEST ANALYSIS OF PIPER ONE PO IC 2 EX-LETUTOUR P.

PERIMENT BY RELAP5/ MOD 3 CODES.

NUREG/CR4202: LONG-TERM AGING AND LOSS OF COOLANT AC-CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U SJFrench Co.

MCCOLD,LN.

operative Research Program.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

COMMISSONING OF THE SHIELDALLOY METALLURGICAL LEWIS,S.W.

CORPORATION. CAMBRIDGE. OHIO, FACILITY. Docket No. 40-8948,U-NUREG-1556 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE-conse No. SMB 1507.

RIALS LICENSES. Program-Specific Gu6 dance About Portable Gauge Licenses. Draft Report For Comment.

MCCONNELL,J.W.

NUREG/CR-5229 V08. FIELD LYSIMETER INVESTIGATIONS: LOW-LIN.D.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES FISCAL YEAR 1995. Annual Report.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-Report.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

LINKAE.

NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL.

ACTIVE WASTEFinal Report.

ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.

NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.

LIPINSKIAE.

NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-VESSEL SUPPORTS.

CORDING TO IMPORTANCE TO SAFETY.

Personal Author inder 47 l

MCoOwEu.,s.L MONROE Wx NUREG/CR4419: SOLUB'LITY TESTING OF ACTINIDES ON BREATH-NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-i ING-ZONE AND AREA AIR SAMPLES.

CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT OPERATIONS AND MAINTENANCE COSTS.

MCOUFFIE P.N.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING MONTELEONE.8.

FOR THE REFERENCE BOluNG WATER REACTOR POWER NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY THIRD STATION. Effects Of Current Regulatory And Other Conaderations On WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-The Financial Assurance Requiremente Of The Decomamessorung Rule aion, Hg' h Bumup Fuel Behavior, Thermal Hydraulic Research.

7 l

And..

NUREG/GP-0149 V02-PROCEEDINGS OF THE TWENTY. THIRD NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING WATER REACTOR SAFETY INFORMATION MEETING. Human Factors FOR THE REFERENCE BOILING WATER REACTOR POWER Research, Advanced 14C Hardware & Software, Severe Accident Re-STATION.Effecte Of Current Regulatory Ano Other Considerations On eserch, Probabilistic Reek Aseseement Topice, indMdual Plant Examine-l The Financ6al Assurance Requirements Of The Decomfruemoning Rule tion.

And....

NUREG/CP 0149 V03: PROCEEDINGS OF THE TWENTY. THIRD WATER REACTOR SAFETY INFORMATION MEETING. Structural &

MCOUIRE,RL Seierme Engineering. Primary Systems Integrity, Equipment Operetnllty NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-And A96ng. ECCS Strainer Blockage Research & Regulatory leeues.

TION ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES-l TIMATES.

MOORE,C.

I NUREG/CR4470 FITNESS FOR DUT( IN THE NUCLEAR INDUSTRY:

l MCMENNA.T.

UPDATE OF THE TECHNICAL ISSUES 1996.

l NUREG.0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL.

UATION OF RADtOLOGICAL EMERGENCY RESPONSE PLANS AND MOORE,M.R.

j PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND PLANTS.Cnterla For Protectrve Action Recommendatione For Severo RADIO. FREQUENCY INTERFERENCE LEVELS IN NUCLEAR POWER Accidente. Draft Report For..

PLANTS.

MCLAUGHLIN,K.L MOORE.R.L NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH NUREG/CR-5535 V07 R1: RELAPS/ MOD 3 CODE MANUALSummaries NETWORK DETECTION CAPABluTIES. Annual Repart. July 1994 July And Reviewe Of Independent Code Aseseement Reports.

1995.

MOR8 ARTY,M.

MCNUTT.WE.

NUREG.1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE.

NUREG-0654 R1 S2 DFC' CRITERIA FOR PREPARATION AND EVAL.

RIALS LICENSING PROCESS REDESIGN.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER MORIN,C.

PLANTS.Crtterte For Emergency Planning in An Earty Site Permit NUREG/CR4202: LONG TERM AGING AND LOSS-OF COOLANT AC-Application. Draft Report For Comment.

CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./ French Co.

operathre Research Program.

NUREG 1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT, MORRISAP.

NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN METZGERAL REGION.Cattical Review And Analyses of Tecton6c Data From The NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH-Central Basin And Range.

ING. ZONE AND AREA AIR SAMPLES.

MOTAMEO,M.

MEYER LC.

NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING OF CONTROL SOFTWARE IN ADVANCED REACTORS.

LESSONS LEARNED (GALL). Man Report And Appendix A.

NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING MULLINSAT, LESSONS LEARNED (GALL). Appendix B.

NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

ED TO RECLAMATION OF THE URANIUM MILL TAlWNGS AT THE MEYER P.D.

ATLAS SITE.MOAB, UTAH. Soura Material Ucense No. SUA-NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR 917, Docket No. 40 3453. (Atlas Corporation)

ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED i

ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-MUSIL,S.A.

POSAL SITES.

NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-MONITORING AND FIELD STUDIES.

TION SOLVER.

NAUS,0.J.

MEZNARICH,HL NUREG/CR4424; REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-REINFORCED CONCRETE STRUCTURES.

CLtDE BURDENS TO PRENATAL RAD lATION DOSES.

NEILSON,R.M.

MICHAUD,WJ.

NUREG/CR.6256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR4426. EFFECTS OF THERMAL AGING ON FRACTURE LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TOUGHNESS AND CHARPY.lMPACT STRENGTH OF STAINLESS TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

STEEL PIPE WELDS.

NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.

MOHANA NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY NELSON,Cf.

SURFACE. CRACKED ELBOWS.

NUREG/CR.6202: LONG. TERM AGING AND LOSS-OF-COOLANT AC-NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S1 French Co-INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN operative Research Program.

ELBOWS.

NEUMAN,S.P.

MOHeE9N.A.

NUREG/CR-6096:

APACHE LEAP TUFF INTRAVAL NUREG.0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL-EXPERIMENTS.Resulte And Leesons Leemed.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND s

1 PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NEVALAINEN,M.

PLANTS. Criteria For Protective Action Recommendations For Severe NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT Accidents. Draft Report For EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

1

48 Personal Author Index NEWSERRY,S.F.

NUREG/CR4219 V12 N' HEAVY-SECTION STEEL TECHNOLOGY NUREG-1568; LICENSE RENEWAL DEMONSTRATION PROGRAM:

PROGRAM.Sernsannual mgress Report For October 1994 - March NRC OBSERVATIONS AND LESSONS LEARNED.

1995.

NEYMOTIN L PETRICH,C.H.

NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

BURNUP CORES.

ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE,MOAB. UTAH. Source Material Ucense No. SUA-NICHOLS,W~E.

917, Docket No. 40-3453. (Atlas Corporation)

NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED PILCH.M.M.

ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WASTE DIS-NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT POSAL SITES.

HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

NICHOLSON,T.J.

NUREG/CR4462: FIE!D TESTING PLAN FOR UNSATURATED ZONE POKHARNA H.

MONITORING ANO FIELD STUDIES.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NICKOLAUS,J.R.

MULTI-DtMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID.

S8WR.

ANCE CITED IN REGULATORY DOCUMENTS.

MIKULSHIN,V.

NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG/lA4129 P01: AN ASSESSMENT OF THE CORCON. MOD 3 NATURAL PROCESSES IN REACTOR CONTAINMENTS.

CODE.Part 1: Thermal-Hydraulic Calculatons.

PRATO,R.J.

NO,H.C.

NUREG-1568: LICENSE RENEWAL DEMONSTRATION PROGRAM:

NUREG/lA 0134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY-NRC OBSERVATIONS AND LESSONS LEARNED.

DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF THE CARR PASSIVE REACTOR (CP 1300).

PRATT,S.L.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-NOWLEN.S.P.

CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-NUREG/CR4476: CIRCulT BRIDGING OF COMPONENTS BY SMOKE.

DIONUCLIDES.

@ONNELL,E.

PRECKSHOT,0.G.

NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO NUREG/CR4421: A PROPOSED AC~,EPTANCE PROCESS FOR COM-NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Fiskt Ex-MERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPLl-pertments At A Humed Region S te.Beltsville. Maryland.

CATIONS.

OLAND,C.B.

RE NFORC NCR TE TR R.

CR4253: PIUS CORE PERFORMANCE ANALYSIS.

OLSON,R.

PUGH.C.E.

NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' MEET-ROUND-ROBIN ANALYSES.

ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC ASTM Headquarters, PNiedelpNa, Pennsylvania, May 2-3,1995.

FORCING FUNCTION.

NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL.

SURFACE CRACKED ELBOWS.

SIRE II).

OLVERA J.R.

RAHMAN,S.

NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER-NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 MALLY STRIPED PIPE FLOWS.

ROUND-ROBIN ANALYSES.

NUREG/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA-ORlANS,C.

TiONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

LEAK-BEFORE-BREAK AND IN SERVICE FLAW EVALUATIONS.

UPDATE OF THE TECHNICAL ISSUES 1996.

RAMEY-SMITH,A.

PAGE.G.

NUREG/CR4350:' A TECHNIQUE FOR HUMAN ERROR ANALYSIS i

NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON (ATHEANA). Technical Basis And Methodology Description.

RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED j

DOCUMENTS.

RANNEY,S.J.

l NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' MEET-ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At NU IA-0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD MODEL AND UNCERTAINTY OUANTIFICATION OF REFLOOD PAK ASTM Headquarters, PhiladelpNa, Pennsylvania, May 2-3,1995.

]

CLAD TEMPERATURE.

RANSOM,C.B.

WUREG/CR4396: EXAMPLES. CLARIFICATIONS, AND GUIDANCE ON PARRYG.W NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS PREPARING REQUESTS FOR REUEF FROM PUMP AND VALVE IN-SERVICE TESTING REQUIREMENTS.

(ATHEANA). Technical Basie And Methodology Description.

PATE,J.R.

RANSON,V.H.

NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITION NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY.

SBWR.

CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-SPECTION.

RAO.D.V.

NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-PELCHAT,J.M.

TRATION FOR LOCA DEBRIS.

NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE.

RIALS LICENSING PROCESS REDESIGN.

RASMUSSEN.T.C.

NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL PENNEL1,W.E.

EXPERIMENTS.Results And Lessons Learned.

NUREG/CR-4219 V11 N2: HEAVY SECTION STEEL TECHNOLOGY NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR j

PROGRAM. Semiannual Progress Report For April-September 1994.

APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

Personal Author Index 49 NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-RATH8UN,P.A.

NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-ACTIVE WASTE. Final Report.

RIALS UCENSING PROCESS REDESIGN.

NUREG 1541 DRFT FC: PROCESS AND DESIGN FOR CONSOUDAT-ROM,D.

ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE Report For Comment.

PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR.

PORATION MOA8 MILLSource Matenal Ucense No. SUA-917, Docket NU G 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-ED TO RECLAMATION OF THE URANIUM MILL TAIUNGS AT THE ROSENFIELD,A.

ATLAS SITE,MOAB, UTAH. Source Maternal Ucense No. SUA-NUREG/CR-6337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 917, Docket No. 40-3453. (Atlas Corporation)

ROUND-ROBIN ANALYSES.

REGAN.C"1557:

R M AND,E NUREG

SUMMARY

OF TECHNICAL INFORMATION AND NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON AGREEMENTS FROM NUCLEAR MANAGEIAENT AND RESOURCES B0 P E COUNCIL INDUSTRY REPORTS ADDRESSING UCENSE RENEWAL f

p ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING REID,LD.

NUREG/CR4344: REALTIME 3-D SAFT-UT SYSTEM EVALUATION STEELS.Techrncal ReportOctober 1992. April 1996.

AND VAUDATION.

NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY SURFACE-CRACKED ELBOWS.

REVANKAR,5.T.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY RUGGLES,AL MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR ~ ~

NUREG/GR4015: BULK TEMPERATURE MEASUREMENT IN THER-SBWR.

MALLY STRIPED PIPE FLOWS.

RHODES,C.R.

RUTHER,WE NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR NUREG/CR 4067 V20: ENVIRONMENTALLY ASSISTED CRACKING IN APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

UGHT WATER REACTORS. Serrgannual Report,0ctober 1994 March 1995.

R'HODES.S.C.

NUREG/CR-4067 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL UGHT WATER REACTORS. Sermannual Report, April 1995 December EXPERIMENTS.Results And Lessons Learned.

1995.

NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN RICE,P.M.

NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF SE.

SIMULATED LWR ENVIRONMENTS.

LECTED AEA/UCSB MODEL FECUMN ALLOYS.

SAMANTA,PX RIDKY,R.W.

NUREG/CR-6415: APPUCATIONS OF RELIABILITY DEGRADATION NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO ANALYSIS.

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-periments At A Humed Regon Site,Beltsv6lle, Maryland.

SANECKI,JL NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN

~

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-g['

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION. CAMBRIDGE, OHIO, FACluTY. Docket No. 40-8948,U-SANFORD,WE cense No. SMB 1507.

NOREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR 1

ROBERTSE W NUREG/CRd753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN FISCAL YEAR 1995. Annual Report.

NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-SAFETY SYSTEMS OF NUCLEAR POWER PLANTS' GENERIC AGING LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NUREG/CR4490 V01: NUCLEAR POWER PLANT TEST RESULTS FOR FISCAL YEARS 1994 AND 1995, LESSONS LEARNED (GALL). Man Report And Apperdx A.

NUREG/CR4490 V02: NUCLEAR POWER PLANI GENERIC AGING SANTIAGO.P.A.

LESSONS LEARNED (GALL). Apperdx B.

NUREG-1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-I ROBERTS,G.D.

RIALS LICENSES. Program Specific Guidance About Portable Gauge NUREG/CR4314: CUALITY ASSURANCE INSPECTIONS FOR SHIP-Ucenses. Draft Report For Comment.

l PING AND STORAGE CONTAINERS.

SCANLON.B.R.

l ROBERTSON,D.E.

NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR MONITORING AND FIELD STUDIES.

PART 61 AND OTHER SELECTED RADIONUCUDES.Uterature l

Reviet SCHEXNAYDER,S.M NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-NUREG 1543: ORAFT ENVIRONMENTAL IMPACT STATEMENT DE-l CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA-COMMISSIONING OF THE SHIELDALLOY METALLURGlCAL DIONUCLlDES.

CORPORATION. CAMBRIDGE. OHIO, FACILITY. Docket No. 40w8948,Li-conse No. SMB 1507.

ROCKHOLD,M.L I

NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR SCHu,A.A ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WASTE DIS-CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-l I

POSAL SITES.

l NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA.

DIONUCUDES.

SCHULTZ,R.R.

ROGERS,R.D.

NUREG/CR 5535 V07 R1: RELAP5/ MOD 3 CODE MANUAL.Summanes NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-And Reviews Of Independent Code Assessment Reports.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YEAR 1995. Annual Report.

SCHULZ,H.

NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER LARGE. SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

SIRE 11).

l

-. ~__.

50 Personal Author Index SCHUL 2,Rx.

SIEvERS,J.

NUREG/CR-4018 V09: CONTROL OF WATER INF;LTRATON INTO NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Flekt Ex-LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-l penments At A Hurnd Region Sate,Beltsville. Maryland.

SIRE II).

SCHUSTER,GJ.

SIKOV,M.R.

l NUREG/CR4344: REAL TIME 3-D SAFT-UT SYSTEM EVALUATION NUREG/CR 5631 R02: CONTRIBUTON OF MATERNAL RADIONU-AND VALIDATION.

CUDE BURDENS TO PRENATAL RADIATION DOSES.

(

SCHWARTZ,M.W.

SILSERNAGEL,M.

NUREG/CR4401: RECOMMENDATIONS FOR PROTECTING AGAINST NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER FAILURE BY BRITTLE FRACTURE. Category ll And 111 Femte Steel INDUSTRY. Annual Summary Of Program Performance Reports CY Shippmg Contamers With Wall Tivekness Greater Then Four inches.

1995.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

SCIACCA,F.

UPDATE OF THE TECHNICAL ISSUES 1996.

NUREG/CH4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

SLOAN,SM.

NUREG/CR-5535 V07 R1: RELAPS/ MOD 3 CODE MANUALSummanes SCIACCAf.W.

And Reviews Of Independent Code Assessment Reports.

NUREG/CR4595 RO1: FORECAST: REGULATORY EFFECTS COST ANALYSIS SOFTWARE MANUAL Version 4.1, SMITH,D.

l NUREG/CR4353: COMMENTS RECElVED ON PROPOSED RULE ON SCOTT,J.A.

RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED i

NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-DOCUMENTS.

MERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPU-CATONS.

SMITH,R.I.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING j

SCOTT,PM.

FOR THE REFERENCE BOluNG WATER REACTOR POWER NUREG/CR-6438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON STATION. Effects Of Current Regulatory And Other Considerations On CARBON STEEL PIPE.

The Financial Assurance Requirements Of The Decommissioning Rule NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC And....

FORCING FUNCTION.

NUREG/CR 6174 V02: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY FOR THE REFERENCE BOILING WATER REACTOR POWER SURFACE-CRACKED ELBOWS.

STATION Effects Of Current Regulatory And Other Considerations On SELCOW LC.

The Financial Assurance Requirements Of The Decommissioning Rule And._

NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

i SMOOT,J.L j

SERNE,RJ.

NUREG/CR.6411: A GEOSTATISTICAL METHODOLOGY TO ASSESS

(

NUREG/CR4124: CHARACTERIZATON OF RADIONUCLfDE CHELAT-THE ACCURACY OF UNSATURATED FLOW MODELS.

l (NG AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-1 CONTAMINATION WASTE. Uterature Review.

SONG,J.

I NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC l

l OEUL4W-RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN i

l NUREG/lA-0130 ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF NUCLEAR POWER PLANTS.

l SB-SG-06 EXPERIMENT SIMULATING A STEAM GENERATOR TUBE j

RUPTURE TRANSIENT.

SOPPET,W.K.

l NUREG/lA 0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN l

MODEL AND UNCERTAINTY OUANTIFICATON OF REFLOOD PAK LIGHT WATER REACTORS. Semiannual Report, October 1994 March i

CLAD TEMPERATURE.

1995.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN SEWELLAT.

UGHT WATER REACTORS. Semiannual Report. April 1995 December NUREG/CR4466: GROUND MOTION INPUT IN SElSMIC EVALUATION 1995.

STUDIES.lmpacts Of Artificial Time History input On in-Structure NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN Demand Spectra.

SIMULATED LWR ENVIRONMENTS.

NUREG/CR4467: IMPACT OF GROUND MOTON CHARACTERIZA-l TION ON CONSERVATISM AND VARIABluTY IN SEISMIC RISK ES-SOUTOfJ.

TIMATES.

NUREG/CR-6367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION TRATION FOR LOCA DEBRIS.

STUDIES,lmpacts On Risk Assessment Of Uniform Hazard Spectra.

NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

NUREG-1557:

SUMMARY

OF TECHNICAL INFORMATION AND SPlVEY,K.H.

AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENEWAL REGION Critral Review And Analyses of Tectonic Data From The NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN Central Basin And Range.

LIGHT WATER REACTORS, Semiannual Report. October 1994 - March 1995.

SPRUNG J.L NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4109: A SIMPUFIED MODEL OF AEROSOL REMOVAL BY UGHT WATER REACTORS. Semiannual Report, April 1995 - December NATURAL PROCESSES IN REACTOR CONTAINMENTS.

1995 NUREG/CR4400 V01: NUCLEAR POWER PLANT GENERIC AGING STASIN,M.G.

LESSONS LEARNED (GALL). Main Report And Appendix A.

NUREG/CR.6345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING MACEUTICALS.

LESSONS LEARNED (GALL). Appendix B.

STAGE,S.A.

SHAH,V.N.

NUREG/CR4210: COMPUTER CODES FCQ EVALUATION OF CON-NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

TROL ROOM HABITABluTY (HABIT).

SHONKA.JJ.

STAMATAKOS,J.

NUREG/CR4450- CHARACTERIZATION OF CONTAMINATION NUREG/CR4401: FAULTING IN THE VUCCA MOUNTAIN THROUGH THE USE OF POSITON SENSITIVE DETECTORS AND REGION Crttical Review And Analyses of Tectonc Data From The 4

DIGITAL IMAGE PROCESSING.

Central Basin And Range.

PCrsonal Author index 51 STAUS.W.P.

TAM,P.S.

NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-NUREG.0847 S20: SAFETY EVALUATION REPORT RELATED TO THE ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND ATLAS SITE.MOAB, UTAH. Source Matertal Ucense No. SUA-

2. Docket Nos. 50-390 And 50 391.(Tennessee Valley Authority) 917, Docket No. 40-3453. (Atlas Corporation) i TAN,C.P.

i STECKLER,K.D.

NUREG 1540: BWR STEEL CONTAINMENT CORROSION NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT-ING ALTERNATIVE TEMPERATURE-TIME CURVE FOR TESTING TANAKA,TJ.

THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL PLANT APPUCATIONS.

DIGITAL SAFETY CHANNEL NUREG/CR4476: CIRCUlT BRIDGING OF COMPONENTS BY SMOKE.

gg NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN TANGAS.

REGION Crttical Review And Analyses of Tectonic Data From The NUREG/CR4484: GUIDE TO VERIFICATION AND VAUDATION OF Comral Beem And Range.

THE SCALE-4 RADIATION SHIELDING SOFTWARE.

STOLLER R.E TAYLOR,J.H.

NUREG/CR4332: MICROSTRUCTURAL CHARACTER 12ATION OF SE-NUREG/CR4350: A TECHNIQUE FOR HUMAN ETIROR ANALYSIS LECTED AEA/UCSB MODEL FECUMN ALLOYS.

(ATHEANA). Technical Basis And Methodology DescriptNm.

NUREG/CR-6384 V02 UTERATURE REVIEW OF ENVIRONMENTAL l

STONKUS,D.

NUREG/CR4384 V02: UTERATURE REVIEW OF ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES.uterature OUAUFICATION OF SAFETY-RELATED ELECTRIC CABLES.uterature Analysis And Appendices j

THAGGARD,M.

f NUR CR4494: CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI MISS N TH ELD M AL ICAL i

DECONTAMINATION.

CORPORATION. CAMBRIDGE, OHIO, FACIUTY. Docket No. 40-8948 U-1 conee No. SMB-1507.

STRANGE,W.E.

i NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSERVA-THOMAS,C.W.

l TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR.

NUREG/CR-6230 RADIOANALYTICAL TECHNOLOGY FOR to CFR ING NETWORK

l PART 61 AND OTHER SELECTED RADIONUCUDES. Literature Review.

l STRIZHOV,V.

NUREG/CR4429 THE ROLE OF ORGANIC COMPLEXANTS AND Mi-NUREG/lA-0129 P01: AN ASSESSMENT OF THE CORCCEMOD3 CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA.

CODE.Part 1: Thermal-Hydraulic Calculations.

DIONUCUDES.

STROM8 ERG,H M.

NUREG/CR4314: QUALITY ASSURANCE INSPECTIONS FOR SHIP-THOMAS,M.L.

PING AND STORAGE CONTAINERS.

NUREG 0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM-MERICAL NUCLEAR POWER REACTORS AND OTHER STROSNIDEMAR.

FACILITIES,1994. Twenty-Seventh Annual Report.

NUREG-1511 Sot: REACTOR PRESSURE VESSEL STATUS REPORT.

THOMAS,V.W.

STR KME ER, NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NRC M DIRECT RADIADON MONITORING PART 61 AND OTHER SELECTED RADIONUCLIDES.uterature NETWORK. Progress Report. October. December 1995.

Review.

NUREG-0837 V16 N01: NRC TLD DIRECT RADIATION MONITORING NUR 4 83 2

R RA ATION MONITORING WOMAS.W.

NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR NETWORK.Progrees Report. April-June 1996.

AUTOMATING ECCS SWITCHOVER AT PWRS.

STUSGS J.B.

NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-THRALL,K.D.

MACEUTICALS.

NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-l CLIDE BURDENS TO PRENATAL RADIATION DOSES.

SUSUDHi,M.

NUREG/CR4336: AGING ASSESSM5NT OF LARGE ELECTRIC TINGLE,W.

MOTORS IN NUCLEAR POWER PLANTS.

NUREG-1556 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE-NUREG/CR4340* AGING ASSESSMENT OF SURGE PROTECTIVE DE' RIALS UCENSES. Program Specific Guidance About Portable Gauge U enses. Draft Report For Comment.

NI

/R 84 VO : U R REVIEW OF ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Summary TOOHEY,R.E.

NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.

NU V02: UTERATU7tE REVIEW OF ENVIRONMENTAL MACEWCALS.

QUAUFICATION OF SAFETY.RELATED ELECTRIC CABLES.uterature Analysis And Appendices.

TOQUAM,J.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

SULUVAN,T.M.

UPDATE OF THE TECHNICAL ISSUES 1996.

NUREG/CR 5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR N 'O N*

I FISCAL YEAR 1995. Annual Report.

NUREG/CR4256 V01: FIELD LYSIMETER INVESTIGATIONS: LOW.

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTER 12A-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TlON ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES-TEST RESULTS FOR FISCAL YEARS 19t#4 AND 1995.

TIMATES.

i NUREG/CR 6492: BLT-MS (BREACH. LEACH, AND TRANSPORT.MUL.

TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat-TRAUS,RJ.

ing Release Of Contamment From Subeurface Low-Level Waste Dio.

NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-CUDE BURDENS TO PRENATAL RADIATION DOSES.

posal Facility.

TAl,A.

TRAVIS,R.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-Report.

TIONS.

. -.~.

52 Personal Author index TUTTLE.M.P.

ATLAS SITE.MOAB, UTAH. Source Matenal Ucense No. SUA.

NUREG/CR4495: CASE STUDY OF UQUEFACTON INDUCED BY THE 917, Docket No. 40-3453. (Atlas Corporation) 1944 MASSENA. NEW YORK CORNWALL, ONTARIO EARTH-QUAKE.

WANGAA, NUREG/CR4413: ANALYSIS OF THE IRRADIATON DATA FOR A302B TYACKE.MJ.

AND A5338 CORRELATION MONITOR MATERIALS.

1 NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG.

ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC.

WANG,W.

CORDING TO IMPORTANCE TO SAFETY.

NUREG/CR4309. SCIENTIFIC DESIGN OF PURDUE UNIVERSITY MULTl-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE UOY,A.C.

S8WR.

NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

WARD,LW, NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

USILTON.W.K.

I NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE.

WARRICK,A.W.

RIALS UCENSING PROCESS REDESIGN.

NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE MONITORING AND FIELD STUDIES.

VACCA,P.C.

NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-WASHINGTON,K.E RIALS UCENSING PROCESS REDESIGN.

NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOUDAT.

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft Repcyt For Comment.

WATKINS,5.

NUREG-1556 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE-NUREG-1415 V08 NO2: OFFICE OF THE INSPECTOR RIALS UCENSES. Program Specrhc Guidance About Portable Gauge GENERALSemiannual Report To Congress. October 1,1995 March Uconees. Draft Report For Comment 31,1996.

NUREG-1415 V09 N01: OFFICE OF THE INSPECTOR VAN DYKE,J.W.

GENERALSemiannual Report To Congress, April 1,1996. September NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

30,1996.

ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE ATLAS SITE,MOAB. UTAH. Source Material Ucense No. SUA-WEISMANN,J.J.

1 917, Docket No. 40-3453. (Atlas Corporation)

NUREG/CR4450: CHARACTERtZATON OF CONTAMINATION THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND VARGAS,P.M-DIGITAL IMAGE PROCESSING.

)

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

WENDELBOE.D.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES VEEH.R.H.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final NUREG/CR4341: MICROBIAL DEGRADATON OF LOW LEVEL RADIO-Report.

ACTIVE WASTE. Final Report.

WERNICKE,5.P.

VESELY,W.E.

NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4415: APPUCATONS OF RELIABluTY DEGRADATON REGION.Cntical Rowew And Analyses of Tectonic Data From The ANALYEIS.

Central Basin And Range.

VILKE P-WEST,K S.

NUREQ/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Ml-NUREG 1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA~

POWER PLANTS.

DIONUCLIDES.

WHITE,V.S.

YlLLARAN,M.

NUREG/CR-6500: OWNERS OF NUCLEAR POWER PLANTS.

NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC MOTORS IN NUCLEAR POWER PLANTS.

WHITTEN,J.E.

NUREG/CR4384 V02 UTERATURE REVIEW OF ENVIRONMENTAL NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-QUAUFICATON OF SAFETY-RELATED ELECTRIC CABLES.uterature RIALS UCENSING PROCESS REDESIGN Analysis And Apporxhces.

NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT.

ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft VILLEGAS,AJ.

Report For Comment.

NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG-1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-MISSONING A REFERENCE LARGE IRRADIATOR AND REFER-RIALS UCENSES. Program-Specific Guidance About Portable Gauge ENCE SEALED SOURCES.

Ucenses. Draft Report For Comment.

VINOGRADOYA,T.

WIBLIN C.

NUREG/lA-0129 Poi: AN ASSESSMENT OF THE CORCON-MOD 3 NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON CODE.Part 1: Thermal-Hydraulle Calculations.

RADOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED DOCUMENTS.

NUREG/CR4300: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY WICHMAN,K.R.

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT.

SBWR.

WlERENGA.PJ.

WADE M.C.

NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE NUREG 1543. DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-MONITORING AND FIELD STUDIES.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION. CAMBRIDGE. OHIO, FACluTY. Docket No. 404948,U-WILKOWSKI,G.M.

cense No. SMB-1507, NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG.2 ROUND-ROBIN ANALYSES.

WALSH,5.

NUREG/CR4438. THE EFFECT OF CYCUC AND DYNAMIC LOADS ON NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR CARBON STEEL PIPE.

AUTOMATING ECCS SWITCHOVER AT PWRS.

NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC FORCING FUNCTION.

TALSH.PJ.

NUREG/CR4440: THE EFFECTS OF CYCLIC AND DYNAMIC LOADING NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE STEELS Technscal Report: October 1992 - Apnl 1996.

Personal Author index 53 NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY WOOD.R.T.

SURFACE-CRACKED ELBOWS.

NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR DIGITAL SAFETY CHANNEL INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND ELBOWS.

RADIO. FREQUENCY INTERFERENCE LEVELS IN NUCLEAR POWER PLANTS.

NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS MtEATHA4.1,A THE ACCURACY OF UNSATURATED FLOW MODELS.

NUREG/CR4350t A TECHNIQUE FOR HUMAN ERROR ANALYSIS (ATHEANA).Techrecal Beeio And Methodology Desertphort wigggggy,y, NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY ggg MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATION

SBWR, STUDIES. impacts Of Artificiel Time History input On Ir>. Structure Demand Spectra.

wu enu n y NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION NUREG/CR-5535 V07 RI: RELAP5/ MOD 3 CODE MANUALSummertes STUDIES. impacts On Risk Acessement Of Uniform Hazard Spectra.

And h Of Independent Code Aseeeement Reporm.

VARDUMIAN,J.

wu anu e a NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR NUREG-0525 V02 R04: SAFEGUARDS

SUMMARY

EVENT LIST APACHE LEAP TUFF; TEMPERATURE EFFECTS AND HYSTERESIS.

(SSEL). January 1,1990 Through December 31,1995.

Wu. SON,R.

YAU,M.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS UPDATE OF THE TECHNICAL ISSUES 1996.

OF CONTROL SOFTWARE IN ADVANCED REACTORS.

WILSON,T.L YOtANGAOL NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE D6GITAL SAFETY CHANNEL MONITORING AND FIELD STUDIES.

WWIGERT,V.L.

ZALUZEC,NJ.

NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND LIGHT WATER REACTORS. Semiennual Report. April 1995. December PREPAREDNESS IN SUPPORT OF NUCLEAR POWER 1995.

PLANTS.Criterte For Emergency Planning in An Early Site Permit son. Draft Report For Comment.

Zgggi une a N

G-0054 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL-NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY; UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND UPDATE OF THE TECHNICAL ISSUES 1996.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS.Criterte For Protective Action RecommendetL,no For Severe ZHENG.R4L Accidente. Draft Report For NUREG/CR 5442: RELIABluTY. BASED CONDITION ASSESSMENT OF STEEL CONTAINMENTS AND LINERS.

WOOO,R.S.

NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-ZlGLER,G.

CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR OPERATIONS AND MAINTENANCE COSTS.

AUTOMATING ECCS SWITCHOVER AT PWRS.

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Subject Index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcome.

10 CFR PART 81 NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON NUREG/CR-6230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.

PART 61 AND OTHER SELECTED RADIONUCUDES.Litersture NUREG/CR-6336: AGING ASSESSMENT OF LARGE ELECTRIC Review.

MOTORS IN NUCLEAR POWER PLANTS.

NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR 10 CFR Part 51 AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC.

NUREG-1437 V01: GENERIC ENVIRONMENTAL IMPACT STATEMENT TIONS.

FOR LICENSE RENEWAL OF NUCLEAR PLANTS. Main Report.

NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-NUREG-1437 V02: GENERIC ENVIRONMENTAL IMPACT STATEMENT VICES IN NUCLEAR POWER PLANTS.

FOR UCENSE RENEWAL OF NUCLEAR PUNTS.

~ es.

NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

NUREG-1529 VO1: PUBLIC COMMENTS ON THE SED 10 CFR NUREG/CR4384 VO1: UTERATURE REVIEW OF ENVIRONMENTAL

^

RA I L N D

RTIN M

S REVI O Pa NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSfVE

'NU G

V PUB H

O ED 0CFR f

PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-NU E /CR 4: R AI F NUC R R PLANT ERATING UCENSES AND SUPPORTING DOCUMENTS: REVIEW OF CONCERNS AND NRC STAFF RESPONSE. Appendices.

NUR /

5 ACT RAL AGING ON SEISMIC RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN 3-D Finite Element Analyele NUREG/CR 6317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT NUCLEAR POWER PLANTS.

EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN SAFETY-RELATED COMPONENTS.

ACRS Report NUREG/CR4490 V01: NUCLEAR POWER PMNT GENERIC AGING NUREG 1125 V17: A COMPILATION OF REPORTS OF THE ADVISORY LESSONS LEARNED (GALL). Main Report And Appendix A.

COMMITTEE ON REACTOR SAFEGUARDS.1995 Annual.

NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING LESSONS LEARNED (GALLt Appendix B.

NUREG-1272 V09 N01: OFFICE FOR ANALYSIS AND EVALUATION OF Air Permeebellty OPERATIONAL DATA.1994 FY 95 Annual Report - Reactors.

NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL NUREG-1272 V09 NO2: OFFICE FOR ANALYSIS AND EVALUATION OF EXPERIMENTS.Results And Lessons Leamed.

OPERATIONAL DATA.1994-FY 95 Annual Report - Nuclear Materials.

NUREG/CR 6360

SUMMARY

OF AIR PERMEABILITY DATA FROM NUREG-1272 V09 NO3: OFFICE FOR ANALYSIS AND EVALUATION OF SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED OPERATIONAL DATA 1994-FY Annual Report. Technical Training.

TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF STEADY STATE TEST INTERPRETATION.

Abnormal Occurrence NUREG-0090 V10 NO2: REPORT TO CONGRESS ON ABNORMAL A

TeeHng Dek OCCURRENCES. April June 1995 NUREG/CR-5758 V06. FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG-0090 V18 NO3: REPORT TO CONGRESS ON ABNORMAL INDUSTRY. Annual Summary Of Program Performance Reports CY OCCURRENCES. July-September 1995.

1995.

AccountetWitty Report NUREG-1542 V01: ACCOUNTABluTY REPORT FISCAL YEAR 1995, Alloy 600 NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN Actinicle SIMULATED LWR ENVIRONMENTS.

NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON BREATH-ING ZONE AND AREA AIR SAMPLES.

Alpha-Mode Containment Failure NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN Achranced Reactor ALPHA-MODE CONTAINMENT FAILURE ANC A REVIEW OF THE NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS CURRENT UNDERSTANDING OF BROADER FUEL COOLANT OF CONTROL SOFTWARE IN ADVANCED REACTORS.

INTERACTION ISSUES. Report Of The Second Steam Explosion Aeroeog Review Group Workshop.

NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY A

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

EG-5 V12: U.S. NUCLEAR REGULATORY COMMISSION 1995 Aging ANNUAL REPORT.

NUREG 1557:

SUMMARY

OF TECHNICAL INFORMATION AND AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES Apache Leap COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENEWAL.

NUREG/CR4457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE NUREG/CP 0149 V03: PROCEEDINGS OF THE TWENTY THIRD TUFF CORES USING A GAS PYCNOMETER.

WATER REACTOR SAFETY INFORMATION MEETING Structural &

NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR Seismic Eng6ncering. Primary Systems integrity, Equipment Operability APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

BET OF Apache Leap Tuff REUAELT NE CONDIT NUR 544 STEEL CONTAINMENTS AND LINERS.

NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL NUREG/CR4753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN EXPERIMENTS.Results And Lessons Leamed.

SAFETY SYSTEMS QF NUCLEAR POWER PLANTS.

NUREG/CR4202: LONG-TERM AGING AND LOSS-OF COOLANT AC.

Area Air Semp6e CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S/ French Co-NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON BREATH-operettve Research Program.

ING-ZONE AND AREA AIR SAMPLES.

55

l l

56 Subject index l

l Array Protie Branch Technical Pceltion NUREG/CR4163; COMPUTER PROGRAMS FOR THE ACQUISITION NUREG-1563: BRANCH TECHNICAL POSITON ON THE USE OF AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA-EXPERT ELICITATON IN THE HIGH-LEVEL RADCACTIVE WASTE NUREG/CR 6357: EVALUATION AND FIELD VALIDATION OF EDDY" PROGRAM ~

CURRENT ARRAY PROBES FOR STEAM GENERATOR TUDE IN-SPECTION.

Breathing 4one Artmetal Time History NUREG/CR-6419: SOLUBlWTY TESTING OF ACTINIDES ON BREATH-NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATION ING-ZONE AND AREA AIR SAMPLES.

STUDIES. impacts Of Artrlicial Time History input On in-Structure l

Demand Spectra.

Drtitle Fracture NUREG/CR4468: GROUND MOTON INPUT IN SEISMIC EVALUATION NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL-STUDIES. impacts On Risk Assessment Of Uruform Hazard Spectra ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT Atmospheric Release EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST i

RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

FAILURE BY BRITTLE FRACTURE. Category li And 111 Ferrttic Steel Ovisory Committee On Nucieer Weste SNpping Containers With Wall Thickness Greater Then Four inches.

NUREG-1423 V06: A COMPILATION OF REPORTS OF THE ADVISORY COMMITTEE ON NUCLEAR WASTE. July 1995 June 1996.

RE PROJECT FOR FRACTURE ANALYSES OF Amiel Surface Crack LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-i NUREG/CR4445: DEVELOPMENT OF A J ESTIMATON SCHEME FOR SIRE 11).

INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN i

ELBOWS.

Budget NUREG-1100 V12: BUDGET ESTIMATES. Fiscal Year 1997.

NUREG/CR4492: BLT MS (BREACH. LEACH, AND TRANSPORT-MUL*

Sulk Temperature l

TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat-NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT iN THER-ing Release Of Contarmnant From Subeurface Low-Level Waste Dis-MALLY STRIPED PIPE FLOWS.

posal Facility.

)

BWR CARM Peseke Reactor NUREG-1540: BWR STEEL CONTAINMENT CORROSION.

NUREG/lA-0134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY.

NUREG-1544: STATUS REPORT: INTERGRANULAR STRESS CORRO-DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL THE CARR PASSIVE REACTOR (CP 1300).

l COMPONENTS.

l NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING CORCON-Mod 3 Code FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/lA-0129 P01: AN ASSESSMENT OF THE CORCON-MOD 3 STATION Effecta Of Current Regulatory And Other Conederations On CODE.Part 1: Thermal Hydraulic Calculations.

The Financial Assurance Requirements Of The Decommisatorung Rule And....

Cattle Fire NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4476: CIRCUIT BRIDQlNG OF COMPONENTS BY SMOKE.

FOR THE REFERENCE BOILING WATER REACTOR POWER j

STATION.Effecta Of Current Regulatory And Other Considerations On Cartion stoet The Financial Assurance Requirements Of The Decommissioning Rule NUREG/CR4438: THE EFFECT OF CYCUC AND DYNAMIC LOADS ON CARBON STEEL PIPE.

NUR /CR4270: ESTIMATING BOILING WATER REACTOR DECOM-l MISSIONING COSTS.A User's Manual For The BWR Cost Estimating Certificates Of e NU C5 NUREG-0383 V01'R19: DIRECTORY OF CERTIFICATES OF COMPLl-R E L T O EAD LOSS AND FIL-l TRATION FOR LOCA DEBRIS.

ANCE FOR RADIOACTIVE MATERIALS PACKAGES. Report Of NRC NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH Approved Packages.

BURNUP CORES.

NUREG-0383 V02 R19: DIRECTORY OF CERTIFICATES OF COMPLI-

)

ANCE FOR RADIOACTIVE MATERIALS PACKAGES.Certificatos Of l

Biological Half-Ufe Compliance.

l NUREG/CR4374: WHOLE BODY EFFECTIVE HALF-LIVES FOR RA-NUREG4383 V03 R16: DIRECTORY OF CERTIFICATES OF COMPLl-i l

DIOLABELED ANTIBODIES AND RELATED ISSUES-ANCE FOR RADIOACTIVE MATERIALS PACKAGES. Report Of NRC B@g h hw Appr ved Quality Assurance Programs For Radioactive Materials Pack-NUREG-1540: BWR STEEL CONTAINMENT CORROSION.

89**'

NUREG 1544: STATUS REPORT: INTERGRANULAR STRESS CORRO-AC ING OF BWR CORE SHROUDS AND OTHER INTERNAL A I NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-FOR THE REFERENCE BOILING WATER REACTOR POWER CONTAMINATION WASTE. Literature Review.

STATION Effects Of Current Regulatory And Other Considerations On The Financial Assurance Requirements Of The Decommissiorung Rule Chemical %. _

And....

NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSONING ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE FOR THE REFERENCE BOILING WATER REACTOR POWER CURRENT UNDERSTANDING OF BROADER. FUELCOOLANT STATION. Effects Of Current Regulatory And Other Considerations On INTERACTION ISSUES. Report Of The Second Steam Explosion The Financial Assurance Requirements Of The Decommissioning Ru6e Review Group Workshop And....

NUREG/CR4270: ESTIMATING BOILING WATER REACTOR DECOM-Circuit Bridging MISSIONING COSTS.A User's Manual For The BWR Cost Estimating NUREG/CR4476: CIRCUlT BRIDGING OF COMPONENTS BY SMOKE.

Computer Program (CECP) Software Final Report.

NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-Circumferential Crack N

2 PO XCURSION ANALYSIS FOR HIGH NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY BURNUP CORES.

SURFACE-CRACKED ELBOWS.

i prochytherapy Closure Law NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN NUREG/lA-0133: DEVELOPMENT,lMPLEMENTATION, AND ASSESS-SAFETY TESTING.Techrucal Report On The Findings Of Task 4 inves.

MENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-ANNULAR tigation of Failed Natinol Brachytherapy Wire.

FILM-BCILING IN A TWO-FLUID MODEL

Subject index 57 Code asessement Core Performance NUREG/CR-5535 V07 R1: RELAP5/ MOD 3 CODE MANUALSummerles NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

And Reviewe Of ;, M Code Assosoment Reporte.

Core Shroud Codes And Standerde NUREG 1544: STATUS REPORT: INTERGRANUuR STRESS CORRO-NUREG/CR-6973 R03: CODES AND STANDARDS AND OTHER GUID-SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL ANCE CfTED IN REGULATORY DOCUMENTS.

COMPONENTS.

Cold Les Olde break Correlation Monitor Meterial NUREG/lA-0131: ASSESSMENT OF RELAPS/ MOD 3 USING BETHSY NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A3028 8.2TC 6 INCH COLD LEG SIDE BREAK COMPARATIVE TEST, AND A5338 CORRELATION MONITOR MATERIALS.

Cotective Does m

NUREG4713 Vie: OCCUPATIONAL RADIATION EXPOSURE AT COM-NUREG 1540 BWR STEEL CONTAINMENT CORROSION.

MERICAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC FACluTIES 1994. Twenty-Seventh Annual Report.

RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUCLEAR POWER PMNTS.

Cameld permadon NUREG-1564: LONG-TERM KINETIC EFFECTS AND COLLOID FORMA-TlONS IN DISSOLUTION OF LWR SPENT FUEL

/

7 V20: ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS. Sermannual Report. October 1994 March Commeroisi Someere NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-1995.

MERCIAL OFF THE-SHELF (COTS) SOFTWARE IN REACTOR APPU.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN UGHT WATER REACTORS. Sermannual Report, April 1995 - December CATIONS.

1995.

Compressive Testing NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 600 IN NUREG/CR4302: THE EFFECTS OF AGING ON COMPRESSIVE SIMULATED LWR ENVIRONMENTS.

STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.

NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT BROOKHAVEN NATIONAL LABORATORY.

Computer Code NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF CON-Cost Analysis TROL ROOM HABITABILITY (HABIT).

NUREG/CR4270: ESTIMATING BOluNG WATER REACTOR DECOM-MISSIONING COSTS.A User's Manual For The BWR Cost Estimating

/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO.

ACTIVE WASTE. Final Report.

Cost Estimate NUREG-1307 R06: REPORT ON WASTE BURIAL CHARGES.Eocalation Of Decormnesiomng WaeM Disposal Coom At LowW WeeM M 4 467: IMPACT OF GROUND MOTION CHARACTERIZA.

TION ON CONSERVATISM AND VARIABluTY IN SEISMIC RISK ES-NUR CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-TIMATES.

MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER.

ENCE SEALED SOURCES.

Conseedaden NUREG 1541 DAFT FC: PROCESS AND DESIGN FOR CONSOUDAT.

I A

NG MATERIALS UCENSING GUIDANCE. Draft R

-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS. Semiannual Report. April 1995 - December Containment 1995.

NUREG/CR4383. CORROSION FATIGUE OF ALLOYS 600 AND 690 IN NUREG 1540 BWR STEEL CONTAINMENT CORROSION.

NUREG/CR-5442 REUABluTY-BASED CONDITION ASSESSMENT OF SIMULATED LWR ENVIRONMENTS.

STEEL CONTAINMENTS AND UNERS.

NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES Creeldng USED YO TRANSPORT VARIOUS CONTENTS.

NUR6G/CP-0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At Conceinment tooledon ASTM Headquarters, PNiedelpNa, Penneytvania, May 2 3,1995.

NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-Critteellty Safety TIONS.

NUREG/CR4483: GUIDE TO VERIFICATION AND VALIDATION OF THE SCALE-4 CRITICAUTY SAFETY SOFTWARE.

Contaminent NUREG/CR4402 BLT MS (BREACH. LEACH, AND TRANSPORT-MUL-Cyonc Loading TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat-NUREG/CR4440: THE EFFECTS OF CYCUC AND DYNAMIC LOADING Ing Reisene Of Contaminant From Subeurface Low-Level Weste Dis-ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING posal Facility.

STEELS. Technical RenortOctober 1992 - April 1996.

Control Room Data Analysie I

NUREG-0700 R01 V01: HUMAN-SYSTEM INTERFACE DESIGN REVIEW NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR GUIDELINES. Process And Guidelines. Final Report TUBING SAMPLES.

NUREG4700 RO1 V02: HUMAN SYSTEM INTEMFACE DESIGN REVIEW GUIDELINES. Reviewer's Checklist Final Report Dooomminoloning NUREG 0700 R01 V03: HUMAN-SYSTEM imERFACE DESIGN REVIEW NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

GUIDEUNES. Review Software And User's Gu6de. Final Report COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION, CAMBRIDGE. OHIO, FACIUTY. Docket No. 40-8948.U-Contrei Room HabitehANy A

FM NU

/CR'4 V01 REVISED ANALYSES OF DECOMMISSIONING UTY FOR THE REFERENCE BOluNG WATER REACTOR POWER f

Control Someero STATION. Effects Of Current Regulator / And Other Consideratione On NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS The Financial Assurance Requirements Of The Decomrmessoning Rule OF CONTROL SOFTWARE IN ADVANCED REACTORS.

g Core tenhaup Tank FOR THE REFERENCE BOluNG WATER REACTOR POWER NUREG/lA4134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY.

STATION. Effects Of Current Regulatory And Other Coneadorations On DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP TANK OF The Financial Assurance Requiremente Of The Decomrmseioning Rule THE CARR PASSIVE REACTOR (CP-1300).

And...

58 Subject Index l

NUREG/CR4270 ESTIMATING BOILING WATER REACTOR DECOM-Ductile Tearing MISSONING COSTS.A User's Manual For The BWR Cost Estimating NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL-NU CR42

.CH LOG,

D OSTS OF DECOM-MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-Dynamic Load i

ENCE SEALED SOURCES.

NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON CARBON STEEL PIPE.

l RADOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED l

DOCUMENTS.

Dynamic Loading i

Dooontamination NUREG/CR4440: THE EFFECTS OF CYCLIC AND DYNAMIC LOADING ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING NUREG/CR4124: CHARACTERIZATON OF RADIONUCLIDE CHELAT.

ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-STEELS. Technical ReportOctober 1992. April 1996.

CONTAMINATION WASTE. Literature Review.

ECCS NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY THIRD NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NUREG/CR4494: CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI WATER REACTOR SAFETY INFORMATION MEETING. Structural &

DECONTAMINATON.

Seismic Engineenng, Pnmary Systems integrity, Equipment Operability And A 6ng, ECCS Strainer Blockage Research & Regulatory lesues.

9 l

DegradeHon ECCS Switchover

)

NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATON l

ANALYSIS.

NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

DegradeWon hchaniern NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

EPICOR-il NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.

Demonstradon Program LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR j

NUREG-1568: LICENSE RENEWAL DEMONSTRATON PROGRAM:

FISCAL YEAR 1995. Annual Report.

NRC OBSERVATONS AND LESSONS LEARNED.

Eary SNe Pen Detecuon Threshold NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL.

NUREG/CR4448 V01: EVALUATON OF NATIONAL SEISMOGRAPH UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NETWORK DETECTON CAPABILITIES. Annual Report, July 1994. July PREPAREDNESS IN SUPPORT OF NUCLEAR POWER i

1995.

PLANTS.Critena For Emergency Planning in An Early Ste Permit ApphcatmDraft Report For Comment.

Devloe Design NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL-1 NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND SAFETY TESTING. Technical Report On The Findings Of Task 4 inves.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER l

16getion of Failed Nrbnol Brachytherapy Wire.

PLANTS.Cnteria For Protective Action Recommendations For Severe Accidents. Draft Report For.

NUREG-1518: DIFFERING PROFESSIONAL VIEWS OR OPINIONS.1994 Earthquake

(

Special Rev6ew Panet NUREG/CR4495: CASE STUDY OF LIQUEFACTION INDUCED BY THE

{

Dignal Equipment 1944 MASSENA, NEW YORK CORNWALL, ONTARIO EARTH-QUAKE' l

NUREG/CR4476: CIRCUlT BRIDGING OF COMPONENTS BY SMOKE.

Eastern Tectonic l

Dignal SofWy Chenal NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR4495: CASE STUDY OF LIQUEFACTON INDUCED BY THE DIGITAL SAFETY CHANNEL 1944 MASSENA, NEW YORK - CORNWALL, ONTARIO EARTH-QUAKE.

Direct Containment Heating

/ 4435 A N LYSIS OF THE IMPACTS OF ECONOMIC IN-H NG UE F ST GH S NTS RG l

DRY COffTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT OPERATONS AND MAINTENANCE COSTS.

i Does Commitment l

NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOACTIVE Eddy Cwrent l

RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology NUREG/CR.6163: COMPUTER PROGRAMS FOR THE ACQUISITION And Data Base AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

l NUREG/CR 2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREWCR4227: PERFORMANCE DEMONSTRATION TESTS FOR RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992' EDDY CURRENT INSPECTON OF STEAM GENERATOR TUBING.

NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY.

Draft Environmentalimpact Statement CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-SPECTION.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL l

CORPOR ON CA BRIDGE. OHIO, FACILITY. Docket No. 40-8948,Li-UREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY SURFACE-CRACKED ELBOWS.

Drug Ostection NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATON SCHEME FOR NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN UPDATE OF THE TECHNICAL ISSUES 1996.

ELBOWS.

Drug Teeeng Date Electric Cable NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR4384 V01: LITERATURE REVIEW OF ENVIRONMENTAL INDUSTRY. Annual Summary Of Program Performance Reports CY QUALIFICATON OF SAFETY-RELATED ELECTRIC CABLES. Summary j

1995.

Of Past Work.

Dry Containment Electric Motor j

NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE MOTORS IN NUCLEAR POWER PLANTS.

DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

Dry Outdetion NUREG/CR4202: LONG TERM AGING AND LOSS OF-COOLANT AC-NUREG 1565: DRY OMIDATON AND FRACTURE OF LWR SPENT CIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S1 French Co-FUEL operative Research Program.

l

Subject Index 59 Electromagnetic interference Failure Analyste NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT RADO-FREQUENCY INTERFERENCE LEVELS IN NUCLEAR POWER BROOKHAVEN NATIONAL LABORATORY.

PLANTS.

Embrtitlement NUREG/CR4350 A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR4413: ANALYSIS OF THE lRRADIATION DATA FOR A3020 (ATHEANA). Technical Basis And Methodology Desenption.

AND A5338 CORRELATON MONITOR MATERIALS.

Fault Tree R 06 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-UATON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND Faulting PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN PUNTS.Crttena For Emergency Planning in An Early Site Permit REGION.Cntical Review And Analyses of Tectonic Data From The Application. Draft Report For Comment.

Central Basin And Range.

Emergency Reeponse Plan Ferritic Steel NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATON AND EVAL-NUREG/CR4491: RECOMMENDATONS FOR PROTECTING AGAINST l

UATON OF RADf0 LOGICAL EMERGENCY RESPONSE PLANS AND FAILURE BY BRrlTLE FRACTURE. Category II And til Ferrttic Steel PREPAREDNESS IN SUPPORT OF NUCLEAR POWER Shipping Containers With Wall Thicknese Greater Than Four inches.

PLANTS.Cntens For Protective Action Recommendations For Severe Accidents. Draft Report For. -

Fleid Expefiment NUREG/CR-4918 V09 CONTROL OF WATER INFILTRATON INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-G 40 N3&4Pt: ENFORCEMENT ACTIONS: SIGNIFICANT ACTIONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress NU C

62 LD TIN NSATURATED 2ONE NUR 4

41 : ENFORCEMENT ACTONS: SIGNIFICANT MONITORING AND FIELD STUDIES.

ACTIONS RESOLVED REACTOR LICENSEES.Serrmannual Progress NURW94 NUREG/lA-0133: DEVELOPMENT,lMPLEMENTATON, AND ASSESS-N 4 : ENFORCEMENT ACTONS: SIGNIFICANT MENT OF SPECIFIC CLOSURE UWS FOR INVERTED-ANNULAR ACTIONS RESOLVED MATERIAL LICENSEES. Semiannual Progress FILM-BOILING IN A TWO FLUID MODEL R

July-December 1995, NUR G 40 V15 N1 P1: ENFORCEMENT ACTONS: SIGNIFICANT AC-lONS RESOLVED 1 IVIDUAL ACTONS. Semiannual Progresa G

V01: REVISED ANALYSES OF DECOMMISSIONING NUR 0940 VI5 P2: ENFORCEMENT ACTONS: SIGNIFICANT AC.

FOR THE REFERENCE BOILING WATER REACTOR POWER TIONS RESOLVED REACTOR LICENSEES. Semiannual Progress STATION. Effects of Current Regulatory And Other Considerations On Report.Januarv4une 1996 The Financial Assurance Requirements Of The Dm v...ang Rule NUREG 0940 Vf 5 N1 P3: ENFORCEMENT ACTONS: SIGNIFICANT AC-And..

TONS RESOLVED MATERIAL LICENSEES.Serrmannual Progress NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING Report January 4une 1996.

FOR THE REFERENCE BOILING WATER REACTOR POWER STATON. Effects Of Current Regulatory And Other Conederations On E/R 50 ARACTERIZATON OF CONTAMINATION And THROUGH THE USE O? POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESSING.

Financial Statement 4

Environmental Impact Statement NUREG-1437 Voi: GENERIC ENVIRONMENTAL IMPACT STATEMENT Fire Berrier FOR LICENSE RENEWAL OF NUCLEAR PLANTS. Main Report-NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

NUREG 1437 V02: GENERIC ENVIRONMENTAL IMPACT STATEMENT ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING NUR G 01 LC MM O

E h10 CFR THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER P

PART $1 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.

NUR RRIER PENETRATION SEALS IN NUCLEAR ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF POWER PUNTS' CONCERNS AND NRC STAFF RESPONSE. Executive Summary NUREG-1529 V02: PUBLIC COMMEN S ON THE PROPOSED 10 CFR Fire Reelstance PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING

$ MENT RELAT.

THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER NU EG 1

E IRONME I

PLANT APPLICATIONS.

ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE MOAB, UTAH. Source Material License No. SUA-Fitnese For Duty NUREG/CR 5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER NI GC 53:

ME T R VE N PROPOSED RULE ON INDUSTRY. Annual Summary Of Program Performance Reports CY RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED DOCUMENTS.

NL G/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

UPDATE OF THE TECHNICAL ISSUES 1996.

Environmental OueMeetion NUREG/CR4384 V01: LITERATURE REVIEW OF ENVIRONMENTAL E

ALIFICA ON OF SAFETY-RELATED ELECTRIC CABLES. Summary E 53 1: G DEUNES FOR PREPARING AND REVIEWING APPLICATIONS FOR THE LICENSING OF NON-POWER Environmental Review REACTORS.Part 1: Format And Content.

NUREG 1440: REGULATORY ANALYSIS FOR AMENDMENTS TO REG-Fracture ULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF NUREG/CR4440: THE EFFECTS OF CYCLIC AND DYNAMIC LOADING NUCLEAR POWER PLANT OPERATING LICENSES. Final Report.

ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING Environmental Testino STEELS. Technical Report October 1992 - April 1996.

NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY DIGITAL SAFETY CHANNEL SURFACE CRACKED ELBOWS.

FORECAST Computer Code Fracture Flow NUREG/CR.5595 RO1: FORECAST: REGULATORY EFFECTS COST NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL ANALYSIS SOFTWARE MANUAL Versson 4.1.

EXPERIMENTS.Resutta And Lessons Leemed.

I

60 Subject index Fracture Mechanico hidaho NUREG/CP-0161: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET-NUREG-1537 PT01: GUlUELINES FOR PREPARING AND REVIEWING I

ING ON NG IN LWR RPV HEAD PENETRATIONS. Held At APPUCATIONS FOR THE UCENSING Of NON PmvFR ASTM PM=Wue, erne, Me 2-3, 1995.

REACTORS. Pert 1: Format And ContenL NUREG/CR-5442 REllABluTY DASED DITION ASSESSMENT OF NUREG-1537 PT02: GUIDELINES FOR PREPARING AND REVIEWING I

STEEL CONTAINMENTS AND UNERS.

APPUCATIONS FOR THE UCENSING OF NON-POWER NUREG/CR4443: DETERMINISTIC AND PROBABluSTIC EVALUA-TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN REACTORS. Pert 2: Standard Review Plan And Acceptance Crtterie.

NUREG/CR-2000 SO5: GUIDEUNES FOR NUCLEAR POWER PLANT LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS-NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR SAFETY ISSUE PR6ORITIZATION INFORMATION DEVELOPMENT INTERNAL CIRCUMFERENTIAL AND AX1AL SURFACE CRACKS IN NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES ELBOWS.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF Report.

GE SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.

Fracture Toughnese NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS

MEET.

Head Laos ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held A NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-ASTM Headquarters, PNiedelpNo Pennsylvanie, May 2 3,1995.

TRATION FOR LOCA DEBRIS.

NUREG/CR4279: APPUCATION dF FRACTURE TOUGHNESS SCAL.

ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.

Head Penetration NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE ASTM Headquarters, PNiedelptus. Pennsylvania, May 2 3,1995.

TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS STEEL PIPE WELDS.

Health Physic NUREG/CR4438: THE EFFECT OF CYCUC AND DYNAMIC LOADS ON NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-CARBON STEEL PIPE.

MACEUTICALS.

Fractured Rock Heat Th NUREG/CR4360:

SUMMARY

OF AIR PERMEABluTY DATA FROM SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF

Shelirradieuon Program ITEADY-STATE TEST INTERPRETATION.

NUhtEG/CR 5591 V06 N2: HEAVY SECTION STEEL IRRADIATION l

Fusi Behowlor PROGRAM.Semiennual Progrees Report For April Through September l

NUREG/CP 0149 V01: PROCEEDINGS OF THE TWENTY THIRD 1995.

WATER REACTOR SAFETY INFORMATION MEETING.Planery See-sion, High Burnup Fuel Behavior, Thermal Hydraulic Research.

Hoovy Steet Technoengy Program NUREG/CR 4219 VII N2 HEAVY SECTION STEEL TECHNOLOGY l

FueM:ooient interaction PROGRAM.Somiennual Progrees Report For April September 1994.

NUREG 1524: A REASSESSMENT OF THE POTENTIAL FOR AN NUREG/CR-4219 V12 N1: HEAVY SECTION STEEL TECHNOLOGY ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE PROGRAM.Som6ennual Progrese Report For October 1994 - March CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT 1995.

INTERACTION ISSUES. Report Of The Second Steem Explosion Review Group Workshop.

High Burnup Core NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH Ose ha - -- - ---

BURNUP CORES.

NUREG/CR4457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE TUFF CORES USING A GAS PYCNOMETER.

Higl> Level Weste NUREG-1563: BRANCH TECHNICAL POSITION ON THE USE OF

^ ^

^

EG 1 S0 REACTOR PRESSURE VESSEL STATUS REPORT.

p og Generic Safety leeue 24 NUREG-1564: LONG-TERM KINETIC EFFECTS AND COLLOID FORMA.

NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR TlONS IN DISSOLUTION OF LWR SPENT FUEL AUTOMATING ECCS SWITCHOVER AT PWRS.

NUREG 1565: DRY OXIDATION AND FRACTURE OF LWR SPENT FUEL Generic Safety leeuse NUREG-0933 S20 A PRIORITIZATION OF GENERIC SAFETY ISSUES.

Hist >Lavel Weste Repoeltory NUREG 0933 S21: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN REGION.Crttical Review And Analyses of Tectorne Date From The NU BRANCH TECHNICAL POSITION ON THE USE OF EXPERT EUCITATION IN THE HIGH LEVEL RADIOACTIVE WASTE Holding Companies PROGRAM.

NUREG/CR4500 OWNERS OF NUCLEAR POWER PLANTS.

Geostenouc Human Error Analyste NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS THE ACCURACY OF UNSATURATED FLOW MODELS.

NUREG/CR4350 A TECHNIQUE FOR HUMAN ERROR ANALYSIS (ATHEANA). Technical Basio And Methodology Desenption.

Global Pooleoning System NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSERVA-Human Factore Engineering TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-NUREG-0700 R01 V01: HUMAN-SYSTEM INTERFACE DESIGN REVIEW ING NETWORK.

GUIDELINES. Process And GuidelinesTanal Report.

NUREG-0700 R01 V02: HUMAN-SYSTEM INTERFACE DESIGN REVIEW Oround Monon GUIDEUNES. Reviewer's Checkleet. Final Report.

j NUREG/CR4466; GROUND MOTION INPUT IN SEISMIC EVALUATION NUREG-0700 R01 V03. HUMAN-SYSTEM INTERFACE DESIGN REVIEW STUDIES. impacts Of Artificial Time History input On in-Structure GUIDEUNES. Review Software And User's Guide. Final Report.

Demand Spectre.

NUREG/CR 6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR446h IMPACT OF GROUND MOTION CHARACTER 12A-(ATHEANA).Techrucal Bases And Methodology Descriptm TION ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES-TIMATES.

Human RollabilNy NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR STUDIES. impacts On Risk Aseeeement Of Uniform Hazard Spectre.

AUTOMATING ECCS SWITCHOVER AT PWRS.

Subject index 61 Humid Region site inservice Testing NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO NUREG/CR4396: EXAMPLES.CLARIFICATONS. AND GUIDANCE ON NEAR SURFACE LLW DISPOSAL UNITS.Progrees Report On Field Ex-PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-penments At A Hurrvd Region Site,Beltaville, Maryland.

SERVICE TESTING REQUIREMENTS.

UCT!

HYDTOLMIC EVALUATION METHODOLOGY FOR NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNNERSITY Integral system scellne NUREG/CR4340:

i l

ESTIMATING WATER MOVEMENT (HrtOU21 TMc ilNSATURATED MULTl-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WAbit: DG cown.

POSAL SITES.

NUREG/CR4368: POLYRES: A POLYGON. BASED RICHARDS EQUA-Intergranuier Strees Corrosion CracW N REM 544: SMS EN MERMM SNESS MO NU

/CR

A GEOSTATISTICAL METHODOLOGY TO ASSESS THE ACCURACY OF UNSATURATED FLOW MODELS.

SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE COMPONENTS.

l MONITORING AND FIELD STUDIES.

lon Es%

INTRAVAL Emportment NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATONS: LOW.

NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR EXPERIMENTS.Results And Leesons Learned.

FISCAL YEAR 1995. Annual Report.

NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE IPIRG-2 STRENGTH OF LOW LEVEL RADCACTIVE WASTE FORMS.

NUREG/CR4337:

SUMMARY

OF RCSULTS FROM THE IPIRG-2 ROUND ROBIN ANALYSES.

Irredleted Reactor Fuel NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISfAIC NUREG 0725 R11: PUBLIC INFORMATION CIRCULAR FOR SHib FORCING FUNCTION.

MENTS OF IRRADIATED REACTOR FUEL ISFS1 Irradiation NUREG 1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY SPENT NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATON OF SE.

FUEL STORAGE SYSTEMS. Draft Report For Comment.

LECTED AEA/UCSB MODEL FECUMN ALLOYS.

NUREG-1567 DRFT FC: STANDARD REVIEW PLAN FOR SPENT FUEL DRY STORAGE FACILITIES. Draft Report For Cornment.

Irredletion Date NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A3020 Impact Loading AND A5338 CORRELATION MONITOR MATERIALS.

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

Irradiator NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-l NU R44 R

MOTION INPUT IN SEISMIC EVALUATON C S LED CE '

STUDIES.lmpacts Of Artificial Time History input On in Structure Demand Spectra-J-Estimation Scheme individual Action NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATON SCHEME FOR NUREG-0940 V15 N1 P1: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN TONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress ELBOWS.

Report,Jarmary-June 1996.

Individual Plant Examinetton NUREG/CR 6367; EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-NUREG-1560 V1 P1 DFC: INDIVIDUAL PLANT EXAMINATION PRO.

TRATION FOR LOCA DEBRIS.

GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT PERFORMANCE. Summary Report. Draft Report For Comment.

LNI

(

NUREG-1560 V2P2-5DFC: INDIVIDUAL PLANT EXAMINATION PRO.

NUREG/CR-6494: CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI GRAM: PERSPECTNES ON REACTOR SAFETY AND PLANT DECONTAMINATON.

PERFORMANCE.Perts 2-5. Draft Report For Comment.

LWR induced Liquefaction NUREG 1564: LONG-TERM KINETIC EFFECTS AND COLLOID FORh i

NUREG/CR4495: CASE STUDY OF LIQUEFACTON INDUCED BY THE TIONS IN DISSOLUTION OF LWR SPENT FUEL 1944 MASSENA, NEW YORK CORNWALL, ONTARIO EARTH-NUREG-1565: DRY OXIDATON AND FRACTURE OF LWR SPENT QUAKE.

FUEL NUREG/CR 4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN Industry Report LIGHT WATER REACTORS. Semiannual Report, October 1994 March NUREG-1557:

SUMMARY

OF TECHNICAL INFORMATION AND 1995.

AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENEWAL LIGHT WATER REACTORS. Semiannual Report April 1995 December 1995.

EG 4375: STRAIN RATE AND INEATIAL EFFECTS ON IMPACT AD I T LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

NUREG/CR4363. CORROSION FATIGUE OF ALLOYS 600 AND 690 IN SIMULATED LWR ENVIRONMENTS.

Mformation DegW NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION INFORMA-LWR Edition TlON DIGEST.1996 Editon.

NUREG-0800 DRFT FC: STANDARD REVIEW PLAN FOR THE REVIEW Inservice Flow OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER NUREG/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA.

PLANTS. LWR Edition. Draft Report For Comment.

TONS FOR UNCERTAINTY IN P1PE FRACTURE PARAMETERS IN l

LEAK DEFORE-BREAK AND IN-SERVICE FLAW EVALUATONS.

U C

3: DETERMINISTIC AND PROBABILISTIC EVALUA.

Jneervice inspectics TONS FOR UNCERTAINTY IN PlPE FRACTURE PARAMETERS IN NUREG/CR-5006: PIPING INSPECTON ROUND ROBIN.

LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS.

j inservice inepection System Leek-Rate NUREG/CR-5965 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 TRASONIC INSERVICE INSPECTION SYSTEM.

ROUND-ROBIN ANALYSES.

l

62 Subject index 8 anaea Rete Uconoing Process NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES NUREG-1539-METHODOLOGY AND FINDINGS OF THE NRC'S MATE-USED TO TRANSPORT VARIOUS CONTENTS.

RIALS UCENSING PROCESS REDESIGN.

L80ef leeuences Ught Water Reactor NUREG4750 V41: NUCLEAR REGULATORY COMMISSION NUREG 0800 DRFT FC: STANDARD REVIEW PLAN FOR THE REVIEW ISSUANCES.Opin6ons And Decissons Of The Nuclear Regulatory Corn-OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER miseson With Selected Orders.Jarcary-June 1995.

PLANTS. LWR Estion. Draft Report For Comment

)

NUREG4750 V42102: INDEXES TO NUCLEAR REGULATORY COM-NUREG-1564: LONG-TERM KINETIC EFFECTS AND COLLOID FORMA-MISSION ISSUANCES. July-December 1995.

TIONS IN DISSOLUTION OF LWR SPENT FUEL NUREG-0750 V42 N05: NUCLEAR REGULATOPY COMMISSION IS-NUREG-1565: DRY OXIDATION AND FRACTURE OF LWR SPENT SUANCES FOR NOVEMBER 1995. Pages 181211t FUEL NUREG 0750 V42 N06: NUCLEAR RwULATORY COMMISSION IS-NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN NU EG 3 :

XES O L

EGULA10RY COM-Missn 653UAHW9 Januarv-March 1996.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG 0750 V43102: INDEXES 1014UCLUP AFGULATOaY COM-MISSION ISSUANCES. January June 1996.

LIGHT WATER REACTORS. Semiannual Report April 1995 December NUREG-0750 V43 NO1: NUCLEAR REGULATORY COMMIS90N IS-NUR /CR-6344: HEAL T;ME 3 D SAFT UT SYSTEM EVALUATION SUANCES FOR JANUARY 1996. Pages 1-11.

NUREG-0750 V43 N02: NUCLEAR REGULATORY COMMISSION IS-NUREG CORROSION FATIGUE OF ALLOYS 600 AND 690 IN SUANCES FOR FEBRUARY 1996. Pa$GULATORY COMMISSION IS-los 13-49.

NUREG-0750 V43 NO3: NUCLEAR R SIMULATED LWR ENVIRONMENTS.

SUANCES FOR MARCH 1996. P 51 121.

SU N F AP 996 0

4202-TERM AGING AND LOSS-OFCOOLANT AC-NUREG-0750 V43 N05: NUCLE [R REGUI'ATORY COMMISSION IS.

CtDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S1 French Co-SUANCES FOR MAY 1996.

operative Research Program.

NUREG-0750 V43 N06: NUCLEAR REGULATORY COMMISSION IS.

NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY SUANCES FOR JUNE 1996.

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG 0750 V44 N01: NUCLEAR REGULATORY COMMISSION IS-SBWR.

SUANCES FOR JULY 1996.Pages 157.

NUREG-0750 V44 NO2: NUCLEAR REGULATORY COMMISSION IS-Low-Level Ramaetive Weste SUANCES FOR AUGUST 1996. Pages 59 78 NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NUREG-0750 V44 NO3: NUCLEAR REGULATORY COMMISSION IS-PART 61 AND OTHER SELECTED RADIONUCLIDES. Literature SUANCES FOR SEPTEMBER 1996. Pages79-106.

Review.

NUREG-0750 V44 N04: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR-6256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-SUANCES FOR OCTOBER 1996. Pages 107 228.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

Leesons Learned NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO.

NUREG 1568: LICENSE RENEWAL DEMONSTRATION PROGRAM:

ACTIVE WASTE. Final Report.

l NRC OBSERVATIONS AND LESSONS LEARNED.

NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR i

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED N E CR U LEA PLA NERIC AGING POSA SITE LESSONS LEARNED (GALL). Appendix B.

NUREG/CR439' : THE EFFECTS OF AGING ON COMPRESSIVE 2

Ucense Renewal STRENGTH OF LOW LEVEL RADIOACTIVE WASTE FORMS.

NUREG 1437 V01: GENERIC ENVIRONMENTAL IMPACT STATEMENT Low-Level Weem NUR G 1 V02 E ER ENV NME A I T

EMENT NUREG/CR4492: BLT MS (BREACH. LEACH AND TRANSPORT-MUL-FOR LICENSE RENEWAL OF NUCLEAR PLANTS. Appendices TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Sunulat-NUREG 1440- REGULATORY ANALYSIS FOR AMENUMENTS TO REG.

ing Release Of Contaminant From Substriace Low-Level Waste Dis-ULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF posal Facility.

NUCLEAR POWER PLANT OPERATING LICENSES Final Report.

NUREG 1529 VOI: PUBLIC COMMENTS ON THE PROPOSED 10 CFR LowM Weste Data Base PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-NUREG/CR4229 V06: FIELD LYSIMETER INVESTIGATIONS LOW.

ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR CONCERNS AND NRC STAFF RESPONSE. Executive Summa FISCAL YEAR 1995. Annual Report NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED I'0 CFR NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

CONCERNS AND NRC STAFF RESPONSE.Apperdcas.

Low-Level Waste Disposal L

RY RE SA G

NSE EW L ng se e

as NUREG-1568: LICENSE RENEWAL DEMONSTRATION PROGRAM:

Facilities.

NRC OBSERVATIONS AND LESSONS LEARNED.

NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO

)

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-LESSONS LEARNED (GALL). Main Report And Appendix A.

pertments At A Humid Region Site,Beltsville, Maryland.

NUREG/CR 6490 V02: NUCLEAR POWER PLAru GENERIC AGING LESSONS LEARNED (GALL). Appendix B.

LY N

/CR 5229 V08: FIELD LYSIMETER INVESTIGATa'WS: LOW-l Ucensed Device LEVEL WASTE DATA BASE DEVELOPMENT ROGRAM FOn j

NUREG-1551: FINAL REPORT OF THE NRC AGREEMENT STATE FISCAL YEAR 1995. Annual Report.

WORKING GROUP TO EVALUATE CONTROL AND ACCOUNTABIL.

NUREG/CR4256 V03: FIELD LYSIMETER INVFdTIGATIONS: LOW-ITY OF LICENSED DEVICES.

LEVEL WASTE DATA BASE DEVELOPMENT FROGRAM LYSIMETER i

TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

1 Uoensed Fuel Facility Status Report i

NUREG-0430 V15:

UCENSED FUEL FACILITY STATUS Main Steam looletion Valve REPORT. inventory Difference Data. July 1,1994 June 30,1995.(Gray NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON Book II).

MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.

Licensed Operating Reactor Maintenance NUREG-0020 V20: LICENSED OPERATING REACTORS STATUS SUM-NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN MARY REPORT. Data As Of December 31,1995.(Gray Book l)

SAFETY RELATED COMPONENTS.

Subject Index 63 Maintonenes Cost Non Peeer Remotor

i. 9 FOR PREPARING AND REVIEWING NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMC IN-NUREG-1537 PT01: r CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT APPUCATIONS FOH

'dE UCENSING OF NON-POWER OPERATIONS AND MAINTENANCE COSTS.

REACTORS. Pert 1: Format And Content NUREG-1537 PT02: GUIDEUNES FOR PREPARING AND REVIEWING Monstenance Program APPUCATIONS FOR THE UCENSING OF NON-POWER NUREG-1661: STANDARD REVIEW PLAN MAINTENANCE PROGRAM REACTORS. Pert 2: Standard Rev6ew Plan And Acceptance Crtterie.

IMPLEMENTING PROCEDURES DOCUMENT.

Nondestructive Evolustion Motorial Usense NUREG/CR-5088: PIPING INSPECTION ROUND ROBIN.

NUREG 1666 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE-NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT RIALS UCENSES.L,..Speci8c Guidance About Portable Gauge REINFORCED CONCRETE STRUCTURES.

Uoeness. Draft Report For Comment.

Nondestructive Evaluation Motortal Liceneses NUREG/CR-6442: REUABluTY-BASED CONDITION ASSESSMENT OF NUREG4940 V15 N1 P3: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

STEEL CONTAINMENTS AND UNERS.

TIONS RESOLVED MATERIAL UCENSEES.Somiennual Progrees NUREG/CR-5966 S01: REVIEW OF P SCAN COMPUTER-BASED UL-Report, January June 1996.

TRASONC INSERVICE INSPECTION SYSTEM.

Meteresse siestrente unrery Notch send M8nFG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOUDAT-NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT ING AND UPDATING MATERMLS UCENSING GUIDANCE.Dren LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

Report For Comment.

Nuoleer industry Motoriale Usensin0 NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

NUREG-1539 METHOOOLOGY AND FINDINGS OF THE NRC'S MATE-UPDATE OF THE TECHNICAL ISSUES 1996.

RIALS UCENSING PROCESS REDESIGN.

NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOUDAT.

Nuoleer Material 1r40 AND UPDATING MATERIALS UCENSING GUIDANCE. Draft NUREG 1272 V09 NO2: OFFICE FOR ANALYSIS AND EVALUATION OF Report For Comment.

OPERATIONAL DATA.1994-FY 95 Annual Report Nucieer Materiale.

NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-MloroMel Degradallen RIALS UCENSING PROCESS REDESIGN.

NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-ACTIVE WASTE. Final Report.

Nuoleer Pipe NUREG/CR4440: THE EFFECTS OF CYCUC AND DYNAMIC LOADING Mloreportculate ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING NUREG/CR4429 THE ROLE OF ORGANIC COMPLEXANTS AND Mi-STEELS. Technical Report: October 1992 - April 1996.

CROPARTCULATES IN THE FACluTATED TRANSPORT OF RA-DIONUCUDES.

Nuoteer Power Plant NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-Charactortassen CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF SE*

OPERATIONS AND MAINTENANCE COSTS.

LECTED AEA/UCSB MODEL FECUMN ALLOYS.

NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETC AND REQUENCY INTERFERENCE LEVELS IN NUCLEAR POWER y,;,

I NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM-NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERC AGING POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency LESSONS LEARNED (GALL). Main Report And Appendix A.

NU E CR4490 V02 ER PLANT GENERIC AGING NUR CR E

S ICATIONS, AND GUIDANCE ON PREPARING REQUESTS FOR REUEF FROM PUMP AND VALVE IN-NUREG/CR4500* OWNERS OF NUCLEAR' POWER PLANTS.

SERVCE TESTING REQUIREMENTS.

Oooupellenal Radletten Exposure NEl W O NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING NUREG M68: UCENSE RENEWAL DEMONSTRATION PROGRAM:

FOR THE REFERENCE BOluNG WATER REACTOR POWER NRC OBtWRVATIONS AND LESSONS LEARNED.

STATION. Effects Of Current Regulatory And Other Considerations On The Financial Assurance Requiremente Of The Decommiessonmg Rule DNIC Agreement m Wortdne Group

^"d NUREG-1561: FML REPORT OF THE NRC-AGREEMENT STATE NUREG/CR-6174 V02: REVISED ANALYSES OF DECOMMISSIONING WORKING GRUIP TO EVALUATE CONTROL ANO ACCOUNTABIL-FOR THE REFERENCE BOluNG WATER REACTOR POWER ITY OF UCENSED SEVCES*

STATION. Effects Of Current Regulatory And Other Considerations On DIRC/ASIIE Sympoelum The Financ6el Assurance Requirements Of The Gm...u.A. A,y Rule NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM.

And-POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency Moe W The inspector W Hotel,WesNngton,DC, July 15-18,1998.

NUREG-1415 VOS NO2: OFFICE OF THE INSPECTOR IfuttARC GENERALSemiennual Report To Congrees,0ctober 1,1995 March NUREG-1567:

SUMMARY

OF TECHNICAL INFORMATION AND 31,1996.

AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES NUREG-1415 V09 Not: OFFICE OF THE INSPECTOR COUNCIL INDUSTRY REPORTS ADDRESSING LCENSE RENEWAL GENERALSemiennual Report To Congress, April 1,1996 - September 30,1996.

Stet Value NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR Organic Complement AUTOMATING ECCS SWITCHOVER AT PWRS.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-CROPARTICULATES IN THE FACIUTATED TRANSPORT OF RA.

Itetwork Simulellen DIONUCUDES.

NUREG/CR4448 Voi: EVALUATION OF NATIONAL SEISMOGRAPH NETWORK DETECTION CAPABluTIES. Annual Report, July 1994 July Organiselion Chart NUREG4325 R19: U.S. NUCLEAR REGULATORY COMMISSION OR.

1995.

GANIZATION CHARTS AND FUNCTIONAL STATEMENTS. January 31, NIIInol 1996.

NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN NUREG-0325 R20: U.S. NUCLEAR REGULATORY COMMISSION OR-SAFETY TESTING. Technical Report On The Findlnes Of Task 4 Irwoo-GANIZATION CHARTS AND FUNCTIONAL STATEMENTS. July 1, tigation of Failed Nitinol Brachytherapy Me.

1996.

64 Subject Index NUREG 0325 R21: U.S. NUCLEAR REGULATORY COMMISSION OR-Procoure Yessel steet GANIZATON CHARTS AND FUNCTIONAL STATEMENTS. August 19, NUREG/CR4332: MICROSTRUCTURAL CHARACTERl2ATON OF SE.

1996.

LECTED AEA/UCSB MODEL FECUMN ALLOYS.

1 Oumore Probetdlistic Risk Aseeeement NUREG/CR450m OWNERS OF NUCLEAR POWER PLANTS.

NUREG-1560 V1 P1 DFC: INDIVIDUAL PLANT EXAMINATON PRO-PIPERM PN2 GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT a

NUREG/lA4135: POST TEST ANALYSIS OF PIPER ONE PO-IC-2 EX-PERFORMANCE. Summary ReportDraft Report For Comment PERIMENT BY RELAP5/ MOD 3 CODES' REM 563: BRANCH WCHN POSRON ON WE USE OF EXPERT EUCITATON IN THE HIGH-LEVEL RADIOACTIVE WASTE PtUS PROGRAM.

NUREG/CR-6253: PlVS CORE PERFORMANCE ANALYSIS.

NUREG/CP-0149 V02: PROCEEDINGS OF THE TWENTY THIRD WATER REACTOR SAFETY INFORMATION MEETING. Human Factors Packaging inepect6on Research, Advanced l&C Hardware & Software, Severe Accident Re-NUREG/CR4314: QUAUTY ASSURANCE INSPECTONS FOR SHIP-search, Probabilistic Risk Assessment Topics. Individual Plant Examma-PING AND STORAGE CONTAINERS.

tion.

Penetration Seal Program Performance Report NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER POWER PLANTS.

INDUSTRY.Anrest Summary Of Program Performance Reports CY 1995.

Performance Aseseement NUREG/CP 0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE*

Proposed Rule POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON Holiday Inn Crowne Plaza, Rockville, Maryland, September 19-20, 1994.

RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED DOCUMENTS.

NUREG-1542 V01: ACCOUNTABluTY REPORT FISCA'. YEAR 1995.

Putdic Com nent Poudone For Rulemaking NUREG-1529 V01: PUBLC COMMENTS ON THE PROPOSED 10 CFR NUREG 0936 V14 NO2: NRC REGULATORY AGENDA.Samaannual PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.

ReportJuly December 1995.

ERATING UCENSES AND SUPPORTING DOCUMENTS: REVIEW OF NURt.G 0936 V15 N01: NRC REGULATORY AGENDA. Semiannual CONCERNS AND NRC STAFF RESPONSE. Executive Summary.

ReportJanuary June 1996.

NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 CFR PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.

Pipe ERATING UCENSES AND SUPPORTING DOCUMENTS: REVIEW OF NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 CONCERNS AND NRC STAFF RESPONSE.Appendcas.

ROUND-ROBIN ANALYSES.

NUREG/CR4438: THE EFFECT OF CYCUC AND DYNAMIC LOADS ON Pump Testing CARBON STEEL PIPE.

NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM.

NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC POSIUM ON VALVE AND PUMP TESTING. Held At The Hvatt Regency FORCING FUNCTION.

Hotel,WanNngton,00, July 15-18,1996, NUREG/CR4443: DETERMINISTIC AND PROBABluSTIC EVALUA-NUREG/CR4396: EXAMPLES, CLARIFICATIONS, AND GUIDANCE ON TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN PREPARING REQUESTS FOR RELIEF FROM PUMP AN') VALVE IN-LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS-SERVCE TESTING REQUIREMENTS.

NUREG/GR4015: BULK TEMPERATURE MEASUREMENT IN THER-MALLY STRIPED PIPE FLOWS-Quality Assurance Piping NUREG/CR4314: QUAUW ASSURANCE INSPECTIONS FOR SHIP.

NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.

PING AND STORAGE CONTAINERS.

Plant Performance RELAP6/IAOO3 NUREG-1560 V2P2-5DFC: INDIVIDUAL PLANT EXAMINATION PRO-NUREG/CR 5535 V07 Rt: RELAP5/ MOD 3 CODE MANUALSummenes GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT And Reviews Of Independent Code Assessment Reports.

PERFORMANCE. Parts 2-5. Draft Report For Comment.

NUREG/lA4130- ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF SB-SG-06 EXPERIMENT SIMULATING A STEAM GENERATOR TUBE Pneumatic infection RUPTURE TRANSIENT.

NUREG/CR4360

SUMMARY

OF AIR PERMEABILITY DATA FROM NUREG/lA4131: ASSESSMENT OF RELAP5/ MOD 3 USING BETHSY SINGLE-HOLE INJECTON TESTS IN UNSATURATED FRACTURED 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF NUREG/lA 0132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFLOOD STEADY-STATE TEST INTERPRETATION.

MODEL AND UNCERTAINTY OUANTIFICATION OF REFLOOD PAK CLAD TEMPERATURE.

Portatdo Gacge NUREG/lA 0133: DEVELOPMENT,lMPLEMENTATION, AND ASSESS-NUREG-1556 V01 DR FC: CONSOLIDATED GUIDANCE ABOUT MATE-MENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-ANNULAR RIALS LCENSES. Program-Specthe Guidance About Portable Gauge FILM-BOILING IN A TWO-FLUID MODEL.

Licenses. Draft Report For Comment NUREG/lA-0135: POST TEST ANALYSIS OF PIPER-ONE PO-lC 2 EX-PERIMENT BY RELAP5/ MOD 3 CODES.

Poettion Sonettive Detector NUREG/lA 0134: ASSESSMENT OF RELAP5/ MOD 3.1 FOR GRAVITY.

NUREG/CR4450: CHARACTERIZATION OF CONTAMINATION DRIVEN INJECTON EXPERIMENT IN THE CORE MAKEUP TANK OF THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESSING.

THE CARR PASSIVE REACTOR (CP 1300).

Rad 6suon Does Power Escursion NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.

NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH BURNUP CORES' CUDE BURDENS TO PRENATAL RADIATION DOSES.

NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.

Practice And Procedure D6 gest MACEUTICALS.

NUREG 0386 D07: UNITED STATES NUCLEAR REGULATORY COM-MISSION STAFF PRACTICE AND PROCEDURE DIGEST.Commass.on, Radiation Effect Appeal Board And Ucensing Board Decassons. July 1972 - June 1995.

N'JREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE VESSEL SUPPORTS.

Prenatal Does NUREG/CR 5631 R02: CONTRIDUTION OF MATERNAL RADIONU.

Radiation Embrfttlement CUDE BURDENS TO PFIENATAL RADIATION DOSES.

NUREG 1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT,

Subject Index 65 Radletion Exposure ing Release Of Contanwnant Frorn Subsurface Low-Level Waste Dis-NUREG 0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM-posal Facility.

MERICAL NUCLEAR POWER REACTORS AND OTHER FACluTIES,1994. Twenty-Seventh Annual Report.

Radiopharmaceutical NUREG/CR4345: RADIATON DOSE ESTIMATES FOR RADIOPHAR-Radecon Protocuon MACEUTICALS' NVREG/CR4374: WHOLE-BODY EFFECTIVE HALF LIVES FOR RA-DIOuBELED ANTIBODIES AND RELATED ISSUES-Reactor Appucadon NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-RadaHon Sh6eidng NUREG/CR-6484: GUIDE TO VERIFICATION AND VAUDATION OF MEGCtAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPU-THE SCALE 4 RADLATION SHIELDING SOFTWARE.

CATIONS.

Radiation Survey Reactor Cornponent NUREG-1575 DRFT FC: MULTI AGENCY RADIATON SURVEY AND NUREG/CR4339: AGING ASSESSMENT OF WESTINCTUSE PWR SITE INVESTIGATION MANUAL (MARSSIM). Draft For Public Com-AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATO1 FUNC.

rnent.

TONS.

NUREG/CR4415: APPLICATIONS OF REUABluTY DEGRADATION Radio Frequency interference ANALYSIS NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES AT RADIO-FREQUENCY INTERFERENCE LEVELS IN NUCLEAR POWER BROOKHAVEN NATONAL LABORATORY.

PLANTS.

Reactor Containment Redonctive Matertal NUREG4383 V01 R19: DIRECTORY OF CERTIFICATES OF COMPU-NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY ANCE FOR RADIOACTIVE MATERIALS PACKAGES. Report Of NRC NATURAL PROCESSES IN REACTOR CONTAINMENTS.

RIO: DIRECTORY OF CERTIFICATES OF COMPLi-Reactor Licensees NU G438 V ANCE FOR RADIOACTIVE MATERIALS PACKAGES. Certificates Of NUREG-0940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

NU V03 R16: DIRECTORY OF CERTIFICATES OF COMPLl-Re Ja is1996 ANCE FOR RADIOACTIVE MATERIALS PACKAGES Report Of NRC Approved Quality Assurance Prograrns For Radioactive Materials Pack-Reactor Operator ages.

NUREG-0700 R01 V01: HUMAN-SYSTEM INTERFACE DESIGN REVIEW GUIDELINES. Process And G4thnes. Final Report.

Radioactive Release NUREG-0700 ROI V02 HUMAN-SYSTEM INTERFACE DESIGN REVIEW NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOACTIVE GUIDEUNES. Reviewer e Checklist. Final Report.

RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology NUREG-0700 R01 V03: HUMAN-SYSTEM INTERFACE DESIGN REVIEW And Data Base.

NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE GUIDELINES. Review Software And Users Guide. Final Report.

RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

Rad 6oactive Weste NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE NUREG/CR4457: RAPID ESTIMATE OF SOUD VOLUME IN LARGE VESSEL SUPPORTS.

TUFF CORES USING A GAS PYCNOMETER.

NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT.

NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

LARGE SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-SIRE II).

Radionnalytical Technology NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR PA 61 AND OTHER SELECTED RADIONUCUDES.uterature RG 4 34 : AGIN ASSESSMENT OF SURGE PROTECTIVE DE-VICES IN NUCLEAR POWER PLANTS.

Rad 6olabe6ed Antibodies NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-UVES FOR RA.

OlGITAL SAFETY CHANNEL DIOLABELED ANTIBODIES AND RELATEDISSUES.

Reactor Safety Rad 6ological Criteria NUREG-1560 V2P2-SDFC: INDIVIDUAL PLANT EXAMINATION PRO-NUREG/CR4353. COMMENTS RECEIVED ON PROPOSED RULE ON GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED PERFORMANCE. Parts 2 5. Draft Report For Cornrnent.

DOCUMENTS.

NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY THIRD WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-Radiological Emergency Response Plan sion, High Burnup Fuel Behavior, Therrnal Hydraulic Research.

NUREG4654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL.

NUREG/CP 0149 V02: PROCEEDINGS OF THE TWENTY-THIRD UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND WATER REACTOR SAFETY INFORMATION MEETING. Human Factors PREPAREDNESS IN SUPPORT OF NUCLEAR POWER Research, Advanced l&C Hardware & Software, Severe Accident Re-PLANTS.Crtteria For Emergency Plantwng in An Early Site Permit search, Probabihstic Risk Assesstnent Topica, Individual Plant Examina.

Application. Draft Report For Cornrnent tion.

Radionuclide NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY THIRD NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.

WATER REACTOR SAFETY INFORMATION MEETING. Structural &

CLIDE BURDENS TO PRENATAL RADIATION DOSES.

Seismic Engineenng, Pnmary Systems integrity, Equiprnent Operabihty NUREG/CR4124: CHARACTERIZATON OF RADIONUCUDE-CHELAT-And Aging, ECCS Strainer Blockage Research & Regulatory issues.

ING AGENT COMPLEXES FOUND IN LOW. LEVEL RADIOACTIVE DE-NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-CONTAMINATION WASTE Uterature Review.

VICES IN NUCLEAR POWER PLANTS.

NUREG/CR4a0: COMPUTER CODES FOR EVALUATION OF CON-NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS N E/

3 F A

Y TECdIOLOGY FOR 10 CFR (ATHEANA).Techrwcal Basis And Methodology Description.

PART 61 AND OTHER SELECTED RADIONUCUDES.Uterature Reactor System NUREG/CR4421: A PROMSED ACCEPTANCE PROCESS FOR COM-NUR CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA.

MERCIAL OFF-THE-SG F (COTS) SOFTWARE IN REACTOR APPLi-CATIONS.

DIONUCLIDES.

Radionucede M6gration Reactor Vessel NUREG/CR4492: BLT MS (BREACH. LEACH, AND TRANSPORT-MUL-NUREG/CR-2800 SOS: GUIDEUNES FOR NUCLEAR POWER PLANT TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat-SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

1 66 Subject index i

Rectemation NUREG 0700 R01 V02: HUMAN-SYSTEM INTERFACE DESIGN REVIEW NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

GUIDELINES. Renewer's CheckhetFmal Report.

ED TD RECLAMATION OF THE URANIUM MILL TAlWNGS AT THE NUREG 0700 R01 V03: HUMAN-SYSTEM INTERFACE DESIGN REVIEW ATLAS SITE,MOAB, UTAH. Source Material Ucense No. SUA.

GUIDEUNES. Review Software And User's Guide.Flnsi Report 917, Docket No.404453. Atlas CorportJon)

NUREG-1532: DRAFT TEC(HNICAL EVALUATION REPORT FOR THE Michartie Esquation Solver PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-NUREG/CR4306: POLYRES: A POLYGON-BASED RICHARDS EQUA.

PORATION MOAB MILLSource Maternal Ucense No. SUA-917, Docket TION SOLVER.

No. 40-3453.(Atlas Corporation)

Reoortis Dispooftlon NUREG/CR-6388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-NUREG4910 R02 SO2: NRC COMPREHENSIVE RECORDS DISPOSI-ED ROCK MASS.

TION SCHEDULE.

Rock Mass Reflood Pet Clod Temperature NUREC'8:4132: IMPROVEMENTS TO THE RELAP5/ MOD 3 REFmOD NUREG/CR 6388: SEISMC RESPONSE OF ROCK JOINTS AND JOINT.

ED ROCK MASS.

MODa ND UNCERTAINTY OUANTIFICATION OF REFLOOD PAK CLAD 7 4PERATURE.

Rock Mechanico Registrouan WMeete NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-NUREG W0: STANDAR0 REVIEW PLAN FOR APPUCATIONS FOR POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At SEALEU SOURCE AND DEVICE EVALUATIONS AND REGISTRA.

Holide/ Inn Crowne Plaza, Rockville, Maryland, September 19-20, 1994.

TIONS.

Rules NUREG-0936 V14 NO2: NRC REGULATORY AGENDA.Sermannual

-09 2 NRC REGULATORY AGENDA.Sermannual NU 36 1: N IC REGULATORY AGENDA. Semiannual NUR V15 N01: NRC REGULATORY AGENDA. Semiannual Report.Jarmary-June 1996.

Report.Jonuary4une 1996.

Rules Of M Regulatory Analyste NUREG-0386 D17: UNITED STATES NUCLEAR REGULATORY COM-NUREG/CR-5595 Rot: FORECAST: REGULATORY EFFECTS COST MISSION STAFF PRACTICE AND PROCEDURE DICEST.Commiseson, ANALYSl? SOFTWARE MANUAL Version 4.1.

Appeal Board And Ucerrang Board Decisione. July 1972 June 1995.

Regulatory And Technical Report SAFT-UT Syrtem NUREG-0304 V20 NO3: REGULATORY AND TECHNICAL REPORTS NUREG/CR4344: REAL TIME 3-D SAFT-UT SYSTEM EVALUATION (ABSTRACT INDEX JOURNAL). Compilation For Third Quarter AND VAUDATION.

NUR G-0 20 N04: REGUMTORY AND TECHNICAL REPORTS SSWR (ABSTRACT WDEX JOURNAL). Annual CompilatKn For 1995.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG-0304 V21 N01: REGULATORY AND TECHNICAL REPORTS MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE (ABSTRACT INDEX JOURNAL). Compilation For First Quarter SBWR.

1996,Januvy-March.

NUREG-0304 V21 NO2: REGULATORY AND TECHNICAL REPORTS SCALE 4 (ABSTRACT INDEX JOURNAL). Compilation For Second Quarter NUREG/CR4483: GUIDE TO VERIFICATION AND VAUDATION OF 1996. April, June.

THE SCALE-4 CRITICAUTY SAFETY SOFTWARE.

NUREG/CR4484: GUIDE TO VERIFICATION AND VAUDATION OF Reguistory Document THE SCALE-4 RADIATION SHIELDING SOFTWARE, NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID-ANCE CITED IN REGULATORY DOCUMENTS.

SE(S) Spoolmen NUREG/CR-6317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT fiUREGI44 EG ORY ANALYSIS FOR AMENDMENTS TO REG-1 UuTIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF Safeguardo Summary Event List NUCLEAR POWER PLANT OPERATING LICENSES. Final Report.

NUREG-0525 V02 A04: SAFEGUARDS

SUMMARY

EVENT LIST g

(SSEL). January 1,1990 Through December 31,1995.

NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT REINFORCED CONCRETE STRUCTURES.

Safety Analyste NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMC NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN OF CONTROL SOFTWARE IN ADVANCED REACTORS' NUCLEAR POWER PLANTS-Safety Analysis Report NUREG 0800 DRFT FC: STANDARD REVIEW PLAN FOR THE REVIEW EG NO2: REPORT TO CONGRESS ON ABNORMAL OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER OCCURRENCES. April 4une 1995.

PLANTS. LWR Edition. Draft Report For Comment.

NUREG4090 V18 NO3: REPGRT TO CONGRESS ON ABNORMAL OCCURRENCES. July-September 1995.

N EG S20 ETY EVALUATION REPORT RELATED TO THE Repository DeWgn OPERATION OF WATTS BAR NUCLEAR PLAT, UNITS 1 AND NUREG/CP-0150 WORKSHOP ON ROCK MECHANICS ISSUES IN RE.

2. Docket Nos. 50 390 And 50-391.(Tennessee Valle! Authonty)

POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At Holiday Inn Crowne Plaza, Rockville. Maryland, September 19-20, 1994.

E CR GUIDEUNES FOR NUCLEAR POWER PLANT Roeponse Spectre SAFETY ISSUE PRIORJTIZATION INFORMATION DEVELOPMENT.

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-TION ON CONSERVATISM AND VARIABluTY IN SEISMC RISK ES.

Safety System TIMATES.

NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

Retention Period NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES NUREG.0910 R02 S02: NRC COMPREHENSIVE RECORDS DISPOSI-FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final TION SCHEDULE.

Report Review Gukleitne Safety-Related CO-..

NUREG-0700 RO1 V01: HUMAN-SYSTEM INTERFACE L,ESIGN REVIEW NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN GUIDEUNES. Process And Guidelines Final Report.

SAFETY-RELATED COMPONENTS.

I l

l

Subject Index 67 Schedule Shipping Container NUREG-0910 R02 S02: NRC COMPREHENSIVE RECORDS DISPOSI-NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST l

TION SCHEDULE.

FAILURE BY BRITTLE FRACTURE. Category 11 And lil Ferritic Steel SNppin0 Containers With Wall Thickness Greater Than Four inches.

NUREG-1550: STANDARD REVIEW PLAN FOR APPUCATIONS FOR Silicone Foam SEALED SOURCE AND DEVICE EVALUATIONS AND REGISTRA-NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR TIONS.

POWER 'LANTS.

NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN SAFETY TESTING. Technical Report On The F dogs Of Task 4 inves-Simp #fied Soiling Water Reactor m

tigation of Failed Nilinoi Dr apy Wire.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG/CR4200: TECH Y, SAFETY,AND COSTS OF DECOM-MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER" S8WR.

ENCE SEALED SOURCES.

Site Charactortsstion Setemic NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-NUREG/CR4439: DESIGN OF THE iPIRG-2 SIMULATED SEISMIC POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At FORCING FUNCTION.

Holeday Inn Crowne Plaza, Rockville, Maryland. September 19-20, 1994.

Seismic Engineering Site in-

- Manuel NUREG d75 DRFT FC: MULTI-AGENCY RADIATION SURVEY AND WATER REA A ETY N MATION MEETI S sl SITE INVESTIGATION MANUAL (MARSSIM). Draft For Public Com-Seatmec Enginesiing. Primary Systeme Integrity, Equipment Operability

- "E And Agmg, ECCS Strainer Blockage Research & Regulatory issues.

88**

Seismic Roeponse NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.

NUREG/CR4388. SEISMIC RESPONSE OF ROCK JOINTS AND JOINT.

ED ROCK MASS.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES Setemic Risk NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTER 17.A.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final TlON ON CONSERVATISM AND VARIABiUTY IN SEISMIC RISK ES.

Report.

TIMATES.

NUREG/CR4468: GROUND MOTION lh?JT IN SEISMIC EVALUATION Special Review Panel NUREG-1518: DIFFERING PROFESSIONAL VIEWS OR OPINIONS.1994 STUDIES. impacts On Rak Assessment Of Uniform Hazard Spectra.

Special Review Pe..ai.

Setemic Risk Analysie NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATION Spet Fuel STUDIES. impacts Of Artificial Time History input On in-Structure NUREG-1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY SPENT FUEL STORAGE SYSTEMS. Draft Report For Comment.

Demand Spectra.

AIREG-1564: LONG TERM KINETIC EFFECTS AND COLLOID FORMA-Setemic Riek Aceseement TIONS IN DISSOLUTION OF LWR SPENT FUEL NUREG/CR4425: IMPACT OF STRUCTUPAL AGING CN SEISMIC NUREG 1565: DRY OXIDATION AND FRACTURE OF LWR SPENT RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN FUEL NUCLEAR POWER PLANTS.

NUREG 1567 DRFT FC: STANDARD REVIEW PMN FOR SPENT FUEL DRY STORAGE FACluTIES. Draft Report For Comment.

Setemograph NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH ING AND DAY SPENT FUEL STORAGE SYSTEM COMPONENTS AC.

NETWORK DETECTION CAPABILITIES. Annual Report, July 1994 July CORDING TO IMPORTANCE TO SAFETY.

1995.

Spent Fuel Dry Storage System 8'"'" W' NUREG/CR4314: QUALITY ASSURANCE INSPECTIONS FOR SHIP-NUREG/CR 6339: AGING ASSESSMENT OF WESTINGHOUSE PWR PING AND STORAGE CONTAINERS.

AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNO-TiONS.

Spent Fuel Shipment NUREG/CR4415: APPUCATIONS OF RELIABILITY DEGRADATION NUREG4725 R11: PUBUC INFORMATION CIRCULAR FOR SHIP.

ANALYSIS.

MENTS OF IRRADIATED REACTOR FUEL EG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON MAIN isTEAM ISOLATION VALVES AND VALVE OPERATORS.

OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PMNTS. LWR Eartion. Draft Heport For Comment.

Severe Accident NUREG-1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY SPENT NUREG-0654 R1 S3 DFC: CRITERIA FOR PREPARATION AND EVAL.

FUEL STORAGE SYSTEMS. Draft Report For Comment.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG 1537 PT02 GUIDEUNES FOR PREPARING AND REVIEWING PREPAREDNESS IN SUPPORT OF NUCLEAR POWER APPLICATIONS FOR THE LICENSING OF NON-POWER PMNTS.Crttone Mr Protective Action Recommendatione For Severe REACTORS.Part 2: Standard Review Plan And Acceptance Celteria.

Accidents. Draft R For NUREG-1540- BWR TEEL dbNTAINMENT CORROSION.

NUREG-1550: STANDARD REVIEW PLAN FOR APPLICATIONS FOR SEALED SOURCE AND DEVICE EVALUATIONS AND REGISTRA.

NUREG-1560 V1 P1 DFC: INDIVIDUAL PLANT EXAMINATION PRO.

GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT TIONS.

NUREG-1561: STANDARD REVIEW PLAN MAINTENANCE PROGRAM PERFORMANCE. Summary Report. Draft Report For Comment.

NUREG-1560 V2P2-5DFC: INDIVIDu4L PLANT EXAMINATION PRO.

IMPLEMENTING PROCEDURES DOCUMENT.

NUREG 1567 DRFT FC: STANDARD REVIEW PLAN FOR SPENT FUEL l

GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT DRY STORAGE FACiUTIES. Draft Report For Comment PERFORMANCE. Parts 2-5. Draft Report For Comment NUREG/CP-0149 V02: PROCEEDINGS OF THE TWENTY THIRD NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID-WATER REACTOR SAFETY INFORMATION MEETING. Human Factors ANCE CITED IN REGULATORY DOCUMENTS.

l Research, Advanced l&C Hardware & Software, Severe Accident Re.

Steam Exploelon I

search, Probabelistic Rink Assessment Top 6ce, Individual Plant Examina.

I NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOP AN tion.

ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF mE Severs Reactor Accident CURRENT UNDERSTANDING OF BROADER FUEL COOtrNT NUREG/CR 6189: A SIMPUFIED MODEL OF AEROSOL REMOVAL BY INTERACTION ISSUES. Report Of The Second Steam Expkmlon NATURAL PROCESSES IN REACTOR CONTAINMENTS.

Review Group Workshop.

68 Subject index Steam Generator NUREG-0837 V16 N01: NRC TLD DIRECT RADIATION MONITORING NUREG/CR-2800 S05: GUIDELINES FOR NUCLEAR POWER PLANT NETWORK. Progress Report January-March 1996.

SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

NUREG 0837 V16 NO2: NRC TLD DIRECT RADIATION MONITORING NUREG/CR 6163: COMPUTER PROGRAMS FOR THE ACQUISITON NETWOAK.Progren Report. Aprildune 1996.

AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

NUREG/CR4227: PERFORMANCE DEMONSTRATON TESTS FOR Talling EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RE!.AT-NUREG/CR4357: EVALUATON AND FIELD VAUDATON OF EDDY-CURRENT AHRAY PROBES FOR STEAM GENERATOR TUBE IN-ED TO RECLAMATON OF THE URANIUM MILL TAluNGS AT THE SPECTION.

ATLAS SITE,MOAB, UTAH. Source Material Ucense No. SUA.

NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.

917. Docket No. 40 3453. (Atlas Corporation)

NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE NUREG/CR4455; DATA ANALYSIS FOR STEAM GENERATOR PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-NU

/lA 0 A SESSMENT Or RELAP5/ MOD 3.1 WITH THE LSTF PORATION MOAB MILLSource Material Ucense No. SUA-917, Docket SB-SG46 EXPERIMENT SIMULATING A STEAM GENERATOR TUBE No. 40-34534 Atlas Corporation)

RUPTURE TRANSIENT.

Technical Evaluation Report Storage Caek NUREG-1532: DRAFT TECHNICAL EVALUATON REPORT FOR THE NUREG 1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY SPENT PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-FUEL STORAGE SYSTEMS. Draft Report For Cornmort PORATION MOAB MILLSource Material Ucense No. SUA.917, Docket No. 40-34534 Atlas Corporation)

Storage System NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG.

Technical Training ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC.

NUREG-1272 V09 NO3: OFFICE FOR ANALYSIS AND EVALUATON OF CORDING TO MPORTANCE TO SAFETY.

OPERATIONAL DATA.1994-FY Annual Report Technical Trairung.

Strain Monttoring Network.

Tectonic Data NUREG/CRJ W3. GLOBAL POSITIONING SYSTEM REOBSERVA-NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN TiOrtS OVER THE EASTERN UNITED STATES STRAIN MONITOR-REGION.Cntical Review And Analyses of Tectoruc Data From The ING NETWORK.

Central Basan And Range.

Strain Rate Temperature-Time Curve NUREG/CR.6375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

NUREG 1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT-ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING S

Cwm CrackMg THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER NUREG/CR.4667 V20 ENVIRONMENTALLY ASSISTED CRACKING IN D"3' UGHT WATER REACTORS. Semiannual Report, October 1994 - March Thermal Aging NL G/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE UGHT WATER REACTORS. Semiannual Report, April 1995 December TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS 1995.

STEEL PIPE WELDS.

Structural Rollabliity hennel Muelon NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/GR4015: BULK TEMPERATURE MEASUREME.NT IN THER-REINFORCED CONGRETE STRUCTURES.

MALLY STRIPED PIPE FLOWS.

Structural Support thermal Hydraulic Research NUREG-1500: RADIATION EFFECTS ON REACTOR PRESSURE NUREG/CP 0149 V01: PROCEEDINGS OF THE TWENTY-THIRD VESSEL SUPPORTS.

WATER REACTOR SAFETY INFORMATION MEETINGPlenary Ses-ason, High Burnup Fuel Behavior, Thermal Hydraulic Research.

NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT Thermal Hydraut$c HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE NUREG/LA4129 P01: AN ASSESSMENT OF THE CORCON-MOD 3 DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

CODE.Part I: Thermal-Hydraulic Calculations.

Subourface Flow Thermoluminescent Doolmeter NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-NUREG4837 V15 N04: NRC TLD DIRECT RADIATON MONITORING TON SOLVER.

NETWORK. Progress Report. October December 1995.

Mace Contarninadon NUREG-0837 V16 Not: NRC TLD DIRECT RADIATON MONITORING MUREG/CR4450: CHARACTER 12ATION OF CONTAMINATON NETWORK. Progress Report January March 1996.

THROUGH THE USE OF POSITON SENSITIVE DETECTORS AND NUREG-0837 V16 NO2: NRC TLD DIRECT RADIATION MONITORING DIGITAL IMAnF PROCFRS!NG NETWORK. Progress Report April-June 1996.

Tr.%,-4,eisele U EG 4337:

SUMMARY

OF RESULTS FROM THE IPIRG-2 ROUND-ROBIN ANALYSES.

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NUREG/CR4439: DESIGN OF THE iPIRG-2 SIMULATED SEISMIC FORCING FUNCTON.

Title Ust NUREG4540 V17 N11: TITLE UST OF DOCUMENTS MADE PUBUCLY Surge Protective Device AVAILABLE. November 1-30,1995.

NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-NUREG-0540 V17 N12-TITLE UST OF DOCUMENTS MADE PUBUCLY VICES IN NUCLEAR POWER PLANTS' AVAILABLE. December 1 31,1995.

NUREG-0540 V18 N01: TITLE UST OF DOCUMENTS MADE PUBUCLY System Analyste AVAIL.ABLE. January 1 31,1996.

MUREG/CR4415: APPUCATONS OF REUABluTY DEGRADATON NUREG 0540 V18 NO2: TITt.E UST OF DOCUMENTS MADE PUBUCLY

ANALYSIS, AVAILABLE. February 1-29,'996.

NUREG-0540 V18 NO3: TITLE LST OF DOCUMENTS MADE PUBLICLY Systematic Assesament Of Ucensee Performance AVAILABLE. March 1 31,1996.

NUREG-1214 R14: HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

NUREG-0540 V18 N04: TITLE UST OF DOCUMENTS MADE PUBLICLY IC ASSESSMENT OF UCENSEE PERFORMANCE.

AVAILABLE.Aprtl 1-30, 1996.

TLD NUREG-0540 V18 N05: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. May 1-31,1996.

NUREG0837 V15 N04: NRC TLD DIRECT RADIATION MONITORING NUREG-0540 V18 N06: TITLE UST OF DOCUMENTS MADE PUBLICLY NETWORK Progress Report October-Decemter 1995.

AVAILABLE. June 1 30, 1996.

l

... i

Subject index 69 NUREG4540 V18 N07: TITLE UST OF DOCUMENTS MADE PUBLICLY TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF AVAILABLE. July 1 31,1996.

STEADY STATE TEST INTERPRETATION.

NUREG-0540 V18 N08: TITLE LIST OF DOCUMENTS MADE PUBLICLY NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR NUI E V N09: il L ST OF DOCUMENTS MADE PUBUCLY AVAllABLE. September 1-30,1996.

NUREG-0540 V18 N10 TITLE UST OF DOCUMENTS MADE PUBLICLY Uneaturated Zone AVAILABLE. October 1 31,1996.

NUREG/CR4346. HYDROLOGIC EVALUATION METHODOLOGY FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED Topical Report ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WASiE DIS-NUREG-0390 V10: TOPICAL REPORT REVIEW STATUS.(Blue Book)

NU E /

66: POLYRES: A POLYGON. BASED RICHARDS EQUA-Transformer TON SOLVER.

NUREC/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN NUREG/CR-6411: A GEOSTATISTICAL METHODOLOGY TO ASSESS SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

THE ACCURACY OF UNSATURATED FLOW MODELS.

Tranalent Worker NUREG/CR4462: FIELD TESTING PLAN FOR UNSATURATED ZONE NUREG0713 V16: OCCUPATONAL RADIATION EXPOSURE AT COM-MONITORING AND FIELD STUDIES.

MERICAL NUCLEAR POWER REACTORS AND OTHER Uranium FACIUTIES.1994. Twenty-Seventh Annual Report.

NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH.

Tr e ING-ZONE AND AREA AIR SAMPLES.

NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-Uranium MW CROPARTOULATES IN THE FACluTATED TRANSPORT OF RA-DIONUCUDES-NUREG-1531: ORAFT ENVIRONMENTAL lMPACT STATEMENT RELAT.

4 ED TO RECLAMATON OF THE URANIUM MILL TAluNGS AT THE Transportation Package ATLAS SITE,MOAB, UTAH. Source Matenal Ucense No. SUA-NUREG/CR4314: QUAUTY ASSURANCE INSPECTIONS FOR SHIP.

917, Docket No. 40-3453. (Atlas Corporaton)

PING AND STORAGE CONTAINERS.

NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-Vransportation Packag6ng PORATION MOAB MILLSource Matenal License No. SUA 017, Docket NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-No. 40-3453 (Atlas Corporaton)

ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-CORDING TO IMPORTANCE TO SAFETY.

Validation Tube Failure NUREG/CR4483: GUIDE TO VERIFICATON AND VAUDATION OF NUREG/CR4365 STEAM GENERATOR TUBE FAILURES-THE SCALE-4 CRITICAUTY SAFETY SOFTWARE.

NUREG/CR4484: GUIDE TO VERIFICATION AND VAUDATION OF Tube impectim THE SCALE-4 RADIATION SHIELDING SOFTWARE.

NUREG/CR4227: PERFORMANCE DQlONSTRATION TESTS FOR EDDY CURRENT INSPECTON OF STEAM GENERATCFI TUBING.

ValuNmpact Analysis NUREG/CR-5595 RO1: FORECAST: REGULATORY EFFECTS COST Tube Rupture ANALYSIS SOFTWARE MANUAL Version 4.1.

NUREG/lA 0130: ASSESSMENT OF RELAP5/ MOD 3.1 WITH THE LSTF G EXPER ME SlMULATING A STEAM GENERATOR TUBE Valve stor MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.

Tubing inspect 6on NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITION Valve Testing AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

NUREG/CP 0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM.

NUREG/CR4357: EVALUATON AND FIELD VAUDATON OF EDDY-CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency SPECTON.

Hotel. Washington,0C, July 1518,1996.

NUREG/CR4396: EXAMPLES.CLARIFICATONS. AND GUIDANCE ON NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR TUBING SAMPLES.

PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-SERVICE TESTING REQUIREMENTS.

TuM NUREG/CR4457: RAPID ESTIMATE OF SOLID VOLUME IN LARGE Vanadium TUFF CORES USING A GAS PYCNOMETER.

NUREG/CR4494. CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR DECONTAMINATION.

APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERESIS.

Vendorinaput e Two-Fluid Model NUREG 0040 V10 N04: UCENSEE CONTRACTOR AND VENDOR IN-NUREG/lA-0133: DEVELOPMENT.lMPLEMENTATION, AND ASSESS.

SPECTION STATUS REPORT. Quarterty Report,0ctober-December MENT OF SPECIFIC CLC3URE LAWS FOA WVERTED-ANNULAR 1995 (White Book)

FILM-BOILING IN A TWO-FLUID MODEL.

NUREG 0040 V20 N01: LICENSEE CONTRACTOR AND VENDOR IN.

SPECTION STATUS REPORT. Quarterly Report. January-March Type 8 Package 1996.(White Book)

RUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES NUREG4040 V20 NO2: UCENSEE CONTRACTOR AND VENDOR IN-USED TO TRANSPORT VARIOUS CONTENTS-SPECTON STATUS REPORT. Quarterly Report April-June 1996 (White Ultrasonic NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-Vertftcation TRASONIC INSERVICE INSPECTION SYSTEM.

NUREG/CR4483: GUOE TO VERIFICATION AND VALIDATON OF Underground Disposal THE SCALE-4 CRITICAUTY SAFETY SOFTWARE.

RUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR NUREG/CR4484: GUIDE TO VERIFICATION AND VAUDATION OF ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED THE SCALE-4 RADIATION SHIELDING SOFTWARE.

ZONE AT COMMERCIAL LOW-LEVEL RADIOAC11VE WASTE DIS-POSAL MES.

Wa8 Thicknees NUREG/CR4401: RECOMMENDATIONS FOR PROTECTING AGAINST Uniform Haza1 Spectrum FAILURE BY BRITTLE FRACTURE. Category ll And m Ferntic Steel NUREG/CRJ468: GROUND MOTION INPUT IN SEISMO EVALUATON Shipping Contasners With Wall Theckress Greater Than Four inches.

STUDIES Impacts On Rg k P

,, M Of Uniform Hazard Spectra.

Waste Burial Uneaturated Flow NUREG 1307 R06: REPORT ON WASTE BURIAL CHARGES Escalation MUREG/CR4360

SUMMARY

OF AIR PERMEABluTY DATA FROM Of Decommissaorwng Waste Disposal Costa At Low Level Waste Bunal SINGLE-HOLE INJECTON TESTS IN UNSATURATED FRACTURED Facilities.

t

70 Subject index Weste Form Leechste Wold NUREG/CR4124: CHARACTER 12ATION OF RADIONUCLIDE-CHELAT-NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE ING AGENT COMPLEXES FOUND IN LOW LEVEL RADIOACTIVE DE-TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS CONTAMINATION WASTE. Uterature Revlow.

STEEL PIPE WELDS.

Water infiltrathm Yucca Mountain NUREG/CR4918 V09: CCNTROL OF WATER INFILTRATION INTO NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-REGION.Crmcal Renew And Analyses of Tectorne Data From The periments At A Humid Regean Sne.Beltsvtile. Maryland.

Central Basm And Range.

1

NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by major NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

ADVISORY COMMITTEE (S)

NUREG-0540 V18 N01: TITLE LIST OF DOCUMENTS MADE PUBLIC.

ADVISORY COMMITTEE ON NUCLEAR WASTE LY AVAILABLE. January 1 31,1996.

NUREG-1423 V06: A COMPILATION OF REPORTS OF THE ADVISO-NUREG4540 V18 NO2: TITLE UST OF DOCUMENTS MADE PUBLIC.

RY COMMITTEE ON NUCLEAR WASTE. Jug 1995 - June 1996.

NUREG 0540 V18 NO3: TITLE LIST O'F DOCUMENTS MADE PUBUC-LY AVAILABLE. February 1-29,1996 NURE 112 17 LAT ON REP S F ADVISO-RY COMMITTEE ON REACTOR SAFEGUARDS.1995 Annual.

NUREG0 0V8 4 i L T' OF DOCUMENTS MADE PUBUC-OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)

LY AVAILABLE. April 1-30.1996.

REGION 1 (POST 820201)

NUREG-0540 V18 N05: TITLE LIST OF DOCUMENTS MADE PUBLIC-NUREG.0837 V15 N04: NRC TLD DIRECT RADIATION MONITORING LY AVAILABLE. May1 31,1996.

NETWORKProgress Report. October-December 1995.

NUREG-0540 V18 N06; TITLE LIST OF DOCUMENTS MADE PUBLIC-NUREG4837 V16 N01: NRC TLD DIRECT RADIATION MONITORING LY AVAILABLE. June 1 30,1996.

N 2: NWTL C RAD T'ON MONITORING NUR J

LY AVA LAB July 131 NUREG 0540 V18 N08: TITLE LIST OF DOCUMENTS MADE PUBUC-OFC O NT (

LY AVAILABLE August 1 31.1996.

NUREG 0940 V14N3&4P1: ENFORCEMENT ACTIONS: SIGNIFICANT NUREG-0540 V18 N09: TITLE LIST OF DOCUMENTS MADE PUBLIC-ACTIONS RESOLVED INDIVIDUAL ACTIONS.Serniannual Progress LY AVAILABLE. September 1 30,1996.

Report, July-December 1995.

NUREG 0540 V18 NIO: TITLE LIST OF DOCUMENTS MADE PUBUC-NUREG 0940 V14N384P2: ENFORCEMENT ACTONS: SIGNIFICANT LY AVAILABLE. October 1-31,1996.

ACTIONS RESOLVED REACTOR LICENSEES. Semiannual Progress NUREG-0750 V41: NUCLEAR REGULATORY COMMISSION Report, July-December 1995.

NUREG-0940 V14N3&4P3: ENFORCEMENT ACTIONS: SIGNIFICANT ISSUANCES. Opinions And Decisions Of The Nuclear Regulatory ACTONS RESOLVED MATERIAL UCENSEES. Semiannual Progress Com asson With Selected Orders. January June 1995.

NUREG4750 V42102: INDEXES TO NUCLEAR REGULATORY COM.

Report. July December 1995.

NUREG4940 V15 N1 P1: ENFORCEMENT ACTIONS: SIGNIFICANT MISSION ISSUANCES. July-December 1995.

ACTIONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress NUREG-0750 V42 N05: NUCLEAR REGUMTORY COMMISSION IS-Report. January 4une 1996.

SUANCES FOR NOVEMBER 1995. Pages 181-219.

NUREG-0940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANT NUREG-0750 V42 N06: NUCLEAR REGULATORY COMMISSION IS-ACTIONS RESOLVED REACTOR UCENSEES.Serruannual Progress SUANCES FOR DECEMBER 1995. Pages 221-258.

Report. January June 1996.

NUREG 0750 V43101: INDEXES TO NUCLEAR REGULATORY COM-NUREG 0940 V15 N1 P3: ENFORCEMENT ACTIONS: SIGNIFICANT MISSION ISSUANCES. January-March 1996.

ACTONS RESOI VED MATERIAL LICENSEES.Serruannual Progress NUREG-0750 V43102: INOFXES TO NUCLEAR REGUuTORY COM-June 1996.

MISSION ISSUANCES. January June 1996.

ApJa NUREG-0750 V43 N01: NUCLEAR REGUuTORY COMMISSION IS.

O EG 2 19 U L

EGULATORY COMMISSION OR.

SUA FOR JANUAR 1996 Pa 1

IZATION CHARTS AND FUNCTIONAL STATEMENTS. January NUR SUANCES FOR FEDRUARY 1996. Pages 13 49.

NUREG-03'25 R20: U.S. NUCLEAR REGULATORY COMMISSION OR.

NUREG-0750 V43 NO3: NUCLEAR REGULATORY COMMISSION IS-GAN12ATON CHARTS AND FUNCTIONAL STATEMENTS. July 1, SUANCES FOR MARCH 1996. Pages51-121.

1996 NUREG4750 V43 N04: NUCLEAR REGULATORY COMMISSION IS.

NUREG-0325 R21: U.S. NUCLEAR REGULATOR'l COMMISSION OR.

GANIZATON CHARTS AND FUNCTIONAL STATEMENTS. August SUANCES FOR APRIL 1996.Page 123-210.

NUREG-0750 V43 N05: NUCLEAR REGULATORY COMMISSION IS-19,1996.

NUREG 1518: DIFFERING PROFESSIONAL VIEWS OR OPIN.

SUANCES FOR MAY 1996.

NUREG4750 V43 N06: NUCLEAR REGULATORY COMMISSION IS.

ONS.1994 Special ReWw Panel SUANCES FOR JUNE 1mm.

I I

EDO OFFICE OF ADWNtSTRATPON (PRE 870413 & POST 890205)

NUREG4750 V44 N01: NUCLEAR REGULATORY COMMISSION IS-i OFFICE OF ADMINIS"RATON, DIRECTOR (POST 940714)

SUANCES FOR JULY 1996.Pages 1-57.

NUREG-1145 V12: U.% HUCLEAR REGULATORY COMMISSION NUREG 0750 V44 NO2: NUCLEAR REGULATORY COMM!SSION IS.

OlVis OF E

C INFORMATION & FUBUCATONS SERV.

NUREG V 4 NO3 N R GULA ORY COMMISSION IS-SUANCES FOR SEPTEMBER 1996. Pages79-106.

NUREG-0304 V20 NO3: REGULATORY AND TECHNICAL REPORTS NUREG 0750 V44 N04: NUCLEAR REGULATORY COMMISSION IS-

{

(ABSTRACT INDEX JOURNAL). Compilaton For Third Quarter SUANCES FOR OCTOBER 1996. Pages 107-228.

1995, July-September NUREG-0936 V14 NO2: NRC REGULATORY AGENDA.Sermannual NUREG 0304 V20 N04: REGULATORY AND TECHNICAL REPORTS Report. July-December 1995.

(ABSTRACT INDEX JOURNAL). Annual Compilation For 1995.

NUREG-0304 V21 NOI: REGULATORY AND TECHNICAL REPORTS NUREG 0936 V15 N01: NRC REGULATORY AGENDA. Semiannual (ABSTRACT INDEX JOURNAL). Compilation For Frst Ouarter Report. January-June 1996.

1996 January-March.

NUREG-0304 v21 NO2: REGULATORY AND TECHNICAL REPORTS EDO OFFICE OF THE CONTROLLER (PPE 820418 & POST 890205)

OFFICE OF THE CONTROLLER (POST 090205)

(ABSTRACT INDEX JOURNAL). Compilation For Second Quarte, NUREG-1542 V01: ACCOUNTABlWTY REPORT FISCAL YEAR 1995.

1996, April-June.

NUREG-0540 V17 N11: TITLE UST OF DOCUMENTS MADE PUBUC-DIVISION OF BUDGET & ANALYSIS (POST 890205)

NUREG 1100 V12: BUDGET ESTIMATE S. Fiscal Year 1997, LY AVAILABLE. November 1 30, 1995.

NUREG-0540 V17 N12: TITLE UST OF DOCUMENTS MADE PUBLIC.

NUREG-1350 V0t NUCLEAR REGULATORY COMMISSION INFOR-LY AVAILABLE. December 1 31,1995.

MATION DIGEST.1996 Editon.

71

72 NRC Originating crganizabn 8 ' : 1x (Staff Reports)

EDO OFFICE FOR ANALYSIS & EVALUAT10N OF C'6 MONAL NUREG-1565: DRY OXIDATION AND FRACTURE OF LWR SPENT DATA FUEL OFFICE FOR ANALYSIS & EVALUATION OF OPERA

,.4AL DATA, Dl-RECTOR U S. NUCLEAR REGULATORY COMMISSION NUREG 0000 V18 NO2: REPORT TO CONGRESJ ON ABNORMAL OFFCE OF THE GENERAL COUNSEL (POST 860701)

OCCURRENCES. April June 1995.

NUREG4386 D07: UNITED STATES NUCLEAR REGULATORY COM-NUREG4090 V18 rarJ: REPORT TO CONGRESS ON ABNORMAL MISSION STAFF PRACTICE AND PROCEDURE OCCURRENCES. July September 1995.

DIGEST.Commesson. Appeal Board And ucensing Board NUREG-1272 V09 N01: OFFCE FOR ANALYSIS AND EVALUATION Declaions. July 1972 June 1995.

OF OPERATIONAL DATA.1994-FY 95 Annual Report - Reactors.

OFFCE OF THE INSPECTOR GENERAL (POST 890417)

NUREG 1272 V09 NO2: OFFICE FOR ANALYSIS AND EVALUATION NUREG 1415 VOS NO2-OFFICE OF THE INSPECTOR OF OPERATIONAL DATA.1994-FY 95 Annual Report Nuclear Ma-GENERALSerrmannual Report To Congress. October 1,1995 March tortale.

31.1996.

NUREG-1272 V09 N03: OFFCE FOR ANALYSIS AND EVALUATON NUREG 1415 V09 NO1: OFFICE OF THE INSPECTOR OF OPERATIONAL DATA.1994 FY Annual Report. Technical Train.

GENERALSerr5nnual Report To Congress, April 1,1996 - Ssptem-N-

bor 30,1996.

EDO OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

(POST $61109) ORMATION DIVISION OF ENGINEERNG TECHNOLOGY (POST 941217)

OFFICE OF INF RESOURCES MANAGEMENT (PUST NUREG 0933 S20: A PRIORITI2ATION OF GENERIC SAFETY 890205)

ISSUES NUREG-0020 V20: UCENSED OPERATING REACTORS STATUS NUREG-0933 S21: A PRIORITIZATION OF GENERIC SAFETY

SUMMARY

REPORT.Deta As Of December 31.1995.(Gra Book ISSUES NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE 0 02 SO C

S VE DS DISP 1 TION SCHEDULE-U 8

8-OfVISION OF REGaATORY APPLICATIONS (POST 941217)

EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG 0713 V10 OCCUPATONAL RADATION EXPOSURE AT OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS COMMERICAL RC. EAR POWER REACTORS AND OTHER NUREG-0383 V01 R19: DIRECTORY OF CER TIFICATES OF COMPU-FACluTIES.1994 Twe ity-Seventh Annual Report.

ANCE FOR RADIOACTIVE MATERIALS PACKAGES. Report Of NRC NUREG-1307 F# 6:

REPORT ON WASTE BURIAL Approved Packages.

CHARGES.Escalme.t Of Dm.. ~.

Weste Deposal Costs At NUREG-0383 V02 R19: DIRECTORY OF CERTIFICATES OF COMPU-Low-Level Waste Burial Facilities.

ANCE 50R RADIOACTIVE MATERIALS PACKAGES. Certificates Of NUREG-1437 V01: GENERC ENVIRONMENTAL lMPACT STATE-Cornpliance.

MENT FOR UCENSE RENEWAL OF NUCLEAR PLANTS. Man NUREG-0383 V03 R16: DIRECTORY OF CERTIFICATES OF COMPU-Report ANCE FOR RADIOACTIVE MATERIALS PACKAGES Report Of NRC NUREG-1437 V02: GENERC ENVIRONMENTAL lMPACT STATE-Approved Quanty Assurance Programs For Radioactive Materials MENT FOR UCENSE RENEWAL OF NUCLEAR Packa s.

PLANTS.Appereces.

NUREG 30 V15: UCENSED FUEL FACluTY STATUS NUREG 1440- REGULATORY ANALYSIS FOR AMENDMENTS TC REPORT. inventory Dfference Data. July 1,

1994 - June 30, REGULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RE-1995.(Gray Book 11).

NEWAL OF NUCLEAR POWER PLANT OPERATING NUREG 0725 R11: PUBLIC INFORMATION CIRCULAR FOR SHIP-UCENSES. Final Report MENTS OF IRRADIATED REACTOR FUEL.

NUREG 1529 VO1: PUBLO COMMENTS ON THE PROPOSED 10 CFR NUREG 1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-SPENT FUEL STORAGE SYSTEMS. Draft Report For Comment.

ERATING UCENSES AND SUPPORTING DOCUMENTS: REVIEW NUREG 1567 DRFT FC: STANDARD REVIEW PLAN FOR SPENT OF CONCERNS AND NRC STAFF RESPONSE.Executsve Summary.

FUEL DRY STORAGE FACluTIES. Draft R For Comment.

NUREG 1529 V02: PUBUC COMMENTS ON THE PROPOSED 10 CFR DMSON OF INDUSTRIAL & MEDICAL N R SAFETY (POST PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.

N G 539-METHODOLOGY AND FINDINGS OF THE NRC'S MA-OF CONCERNS AND NRC STAFF RESPONSE.Appendees.

NURE DR

PR ESS D S GN FOR CONSOUDAT.

NUREG 1575 DAFT FC: MULTI-AGENCY RADIATION SURVEY AND ING AND UPDATING MATERIALS UCENSING GUIDANCE. Draft SITE INVESTIGATION MANUAL (MARSSIM). Draft For Pubiac Com-Repnrt For Comment

- "I-NUREG-1550 STANDARD REVIEW PLAN FOR APPUCATIONS FOR NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION If(TO SEALED SOURCE AND DEVICE EVALUATIONS AND REGISTRA-NEAR SURFACE LLW DSPOSAL UN!TS. Progress Report On Fivid TiONS EvreMmer.a At A Humid Region Site.Bettsville. Maryland.

NUREG-1551: FINAL REPORT OF THE NRC-AGREEMENT STATE WASTE MANAGEMENT BRANCH (POST 941217)

WORKING GROUP TO EVALUATE CONTROL AND ACCOUNT-NUREG/CR-6462: FIELD TESTING PLAN FOR UNSATURATED ZONE ABluTY OF UCENSED DEVICES MONITORING AND FIELD STUDIES.

NUREG-1556 V01 DR FC: CONSO' DATED GUIDANCE ABOUT MA-DIVISION OF SYSTEMS TECHNOLOGY (POST 941217)

U NURFG-0700 ROI V01: HUMAN-SYSTEM !NTERFACE DESION g,~' ~ 'LS UCEwere p-UcenseabaYRhy " Wcs Abwt REVIEW GUIDELINES. Process And Guidelines. Final Report Tma e

Ntable OPERA S BRANCH NUREG-0700 R01 V02: HUMAN-SYSTEM INTERFACE DESIGN NUREG4525 V02 R04: SAFEGUARDS

SUMMARY

EVENT LIST REVIEW GUIDELINES. Reviewer's CheckhstFinal Report.

(SSEL). January 1.1990 Through December 31.1995.

NUREG-0700 R01 V03: HUMAN-SYSTEM INTERFACE DISIGN DIVISION OF WASTE MANAGEMENT (NMSS 940403)

REVIEW GUIDEUNES. Review Software And User's Guide. Final NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RE.

Report LATED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN THE ATLAS SITE.MOAB. UTAH. Source Matenal Ucense No. SUA.

ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE 017. Docket No. 40-3453. (Atlas Corporation)

CURRENT UNDERSTANDING OF BROADER FUEL COOLANT NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE INTERACTION ISSUES. Report Of The Second Steam Explosion PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS Review Group Workshop.

CORPORATION MOAB MILLSource Matertal Ucense No. SUA.

NUREG-1560 V1 P1 DFC: INDMOUAL PLANT EXAMINATION PRO-917. Docket No. 40-3453 (Atlas CorporatKm)

GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT NUREG 1543: ORAFT ENVIRONMENTAL IMPACT STATEMENT DE-PERFORMANCE. Summary ReportDraft Report For Comment COMMISSIONING OF THE SHIELDALLOY METALLURGICAL NUREG 1560 V2P2-5DFC: INDIVIDUAL PLANT EXAMINATION PRO-CORPORATION. CAMBRIDGE. OHIO. FACILITY. Docket No. 40 GRAM: PER5PECTIVES ON REACTOR SAFETY AND PLANT 8948.Ucense No. SMB-1507.

PERFORMANCE. Parts 2-5. Draft Report For Comment.

NUREG 1563: BRANCH TECHNICAL POSITION ON THE USE OF NUREG/CR4189: A SIMPUFIED MODEL OF AEROSOL REMOVAL EXPERT EUC!TATION IN THE HIGH-LEVEL RADOACTIVE WASTE BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

PROGRAM.

NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG-1564: LONG TERM KINETIC EFFECTS AND COLLOID FOR-MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR MATIONS IN DISSOLUTION OF LWR SPENT FUEL GE SBWR.

I l

1 1

1

NRC Originating Organization index (Staff Reports) 73 NUREG/CR4350: A TECHNIOUE FOR HUMAN ERROR ANALYSIS NUREG-1511 S01: REACTOR PRESSURE VESSEL STATUS REPORT.

(ATHEANA).Tedimcel Beam And Wetbattrenny Deecnpt ort NUREG-1537 PT01: GUIDELINES FOR PREPARING AND REVIEW.

500 N OF NUCLEAR REACTOR REGULATION T 000428)

ING APPUCATIONS FOR THE LICENSING OF NON-POWER REACTORS. Pert 1: Format And Content.

NUREG N

ICENSEE C RACT AN IN-NUREG 1537 PT02: GUIDELINES FOR PREPARING AND REVIEW.

SPECTION STATUS REPORT. Quarterty Report, October-December ING APPUCATIONS FOR THE LICENSING OF NON. POWER REACTORS. Pert 2: Standard Review Plan And Cetterte.

N G 0040 V 1: LICENSEE CONTRACTOR AND VENDOR IN-O TE

^

SPECTION STATUS REPORT. Quarterty Report,Jenuary-March g

EPOR l ERGRA ULAR ST' ESS COR-R ROSION CRACKING OF BWR CORE SHROUDS AND OTHER IN-N G4040 V

. LICENSEE CONTRACTOR AND VENDOR IN-CT ATUS REPORT. Quarterly M NU G-54 OGY FOR DEVELOPtNG AND IMPLE.

ge8 MENTING ALTERNATIVE TEMPERATURE-TIME CURVE FOR NUREG 0300 V10- OPICAL REPORT REVIEW STATUS.(Blue Book)

TESTING THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR NUREG-0064 R182 DFC: CRITERIA FOR PREPARATION AND EVAL.

POWER PLANT APPLICATIONS.

UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER POWER PLANTS.

PLANTS.Crtnerte For Ernergency Plannsig in An Early Site Permit NUREG-1557:

SUMMARY

OF TECHNICAL INFORMATION AND

.Dren Report For Comment.

AGREEMENTS FROM NUCLEAR MANAGEMENT AND RE.

G4064 R183 DFC: CRITERIA FOR PREPARATION AND EVAL.

SOURCES COUNCIL INDUSTRY REPORTS ADDRESSING Ll-UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER CENSE RENEWAL.

NUREG-1561: STANDARD REVIEW PLAN MAINTENANCE PRO-PLANTS.Catteria For Protoceve Action Recommendatione For Severe GRAM IMPLEMENTING PROCEDURES DOCUMENT.

NUREG 0000 DRPr FC: STANDARD REVIEW PLAN FOR THE NUREG-1568: LICENSE RENEWAL DEMONSTRATION PROGRAM:

Acddents.Dren Report For....

REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAH NRC 06SERVATIONS AND LESSONS LEARNED.

NUREG/CP 0152: PROCEEDINGS OF THE FOURTH NRC/ASME POWER PLANTS. LWR Edition. Draft Report For Comment.

NUR8.G-0847 S20: SAFETY EVALUATION REPORT RELATED TO SYMPOSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND Hoted, Ween'ngton,DC, July 15-18,1996.

NUR G/ 4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC

2. Docket Nos. 50 300 And 50 391.(Tenneesee VeNey Authority)

NUREG-1214 R14: HISTORICAL DATA

SUMMARY

OF THE SYSTEM-INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER ATIC ASSESSMENT OF LICENSEE PERFORMANCE PLANT OPERATIONS AND MAINTENANCE COSTS.

I t

C

NRC Originating Organization index (International Agreements)

This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

EDO OFFICE OF NUCLEAR REQULATORY RESEARCH (POST 820406)

NUREG/lA 0132: IMPROVEMENTS TO THE RELAP5/ MOO 3 RE-OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 941217)

FLOOD MODEL AND UNCERTAINTY OUANTIFICATION OF RE.

NUREG/lA4129 POI: AN ASSESSMENT OF THE CORCON-MOD 3 FLOOD PAK CLAD TEMPERATURE.

NUREG/lA-0133: DEVELOPMENT,lMPLEMENTATlON, AND ASSESS.

CODE.Part i: TwHydraulic Calculations.

NUREG/lA4130: ASSESSMENT OF RELAPS/ MOO 3.1 WITH THE MENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-ANNULAR

^

" ^^

NU EG 1 :

SSME R

5/ MOD 3.1 FOR GRAVl-OR E R PTURE T AN E NUREG/lA4131: ASSESSMENT OF'RELAPS/ MOD 3 USING BETHSY TY-DRIVEN INJECTEN EXPERIMENT IN THE CORE MAKEUP 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

NU EG/

-0 YS P RONE PO-IC 2 EX-PER! MENT BY RELAP5/ MOO 3 CODES.

I 75

- - - - - - - - - -. - _ _ - _ _. _ _. _ - _ _ _, _ _j

o

NRC Contract Sponsor index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) areaared by that organi-zation if further information is needed, refer to the main citation by t1e NUREG/CR number.

EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS DATA SCAUNG MODELS TO THE DUCTILE TO-BRITTLE TRANSITON.

DIVISION OF SAFETY PROGRAMS ' POST 870413)

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CON-NUREG/CR 6365: STEAM GENERATOR TUBE FAILURES.

STRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T)

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN SPECIMENS.

SAFETY-RELATED COMPONENTS.

NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF SELECTED AEA/UCS8 MODEL FECUMN ALLOYS.

EDO OFFICE OF NUCLEAR MATERIAL SAFETV & SAFEGUARDS NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS MOTORS IN NUCLEAR POWER PLANTS'TS FROM THE NUREG/CR4314: QUALnY ASSURANCE INSPECTIONS FOR SHIP-NUREG/CR4337:

SUMMARY

OF RESUI PING AND STORAGE CONTAINERS.

ROUND-ROBIN ANALYSES l

NUREG/CR4483: GUIDE YO VERIFICATION AND VAUDATION OF NUREG/CR4339: AGING AS'SESSMENT OF WESTINGHOUSE PWR AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION NU EG CR U DE O 9 CA ION A VAUDATION OF NU E CR AGING ASSESSMENT OF SURGE PROTECTIVE NUR G CR 7C T NAL TYPE B PACK.

NU G T

3D FT UT SYSTEM EVALUATION PRC M MANA T POL D EL E T & ANALYSIS NU EG EVALUATION AND FIELD VAUDATON OF EDDY.

NUR 91 COMMENDATIONS FOR PROTECTING CUR ARRAY PROBES FOR STEAM GENERATOR TUBE IN-AGAINST FAILURE BY BRITTLE FRACTURE. Category 11 Ard ill Fer.

ntic Steel SNppm9 Contanors With Wall Thckness Greater Then NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL.

DIVISON l'NDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NUR /CR 5: TRA N TE AND INERTIAL EFFECTS ON NI G 4074 V02: SEALED SOURCE AND DEVICE DESIGN N

CR FA G ALLO S AND 690 SAFETY TESTING. Technical Report On The Findings Of Task 4 in-IN SIMULATED LWR ENVIRONMENTS.

NUYE CR 5 A A O

S ES FOR RADIOPHAR-NUREG/CR4384 V01: UTERATURE REVIEW OF ENVIRONMENTAL QUAUFICATON OF SAFETY-RELATED ELECTRIC MACEUTICALS NUREG/CR4407': CLASSIFICATON OF TRANSPORTATION PACK-N EG VO ER RE REVIEW OF ENVIRONMENTAL AGING AND DRY SPENT FUEL STORAGE SYSTEM COMPO-QUAUFICATION OF SAFETY RELATED ELECTRC NENTS ACCORDING TO IMPORTANCE TO SAFETY.

EShm W Ard W.

NUREG/CR4413: ANALYSIS OF THE 1RRADIATON DATA FOR EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820406)

DIVISON OF ENGINEERING TECHNOLOGY (POST 941217)

A3028 AND A5338 CORRELATION MONITOR MATERIALS.

NUREG/CR-2000 S05: GUIDEUNES FOR NUCLEAR POWER PLANT NUREG/CR4415: APPUCATIONS OF REUABluTY DEGRADATION SAFETY ISSUE PRORIT12ATON INFORMATION DEVELOPMENT.

ANALYSIS.

NUREG/CR-4219 V11 N2 HEAVY-SECTION STEEL TECHNOLOGY NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER L

PROGRAM. Semiannual Progress Report For April-September 1994.

PLANT REINFORCED CONCRETE STRUCTURES.

i NUREG/CR-4219 V12 N1: HEAVY-SECTON STEEL TECHNOLOGY NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC r

PROGRAM.Sermannual Progress Report For October 1994 - March RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES f

1995.

IN NUCLEAR POWER PLANTS.

NUREG/CR4667 V20: ENVIRONMENTALLY ASSISTED CRACKING NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE IN UGHT WATER REACTORS. Sermannual Report,0ctobw 1994 TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS March 1995.

STEEL PIPE WELDS.

NUREG/CR-4667 V21: ENVIRONMENTALLY AS$1STED CRACKING NUREG/CR4432 ESTIMATED NET VALUE AND UNCERTAINTY IN UGHT WATE'R REACTORS. Sermannual Report. April 1995 - De-FOR AUTOMATING ECCS SWITCHOVER AT PWRS.

cember 1995.

NUREG/CR4438: THE EFFECT OF CYCUC AND DYNAMC LOADS NUREG/CR-5068: PlPING INSPECTON ROUND ROBIN.

ON CARBON STEEL PIPE.

NUREG/CR-5442: REUABILITY-BASED CONDITON ASSESSMENT NUREG/CR4439: DESIGN OF THE iPIRG-2 SIMULATED SEISMIC OF STEEL CONTAINMENTS AND LINERS.

FORCING FUNCTION.

NUREG/CR-5591 V06 N2: HEAVY-SECTION STEEL IRRADIATION NUREG/CR4440: THE EFFECTS OF CYCLIC AND DYNAMIC LOAD-PROGRAM.Sermannual Progress Report For April Through Septem.

ING ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING bor 1995.

STEELS. Technical Report October 1992 April 1996.

NUREG/CR-5753. AGING OF SAFETY CLASS 1E TRANSFORMERS NUREG/CR4443: DETERMINISTIC AND PROBAB!LISTIC EVALUA-IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN NUREG/CR-59tl5 Sot: REVIEW OF P-SCAN COMPUTER-BASED UL-LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATONS.

TRASONIC INSERVCE INSPECTON SYSTEM.

NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITON SURFACE CRACKED ELBOWS.

AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATON SCHEME NUREG/CR4202: LONG-TERM AGING AND LOSSOF COOLANT FOR INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE ACCIDENT (LOCA) TESTING OF ELECTRICAL CABLES.U.S./

CRACKS IN ELBOWS.

French Cooperative Research am.

NUREG/CR4448 VOI: EVALUATION OF NATONAL SEISMOGRAPH NUREG/CR4227: PERFORMA - DEMONSTRATION TESTS FOR NETWORK DETECTION CAPABluTIES. Annual Report, July 1994 -

EDDY CURRENT INSPECTON OF STEAM GENERATOR TUBING.

July 1995.

NUREG/CR4246: EFFECTS OF AGING AND SERVCE WEAR ON NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR MAIN STEAM ISOLATON VALVFS AND VALVE OPERATORS.

TUBING SAMPLES.

77

78 NRC Contract Sponsor index NUREG/CRo460 CSNI PROJECT FOR FRACTURE ANALYSES OF NUREG/CR4429' THE ROLE OF ORGANIC COMPLEXANTS AND Mi-LARGE-SCALE INTFRNATONAL REFERENC3 EXPERIMENTS CROPARTICULATES IN THE FACluTATED TRANSPORT OF RA-(FALSIRE II).

DIONUCLIDES.

NUREG/CR4466: GROUND MOTON INPUT IN SEISMIC EVALUA-NUREG/CR4450- CHARACTERl2ATON OF CONTAMINATION TION STUDIES.lmpacts Of Arbficial Time History input On in-Strue.

THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND ture Demand Spectra.

DIGITAL IMAGE PROCESSING.

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-NUREG/CR4457: RAPID ESTIMATE OF SOLIO VOLUME IN LARGE TON ON CONSERVATISM AND VARIABluTY IN SEISMIC RISK TUFF CORES USING A GAS PYCNOMETER.

ESTIMATES.

NUREG/CR4458: MOISTURE CHARACTERISTIC CURVES FOR NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUA-APACHE LEAP TUFF: TEMPERATURE EFFECTS AND HYSTERE-TION STUDIES.lmpacts On Risk Assessment Of Uniform Hazard ses.

NU

/CR4473: GLOBAL POSITONING SYSTEM REOBSERVA-M i OR N

ELD S lE TONS OVER THE EASTERN UNGED STATES STRAIN MONITOR-NUREG/CR4492: BLT-MS (BREACH. LEACH, AND TRANSPORT-MULTIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For NI

/ 4495 CASE STUDY OF UQUEFACTON INDUCED BY D

THE 1944 MASSENA, NEW YORK CORNWALL, ONTARIO Was FW EARTHOUAKE NUREG/CR4494: CONTINUOUS ANALYSIS FOR VANADIUM IN DIVISION OF REGULATORY APPLICATONS (POST 941217)

NUREG/CR-4918 V09. CONTROL OF WATER INFILTRATON INTO LOMI DEMAMINATON.

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field N EG/CR 5 ELAP5/ OD3 CODE NUR 52 ELWYS ME G ONS: LOW.

MANUALSummanes And Reviews Of independent Code Assess.

^

NU E 189-A ? WUFIED MODEL OF AEROSOL REMOVAL Y R 99 lR NUREG/CR-5595 RO1: FORECAST: REGULATORY EFFECTS COST BY NATURAL PRO'1SSES IN REACTOR CONTAINMENTS.

ANALYSIS SOFTWARE MANUAL Version 4.1.

NUREG/CR4210 COMPUTER CODES FOR EVALUATION OF CON-NUREG/CA.5631 A02: CONTRIBUTION OF MATERNAL RADONU.

TROL ROOM HABITABluTY (HABIT).

CLICE BURDENS TO PRENATAL RADIATION DOSES.

NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR EXPERIMENTS.Results And Lessons Leamed.

GE SBWR.

NUREG/CR4124: CHARACTERIZATION OF RADIONUCUDE CHE.

NUREG/CR4338: RESOLUTON OF THE DIRECT CONTAINMENT LATING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOAC-HEATING IESUE FOR ALL WESTINGHOUSE PLANTS WITH TIVE DECONTAMINATION WASTE. Uterature Revew.

LARGE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAIN.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING MENTS.

FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS STATON. Effects Of Current Regulatory And Other Considersbons (ATHEANA. Technic 9 9 asis And Me Deson'ption.

On The Financial Assurance Requirements Of The Deconmssiorung NUREG/CR4 406: ENVIHONMENTAL TESTI OF AN EXPERIMEN-Rule And.

TAL DIGIT. L SAFETY CHANNEL NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSONING NUREG/CR4422-POWER EXCURSION ANALYSIS FOR HIGH FOR THE REFERENCE BOILING WATER REACTOR POWER BURNUP CORES.

STATION Effects Of Current Regulatory And Other Considerations NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND On The Financial Assurance Requirements Of The Decommissioning RADIO. FREQUENCY INTERFERENCE LEVELS IN NUCLEAR Rule And..

POWER PLANTS.

NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NUREG/CR4463; REVIEW GUIDEUNES ON SOFTWARE LAN-PART 61 AND OTHER SELECTED RADIONUCUDES.uterature GUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY Review.

SYSTEMS Final Report.

NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATONS: LOW.

NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALY.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIME.

SIS OF CONTROL SOFTWARE IN ADVANCED REACTORS.

TER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

NUREG/CR4476: CIRCUIT BRIDGING OF COMPONENTS BY NUREG/CR4270- ESTIMATING BOluNG WATER REACTOR DE-SMOKE.

COMMISSIONING COSTS.A User's Manual For The BWR Cost Ests mating Computer Program (CECP) Software Final Report.

EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)

NUREG/CR4280- TECHNOLOGY, SAFETY.AND COSTS OF DECOM-OFFICE OF NUCLEAR REACTOR REGULATON (POST 941001)

MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER.

NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOAC.

ENCE SEALED SOURCES.

TIVE RELEASES FROM NUCt EAR POWER PLANT NUREG/CR4341: MICROBIAL DEGRADATION OF LOW LEVEL RA.

SITES. Methodology And Data Base.

DIOACTIVE WASTE. Final Report.

NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOAC-NUREG/CR4346: HYDROLOGIC EVALUATON METHODOLOGY TIVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATU.

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR RATED ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE POWER INDUSTRY. Annual Summary Of Program Performance Re-WASTE DISPOSAL SITES.

ports CY 1995.

I NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER

)

i, RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELAT.

GUIDANCE CITED IN REGULATORY DOCUMENTS.

ED DOCUMENTS.

NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.

NUREG/CR4360:

SUMMARY

OF AIR PERMEABlUTY DATA FROM NUREG/CR4396: EXAMPLES.CLARIFICATONS, AND GUIDANCE SINGLE-HOLE INJECTON TESTS IN UNSATURATED FRACTURED ON PREPARING REQUESTS FOR REUEF FROM PUMP AND TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF VALVE INSERVICE TESTING REQUIREMENTS.

STEADY STATE TEST INTERPRETATON.

NOREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR NUREG/CR4366: POLYRES: A POLYGON-DASED RICHARDS COMMERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR j

1 EQUATON SOLVER.

APPUCATIONS.

NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-LIVES FCR RA.

NUREG/CR4430 SOFTWARE SAFETY HAZARD ANALYSIS.

f DIOLABELED ANTIBODIES AND RELATED ISSUES.

NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMsC NUREG/CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER JOINTED ROCK MASS.

PLANT OPERATONS AND MAINTENANCE COSTS.

NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUS-STRENGTH OF LOW-LEVEL RADCACTIVE WASTE FORMS.

TRY: UPDATE OF THE TECHNICAL ISSUES 1996.

l NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4489

SUMMARY

OF FAILURE ANALYSIS ACTIVITIES i

REGION Cntical Review And Anaryses of Tectonic Data From The AT BROOKHAVEN NATONAL LABORATORY.

Central Basin And Range.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS LESSONS LEARNED (GALL). Main Report And Appendix A.

THE ACCURACY OF UNSATURATED FLOW MODELS.

NUREG/CR4400 V02: NUCLEAR POWER PLANT GENERIC AGING NUREG/CR4419-SOLUBILITY TESTING OF ACTINIDES ON LESSONS LEARNED (GALL). Appendix B.

BREATHING-ZONE AND AREA AIR SAMPLES.

NUREG/CR4500: OWNERS OF NUCLEAR POWER PLANTS.

Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.

NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR ADVANCED SYSTEMS TECHNOLOGY, INC.

INTERNAL CIRCUMFERENTIAL AND AX1AL SURFACE CRACKS IN NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED ELBOWS.

DOCUMENTS.

BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST AMERICAN SOCIETY OF MECHANICAL ENGINEERS LABORATORY NUREG/CP 0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM-NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

Hotel. Washington.DC, July 15-18,1996.

NUREG/CR 2850 Soi: DOSE COMMfTMENTS OUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES Methodology ARGONNE NATIONAL LABORATORY And Data Base.

NUREG 1557:

SUMMARY

OF TECHNICAL INFORMATION AND NUREG/CR 2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE AGREEMENTS FROM NUCLEAR MANAGEMENT AND RESOURCES RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.

i

)

COUNCIL INDUSTRY REPORTS ADDRESSING LICENSE RENEWAL NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.

NUREG/CR-4667 V20- ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-j UCHT WATER REACTORS. Semiannual Report, October 1994 March CUDE BURDENS TO PRENATAL RADIATION DOSES.

NUREG/CR 4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR 5758 V08: FITNESS FOR DUTY IN THE NUCLEAR POWER 1995.

INDUSTRY. Annual Summary Of Program Performance Reports CY UGHT WATER REACTORS. Semisnnual Report, April 1995 - December 1995.

NUREG/CR-5229 V08: FIELD LYSJMETER INVESTIGATIONS: LOW-NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID-1995.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR ANCE CITED IN REGULATORY DOCUMENTS.

FISCAL YEAR 1995. Annual Report.

NUREG/CR-5985 S01: REVIEW OF P SCAN COMPUTER-BASED UL-NUREG/CR4256 V03: FIELD LYSNETER INVESTIGATIONS: LOW

TRASONIC INSERVICE INSPECTION SYSTEM.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NUREG/CR-6124: CHARACTERIZATION OF RADIONUCLIDE-CHELAT-"

NU

/CR 83 R

GUE AL C 600 AND 690 IN CONTAMINATION WASTE. Uterature Review.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMM:SSIONfNG NU C

8 EF S

ERMAL AGING ON FRACTURE FOR THE REFERENCE BOluNG WATER REACTOR POWER TOUGHNESS AND CHARPY lMPACT STRENGTH OF STAINLESS STATION Effects Of Current Regulatory And Other Considerations On STEEL PIPE WELDS.

The Financial Assurance Requirements Of The Decommissioning Rule NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING And_

LESSONS LEARNED (GALL) Main Report And Appendix A.

NUREG/CR4490 V02: NUCLEAR POWER PLANT GENERIC AGING NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING FOR THE REF ERENCE BOILING WATER REACTOR POWER LESSONS LEARNED (GALL). Appendix B.

STATION. Effects & Current Regulatory And Other Consa$erations On The Financial Assurance Requirements Of The Decommissioning Rule AHIZONA, UNIV. OF, TUCSON, AZ NUREG/CR4096:

APACHE LEAP TUFF INTRAVAL And....

EXPERIMENTS.Results And Lessons Learned-NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF CON-NUREG/CR4360:

SUMMARY

OF AIR PERMEABluTY DATA FROM TROL ROOM HABITABILITY (HABIT).

S'NGLE-HOLE INJECTICN TES1S IN UNSATURATED FRACTURED NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.

NUREM-6230: RADOANAWAL TECmW NA M N NU CR 57 P

Tl AE SOUD VOLUME IN LARGE TUFF CORES USING A GAS PYCNOMETER.

Review.

NUREG/CR4458: MOISTURE CHAR / $TFPMIC CURVES FOR NUREG/CR4270: ESTIMATING BOlUNG WATER REACTOR DECOM-APACHE LEAP TUFF: TEMPERATFTJ ? fih;TS AND HYSTERESIS.

MISSIONING COSTS.A User's Manual For The BWR Cost Estimating NUREG/CR4462: FIELD TESTING PLV bOR UNSATURATED ZONE Computer Program (CECP) Software. Final Report MONITORING AND FIELD STUDIF NUREG/CR4280: TECHNOLOGY SAFETY,AND COSTS OF DECOM-MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-ASCA, INC NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS ENCE SEALED SOURCES.

OF CONTROL SOFTWARE IN ADVANCED REACTORS.

NUREG/CR4344: REAL TIME 3-D SAFT-UT SYSTEM EVALUATION AND VALIDATION.

BATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR NUREG/CR4337:

SUMMARY

OF RESULTS FROM THE IPIRG.2 ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED

^

NUR G/ 44 : H FFECT OF CYCUC AND DYNAMIC LOADS ON k^STE NUREG/CR-6368 POLYRES: A POLYGON-BASED RICHARDS EQUA.

IGN OF THE IPIRG-2 SIMULATED SEISMIC TION SOLVER.

NU E / R FORCING FUNCTION NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS NUREG/CR-6440- THE ETFECTS OF CYCUC AND DYNAMIC LOADING THE ACCURACY OF UNSATURATED FLOW MODELS.

ON THE FRACTURE RESISTANCE OF NUCLEAR PIPING NUREG/Ch4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-STEELS Technical Report October 1992 Anni 1996 CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-NUREG/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA-OIONUCLIDES.

TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-LEAK BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS NUREG/CR4444: FRACTURE BEHAVIOR OF CIRCUMFERENTIALLY CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER Pt. ANT OPERATIONS AND MAINTENANCE COSTS.

SURFACE CRACKED ELBOWS.

i 79

l 80 Contractor Index l

BATTELLE SEATTLE RESEARCH CENTER COMMERCE DEPT. OF, NATIONAL OCEANIC & ATMOSPHERIC NUREG/CR 5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER ADMINISTRATION INDUSTRY. Annual Summary Of Program Performance Reports CY NUREG/CR4473: GLOBAL POSITONING SYSTEM REOBSERVA-1906.

TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR.

NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

ING NETWORK.

UPDATE OF THE TECHNICAL ISSUES 1996.

ECODYNAMICS RESEARCH ASSOCIATES,INC.,

SROOKHAVEN NATIONAL LABORATORY NUREG/CR4492: BLT MS (BREACH LEACH, AND TRANSPORT-MUL-NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Sarnulat-ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE ing Release Of Contaminant From Subsurface Low Level Waste Dis-CURRENT UNDERSTANDING OF BROADER FUELCOOLANT posal Facility.

n' a

w

(

FEDERAL EMERGENCY MANAGEMENT AGENCY NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY THIRD NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL.

WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses.

UATON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND sion. Hegh Burnup Fuel Behavior, Thermal Hydraulic Research.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CP 0149 V02-PROCEEDINGS OF THE TWENTY THIRD PLANTS.Crttena For Emergency Planning in An Earty Site Permst WATER REACTOR SAFETY INFORMATION MEETING. Human Factors Application. Draft Report For Comment.

Research, Advanced l&C Hardware & Software, Severe Accwient Re.

NUREG4654 R1 S3 DFC: CRITERIA FOR PREPARATON AND EVAL-search, Probabilistic Risk Assessment Topics, Individual Plant Examina-UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND bon.

PRCPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CP.0149 V03: PROCEEDINGS OF THE TWENTY-THIRD PLANTS.Cntena For ProtectNe Actson Recommendations For Severe WATER REACTOR SAFETY INFORMATON MEETING. Structural &

Accidents. Draft Report For....

Seesmic En@neenng, Pnmary Systems integrtty, Equipment Operability FLORIDA, UNIV. OF GAINESVILLE, FL' NU G 5

ELD MET ES OW-NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-LEVEL WASTE DATA SASE DEVELOPMENT PROGRAM FOR VICES IN NUCLEAR POWER PLANTS.

FISCAL YEAR 1995. Annual Report.

NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS FRANCE NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATONS: LOW-NUREG/CR4202: LONG-TERM AGING AND LOSS-OF-COOLANT AC.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER CIDENT (LOCA) TESTING OF ELECTRICAL CABLES'U.S'/ French Co-TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.

pera e esearch Wm NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC MOTORS IN NUCLEAR POWER PLANTS.

GEORGIA, UNIV OF, ATHENS, GA NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR NUREG/CR-6096:

APACHE LEAP TUFF INTRAVAL AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATON FUNC.

EXPERIMENTS.Results And Lessons Leamed.

TONS.

GERMANY, FEDERAL REPUBUC OF NUREG/CR4340 AGING ASSESSMENT OF SURGE PROTECTIVE DE-NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF VICES IN NUCLEAR POWER PLANTS.

NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS LARGE-SCALE INTERNATIONAL REFERENCE EXPERIMENTS (FAL-(ATHEANA).Techrucal Basis And Methodology Description.

SIRE II).

NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF LIVES FOR RA-HALLIBURTON NUS ENVIRONMENTAL CORP.

DOLABELED ANTIBODIES AND RELATED ISSUES.

NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR4384 V01: LITERATURE REVIEW OF ENVtRONMENTAL QUALIFICATON OF SAFETY RELATED ELECTRIC CABLES. Summary (ATHEANA).Techrucal Basis And Methodology Descnption.

Of Past Work.

IDAHO NATIONAL ENGINEERING LABORATORY NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE QUALIFICATON OF SAFETY RELATED ELECTRIC CABLES.Uterature VESSEL SUPPORTS.

Anah sis And Appendices.

NUREG/CR-5229 V08. FIELD LYSIMETER INVESTIGATONS: LOW.

/

NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATION LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR ANALYSTS.

FISCAL YEAR 1995. Annual R NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH NUREG/CR-5535 V07 R1: RE PS/ MOD 3 CODE MANUAL. Summaries BURNUP CORES.

And Rewswa Of levwM Code Assessment Reports.

NUREG/CR4489:

SUMMARY

OF FAILURE ANALYSIS ACTMTIES AT NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN BROOKHAVEN NATIONAL LABORATORY.

SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.

NUREG/CR4492: BLT-MS (BREACH. LEACH, AND TRANSPORT-MUL.

NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-TIPLE SPECIES) DATA INPUT GUIDE.A Computer Model For Simulat.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER ing Release Of Contaminant From Subsurface Low-Level Waste Dis.

TEST RESULTS FOR FISCAL YEARS 1994 AND 1995, posal Facality.

NUREG/CR4314: QUALITY ASSURANCE INSPECTIONS FOR SHIP-PING AND STORAGE CONTAINERS.

CALIFORNIA, UNIV. OF, LOS ANGELES, CA NUREG/CR4341: MICROBIAL DEGRADATON OF LOW LEVEL RADIO-NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-NUR CR 65 EM ERATOR TUDE FAILURES pertments At A Humed Region J4te.Beltsville, Maryland.

NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES NUREG/CR.6396: EXAMPLES. CLARIFICATIONS, AND GUIDANCE ON NUREG-1563: BRANCH TECHNICAL POSITION ON THE USE OF EXPERT ELICITATION IN THE HIGH-LEVEL RADIOACTIVE WASTE R C EST N RE REMENTS.

NUREG/CR4407: CLASSIFICATON OF TRANSPORTATION PACKAG-NURE /

150 WORKSHOP ON ROCK MECHANICS ISSUES IN RE-POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At D NG TO I TAN F

NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN Holiday Inn Crowne Plaza. Rockvtlle. Maryland. September 19-20. 1994.

NUREG/CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT.

SAFETY-RELATED COMPONENTS.

ED ROCK MASS.

NUREG/CR4490 V01: NUCLEAR POWER PLANT GENERIC AGING LESSONS LEARNED (GALL). Main Report And Apix A.

NUREG/CR-6401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4490 V02: NUCLEAR POWER PLAru GENERIC AGING REGON.Cntical Review And Analyses of Tectonic Data From The Central Basin And Range.

LESSONS LEARNED (GALL). Appendix B.

CHALK RIVER NUCLEAR LA80RATORIES ILLINOIS, UNIV. OF, URBANA, IL NUREG/CR4429 THE ROLE OF ORGANIC COMPLEXANTS AND Mt.

NUREG/CR4317: NUMERICAL INVESTIGATON OF 3-D CONSTRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

l CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA.

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT l

DIONUCUDES.

LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

Contractor Index 81 JOHNS HOPKINS UNIV, BALTIMORE, MD NUREG/CR-5591 V06 N2; HEAVY-SECTION STEEL IRRADIATION NUREG/CR-5442: REUABluTY-BASED CONDITON ASSESSMENT OF PROGRAM.Sermannual Progress Report For April Through September STEEL CONTAINMENTS AND UNERS.

1995.

NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITION REINFORCED CONCRETE STRUCTURES.

AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN MAIN STEAM ISOLATON VALVES AND VALVE OPERATORS.

NUCLEAR POWER Pt. ANTS.

NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER WONT-DOHEm EARTH OBSERVAN TEST RESULTS FOR FISCAL YEARS 1994 AND 1995 NUREG/CR4495: CASE STUDY OF LOUEFACTON INDUCED BY THE NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF SE-1944 MASSENA, NEW YORK CORNWALL, ONTARIO EARTH-LECTED AEA/UCSB MODEL FECUMN ALLOYS.

OUAKE.

NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY-CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-LAWRENCE UVERMORE NATIONAL LABORATORY SPECTION.

NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM.

NUREG/CR4406: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL MERCIAL OFF-THE SHELF (COTS) SOFTWARE IN REACTOR APPLI-DIGITAL SAFETY CHANNEL CATIONS NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A302B NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.

NUREG/CR4487: CONTAINMENT ANALYSIS FOR TYPE B PACKAGES AND A5338 CORRELATON MONITOR MATERIALS.

USED TO TRANSPORT VARIOUS CONTENTS.

NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/CR-6491: RECOMMENDATIONS FOR PROTECTING AGAINST REINFORCED CONCRETE STRUCTURES.

FAILURE BY BRITTLE FRACTURE. Category 11 And ill Ferritic Steel NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC SNpping Containers With Wall TNckness Greater Than Four inches.

RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUCLEAR POWER PLANTS.

LOS ALAMOS NATIONAL LABORATORY NUREG/CR4436: SURVEY OF AMBIENT ELECTROMAGNETIC AND NUREG/CR4429: THE ROLE OF ORGANIC COMPLEXANTS AND Mi-RADIO FREOUENCY INTERFERENCE LEVELS IN NUCLEAR POWER CROPARTICULATES IN THE FACILITATED TRANSPORT OF RA-PLANTS.

DIONUCLIDES.

NUREG/CR-6455: DATA ANALYSIS FOR STEAM GENERATOR TUBING SAMPLES MARYLAND, UNIV. OF, COLLEGE PARK, MD NUREG/CR4460: CSNI PROJECT FOR FRACTURE ANALYSES OF NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATON INTO LARGE-SCALE INTERNATONAL REFERENCE EXPERIMENTS (FAL-NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-SIRE II) penments At A Humid Region Site.Beltsville. Maryland.

NUREG/CR4483: GUIDE TO VERIFICATON AND VALIDATON OF THE SCALE 4 CRITICALITY SAFETY SOFTWARE.

MINNESOTA, UNIV. OF, MINNEAPOUS, MN NUREG/CR4484: GUIDE TO VERIFICATION AND VALIDATON OF l

NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR RA-THE SCALE 4 RADIATION SHIELDING SOFTWARE.

DIOLABELED ANTIBODIES AND RELATED ISSUES' NUREG/CR4500: OWNERS OF NUCLEAR POWER PLANTS.

NA N

OF TANDARDS & TECHNOLOGY (FORMERLY OMN! TECH INTERNATIONAL, LTD.

NUREG/CR4494: CONTINUOUS ANALYSIS FOR VANADIUM IN LOMI l

NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

DECONTAMINATION.

ING ALTERNATIVE TEMPERATURE-TIME CURVE FOR TESTING TH I

I CE OF BARRIERS FOR NUCLEAR POWER PURDUE UNIV., WEST LAFAYETTE, IN NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY 4

MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NAVY, DEPT.OF NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL.

SBWR.

ING MODELS TO THE DUCTILE-TO BRITTLE TRANSITION.

NEW MEXICO STATE UNIV., LAS CRUCES, NM NUREG/CR4419: SOI,UBluTY TESTING OF ACTINIDES ON BREATH-1 NUREG/CR4366 POLYRES: A POLYGON-BASED RICHARDS EQUA-ING-ZONE AND AREA AIR SAMPLES.

TION SOLVER.

RISK ENGINEERING,INC.

NORTH CAROUNA STATE OF NUREG/CR4466: GROUND MOTON INPUT IN SEISMIC EVALUATION 1

NUREG 1556 V01 DR FC: CONSOUDATED GUIDANCE ABOUT MATE-STUDIES. impacts Of Artif' ial Trne History input On IrFStructure c

RIALS LICENSES.Prograrn-Specific Guidance About Portable Gauge Dernand Spectra.

Licenses Draft Report For Comment.

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-OAK RIDGE ASSOCIATED UNIVERSITIES TS NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-NUREG/CR'4468. GROUND MOTION INPUT IN SEISMIC EVALUATION MACEUTICALS.

STUDIES. impacts On Risk Assessment Of Uniform Hazard Spectra.

OAK RIDGE NATIONAL LABORATORY SCWED NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.

NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE NETWORK DETECTION CAPABluTIESAnnual Report. July 1994 July ATLAS SITE,MOAB. UTAH. Source Material License No. SUA-M95.

917, Docket No. 40-3453. (Atlas Corporation)

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-S. COMEN & ASSOCIATES, E.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL NUREG/CR-5595 RO1: FORECAST: REGULATORY trFECTS COST CORPORATION. CAMBRIDGE. OHIO. FACluTY. Docket No. 404948.Li-ANALYSIS SOFTWARE MANUAL Version 4.1.

cense No. SMB-1507.

NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

SANDIA NATIONAL LABORATORIES ING ON CRACMNG IN LWR RPV HEAD PENETRATIONS. Held At NUREG/CR4189: A SIMPUFIED MODEL OF AEROSOL REMOVAL BY ASTM Headquarters, PNiede4pNa, Pennfsania, May2 3,1995.

NUREG/CR-4219 VII N2-HEAVY-SEuION STEEL TECHNOLOGY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NUREG/CR4202: LONG-TERM AGING AND LOSSCF. COOLANT AC-PROGRAM. Semiannual Progress Report For April-September 1994.

NUREG/CR-4219 V12 N1: HEAVY SECTON STEEL TECHNOLOGY CIDENT (LOCA) TESTING OF ELECTR! CAL CABLES U.S./ French Co.

PROGRAM. Semiannual Progress Report For October 1994 - March operative Research Program.

1995.

NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG/CR 5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.

HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.

FISCAL YEAR 1995. Annual Report.

NUREG/CR4400: ENVIRONMENTAL TESTING OF AN EXPERIMENTAL NUREG/CR-5442: RELIABluTY BASED CONDITION ASSESSMENT OF DIGITAL SAFETY CHANNEL.

STEEL CONTAINMENTS AND LINERS.

NUREG/CR4476: CIRCUIT BRIDGING OF COMPONENTS BY SMOKE.

i

=

82 Contractor index SCIENCE & ENGINEERING ASSOCIATES,INC.

SOUTHWEST RESEARCH INSTITUTE NUREG/CR-5595 RO1: FORECAST: REGULATORY EFFECTS COST NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN ANALYSIS SOFTWARE MANUAL Vermon 4.1.

SAFETY TESTING.Techrucal Report On The Findings Of Task 4 inves-NUREG/CR-6367; EXPERIMENTAL STUDY OF HEAD LOSS AND FIL.

tigation of Feled Nrtinol Brachytherapy Wire.

TRATION FOR LOCA DEBRIS.

NUREG/CR.6432: ESTIMATED NET VALUE AND UNCERTAINTY FOR TECHNCAL RESEARCH CENTRE OF FINLAND (VTT)

AUTOMATING ECCS SWITCHOVER AT PWRS.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

SCIENCE APPLICATIONS, TENNESSEE, UNIV. OF, KNOXVILLE, TN NUREG4713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM, NUREG/GR4015: BULK TEMPERATURE MEASUREMENT IN THER.

MERICAL NUCLEAR POWER REACTORS AND OTHER MALLY STRIPED PIPE FLOWS.

FACILITIES,1994. Twenty-Seventh Annual Report.

NUREG/CR 4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS TEXAS, UNIV. OF AUSTIN, TX (ATHEANA). Technical Basis And Methodology Descripm NUREG/CR4462 FIELD TESTING PLAN FOR UNSATURATED ZONE NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATION MONITORING AND FIELD STUDIES' ANALYSIS-U.S. NAVAL ACADEMY, ANNAPOLIS, MD NUPEG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL-N REG CR 50 RACTE I ION OF CONTAMINATION THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESSING.

WASH NGTON, UNIV. 0F. SEATTLE. WA NUPEG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:

Lf>DATE OF THE TECHNICAL ISSUES 1996.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES WESTINGHOUSE HANFORD CO.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final HUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RAOlONU-Report.

CLIDE BURDENS TO PRENATAL RADIATION DOSES.

t

International Organization index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.

ITALY KOREA INSTITUTE OF NUCLEAR SAFETY UNIVERSITY OF PISA NUREG/lA4130: ASSESSMENT OF RELAPS/ MOD 3.1 WITH THE NUREG/lA-0135: POST TEST ANALYSIS OF PIPER-ONE PO IC-2 EX-LSTF SB-SG46 EXPERIMENT SIMULATING A STEAM GENERA-PERIMENT BY RELAP5/ MOO 3 CODES-TOR TUBE RUPTURE TRANSIENT.

REPUSUC OF KOREA RUS$lA KOREA ADVANCED INSTITUTE OF SCIENCE AND TECHNOLOGY INSTITUTE OF NUCLEAR SAFETY NUREG/lA-0134: ASSESSMENT OF RELAPS/ MOD 3.1 FOR GRAVI-NUREG/lA4129: AN ASSESSMENT OF THE CORCON-MOD 3 TY DRIVEN INJECTION EXPERIMENT IN THE CORE MAKEUP CODE.PART 1: THERMAL-HYDRAULIC CALCULATIONS.

TANK OF THE CARR PASSIVE REACTOR (CP-1300).

XOREA ATOMIC ENERGY RESEARCH INSTITUTE SWITZERLAND NUREG/lA 0131: ASSESSMENT OF RELAPS/ MOD 3 USING BETHSY PAUL SCHERRER INSTITUTE 6.2TC 6-INCH COLD LEG SIDE BREAK COMPARATIVE TEST.

NUREG/lA 0133: DEVELOPMENT, IMPLEMENTATION, AND AS-NUREG/lA4132-IMPROVEMENTS TO THE RELAPS/ MOD 3 RE-SESSMENT OF SPECIFIC CLOSURE LAWS FOR INVERTED-AN-FLOOD MODEL AND UNCERTAINTY OUANTIFICATION OF RE-NULAR FILM-BOILING IN A FLDOD PAK CLAD TEMPERATURE.

I i

83 l

t k

l e

)

Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

Ef4E 2d:D:$

m"SE

- dM * * '*"""'

52M GE Supeted 8WR M Demon, General NUREG/CR4300 S 391 Wans Bar Nudeer Plant Unit 2 Tennessee NUREG0647 S20 4 4948 Corp., Newisid, PU, NURE41543 85

NRC FORM 335 U S NUCLEAR REGULATORY COMMISSION 1.

REPORT NUMBER Q 8Eh (Assegned by NRC, Add Vol, Supp.,

NRCM 11o2, Rev, and Addondum Numbers. d any) 32oi. 32o2 ClfLIOGRAPHIC DATA SHEET (See insiructions on ine reverse)

NUREG-0304 i

Vol. 21, No. 4 a nne ANDSUisnrEe 3 DAIE HEPORT PU6USMED l

Regulatory and Technical Reports 1

l (Abstract Index Journal)

^"

Annual Compilation for 1996 April 1997 4 FIN OR GRANT NUMBER

6. MHOR(S) 6 TYPE OF HEPOHf Reference

7. PERIOD COVERED (inctumve Dates)

January - December 1996

e. PERFOHMING OFtGANIZATION - NAME AND ADDRESS (if NHC, prowde Dmmon, Omco or Region, U S Nuclear Regulatory Commesseon, and mahng address, W contractor, prowde name and rnehng address )

Publications Branch Office ofInformation Resources Managemcet U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 9.

6PONSOHING OHGANIZATION - IIAME AND ADDRESS (It NRC, type 'Same as above'. W contractor, prowde NRC Dmmon Othee or Region, U S Nuclear Fhegulatory Commemon, Ertd malmg address )

Same as 8, above.

10. SUPPLEMENTARY NOTES M. A. Sheehan, Project Manager

11. ABSTRACT (200 words or less)

This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed-

' ings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

12. KEY WORDSOESCRIPTORS (LJet words or phrases that mil assist researchers in locatmg the report.)

13 AVAILABluiY STATEMENT Unlimited 14 SECURITY CLAS$1FICATION compilation (1h= Par')

abstract index Unclassified

('the Report)

Unclassified 15 NUMBEH OF PACsES 16 PRICE NRe FORM 336 Q+89) f n

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