ML20070J786

Regulatory and Technical Reports (Abstract Index Journal). Compilation for First Quarter 1994,January-March

ML20070J786
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Issue date:	06/30/1994
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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References
NUREG-0304, NUREG-0304-V19-N01, NUREG-304, NUREG-304-V19-N1, NUDOCS 9407250316
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NUREG-0304 Vol.19, No.1 Regu:atory and Technical Reports

< Abstract Index Journal;)

(

Compilation for First Quarter 1994 January - March U.S. Nuclear Regulatory Commission Office of Administration v" "*%,,

j 94072 g g 940#0 o$$4R j

Available from Superintendent of Documents U.S. Government Printing Office Mail Stop SSOP i

Washington, DC 20402-9328 A year's subscription consists of 4 issues for this publication.

Single copies of this publication are availabic from National Technical Information Service Springfield, VA 22161 4

NUREG-0304 Vol.19, No.1 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for First Quarter 1994 January - March Date l'ublished: June 1994 Regulatory Publications Branch Division of Freedom ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 y... 9, e

2 E

=

CONTENTS f'reface,.

y Index Tab Main Citations and Abstracts.

.. 1 l

• Staff Reports

• Conference Proceedings

• Contractor Reports

• International Agreement Reports Secondary Report Number Index...

.. 2 Personal Author index.

3 Subject index 4

NRC Originating Organization index (Staff Reports).

....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 iii l.

i 1

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 ap-preciated. Please send them to:

Technical Publications Section Regulatory Publications Branch Division of Freedom of Information and Publications Services P-223 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/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 iridex.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0808: MARK ll CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.

ANDERSON, 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 accession number, (8) the microfiche address (for internal NRC use).

C jerence Report f

NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND l

RELIABILITY 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 l

the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Docu.

ment Control System accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC internal use),

t-Contractor Report 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.

Sandia Laboratories. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.

j

%'here the entries are (1) report number, (2) report title, (3) report authors, (4) organizational unit of i

authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if Oven), and (9) the microfiche address (for NRC internal use).

i 1

V

International Agreement Report NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftwerk 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 accession 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 documents 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)275-2060 or (202)275-2171. Non-U.S. customers must make payment in advance either 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.

NRC Report Codes 1

The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identification replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-i NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship of j

the work being reported, in addition to the NUREG and NUFFG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is used for international agreement reports.

All these report codes are controlled and assigned by the staff of the Publishing and Translations Section j

of the NRC Division of Publications Services.

)

l l

i vi j

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 reaort. The bibliographic information (see Preface for details) is followed by a brief abstract of t1is report, NUREG-0020 V18: LICENSED OPERATING REACTORS STATUS NUREG-0540 V15 N12: TITLE LIST OF DOCUMENTS MADE

SUMMARY

REPORT. Data As Of December 31, 1993.(Gray PUBLICLY AVAILABLE. December 1-31, 1993.

• Division of Book l) HARTFIELD.R.A. Office of information Resources Man-Freedom of information & Publications Services (Post 890205).

agement (Post 890205). March 1994. 350pp. 9404110367.

February 1994. 371pp. 9404010178. 78719:033.

78819:014.

See NUREG-0540,V15,N11 abstract.

The Nuclear Regulatory Commission's enrr;al summary of 4 NUREG-0540 V16 Not: TITLE LIST OF DOCUMENTS MADE censed nuclear power reactor data is based primarily on the PUBLICLY AVAILABLE. January 1 31,'1994.

• Division of Free-report of operating data submitted by licensees for each unit for dom of Information & Publications Services (Post 890205).

the month of December because that report contains data for March 1994. 288pp. 9404010174. 78718:109.

the month of December, the year to date (in this case calendar See NUREG.0540,V15,N11 abstract.

year 1993) and cumulative data, usually from the date of com-mercial operation. The data is not independently verified, but NUREG-0750 V38101: INDEXES TO NUCLEAR REGULATORY various computer checks are made. The report is divided into COMMISSION ISSUANCES. July-September 1993.

• Division of two sections. The first contains summary highlights and the Freedom of Information & Publications Services (Post 890205).

January 1994. 41pp. 9403140325, 78454:291, second contains data on each individual unit in commercial op-oration. Section 1 capacity and availability factors are simple es s and hs for bsuaxes of N Comdssion, h Atomic Safety and Licensing Board Panel, the Administrative arithmetic averages. Section 2 items in the cumulative column Law Judges, the Directors' Decisions, and the Denials of Peti-are generally as reported by the licensee and notes as to the tions for Rulemaking are presented.

use of weighted averages and starting dates other than com-mercial operation are provided.

NUREG-0750 V38 NOS: NUCLEAR REGULATORY COMMISSION ISSUANCES FOR NOVEMBER 1993. Pages 187-288.

• Division NUREG-0040 V17 N04: LICENSEE CONTRACTOR AND of Freedom of information & Publications Services (Post VENDOR INSPECTION STATUS REPORT. Quarterly 890205). February 1994.109pp. 9405240153. 79484:001.

Report, October-December 1993.(White Book)

• Division of Re-Legal issuances of the Commission, the Atomic Safety & Li-actor inspection & Licensee Performance (Post 921004). Febru.

censing Board Panel, the Administrative Law Judges, and NRC ary 1994. 68pp. 9403150242. 78501:288.

Program Offices are presented.

This periodical covers the results of inspections performed by NUREG-0750 V38 N06: NUCLEAR REGULATORY COMMISSION the NRC's Vendor inspection Branch that have been distributed ISSUANCES FOR DECEMBER 1993. Pages 299-391.

• Division to the inspected organizations during the period from October of Freedom of information & Publications Services (Post through December 1993.

890205). February 1994,109pp. 9403140316. 78477:148.

See NUREG-0750,V38,N05 abstract.

NUREG-0430 V13: LICENSED FUEL FACILITY STATUS REPORT. Inventory Difference Data.Jufy 1,1992 - June 30, NUREG-0837 V13 N04: NRC TLD DIRECT RADIATION MONI-1993.(Gray Book ll) JOY,D.R. Office of Nuclear Material Safety TORING NETWORK. Progress Report. October-Dember 1993.

& Safeguards. February 1994,10pp. 9403150260. 78501:269.

STRUCKMEYER,R. Region 1 (Post 820201). March 1994 NRC h committed to the periodic publication of licensed fuel 328pp. 9404060261. 78758:001, facility inventory difference data, following agency review of the This report provides the status and results of the NRC Ther-information and completion of any related NRC investigations.

moluminescent Doaimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity information in this report includes inventory difference data for of NRC licensed facilitNs thr;ughout the country for the fourth active fuel fabrication facilities possessing more than one effec-quarter of 1993.

tive kilogram of special nuclear material.

NUREG-0936 V12 N04: NRC REGULATORY AGENDA.Ouarterly NUREG-0540 V15 N11: TITLE LIST OF DOCUMENTS MADE Report. October-December 1993.

• Division of Freedom of infor.

PUBLICLY AVAILABLE. November 1 30. 1993.

• Division of mation & Publications Services (Post 890205). February 1994.

Freedom of information & Publications Services (Post 890205).

130pp. 9403150227. 78501:135.

January 1994. 251 pp. 9402150231, 78121:163.

The NRC Regulatory Agenda is a compilation of all rules on This document is a monthly publication containing descrip-which the NRC has recently completed action, or has proposed tions of information received and generated by the U.S. Nuclear action, or is considering action, and all petitions for rulemaking Regulatory Commission (NRC). This information includes (1) which have been received by the Commission and are pending docketed material associated with civilian nuclear power plants disposition by the Commission. The Regulatory Agenda is up-and other uses of radioactive materials, and (2) nondocketed dated and issued each quarter.

material received and generated by NRC pertinent to its role as NUREG-0940 V12 NO3: ENFORCEMENT ACTIONS: SIGNIFi-a regulatory agency. The following indexes are included: Per-CANT ACTIONS RESOLVED.Oua,terty Progress Report July-sonal Author, Corporate Source, Report Number, and Cross September 1993.

• Ofc of Enforcement (Post 870413). Decem-Reference of Enclosures to Principal Documents.

ber 1993. 601pp. 9402220162. 78193:062.

1

2 Main Citations and Abstracts This compilation summartzes significant enforcement actions TNs preapplication safety evaluation report (PSER) presents that have been resolved during one quarterty period (July - Sep-the results of the preapplication design review for the Power tomber 1993) and includes copies of letters, Notices, and Reactor Innovative Small Module (PRISM) liquid-metal (sodium).

Orders sent by the Nuclear Regulatory Commission to licensees cooled reactor, Nuclear Regulatory Commission (NRC) Project with respect to these enforcement actions. It is anticipated that No. 674. The PRISM conceptual design was submitted by the the information in this publication will be widely disseminated to U.S. Department of Energy in accordance with the NRC's managers and employees engaged in actrvtties licensed by the

.. Statement of Policy for the Regulation of Advanced Nuclear NRC, so that actions can be taken to improve safety by avoid-Power Plants" (51 Federal Register 24643). TNs policy provides ing future violations similar to. hose described in this publica-for the early Commission review and interaction with designers D'

and hcensees. The PRISM reactor design is a small, modular, I

NUREG-0940 V12 N04: ENFORCEMENT ACTIONS: SIGNIFl.

pool-type, liquid-metal (sodium)-cooled reactor. The standard P ant design consists of three identical power blocks with a total l

CANT ACTIONS RESOLVED.Ouarterty Progress Report, October-December 1993.

• Ofc of Enforcement (Post electrical output rating of 1395 MWe. Each power block com-870413). March 1994. 387pp. 9404010220. 78721:266.

prises three reactor modules, each with a thermal rating of 471 TNs compilation summartzes significant enforcement actions MWt. Each module is located in its own below-grade silo and is that have been resolved dunng one quarterty penod (October -

connected to its own intermediate heat transport system and December 1993) and includes copies of letters, Notices, and steam generator system. The reactors utilize a metallic-type Orders sent by the Nuclear Regulatory Commission to licensees fue;, a tomary alloy of U-Pu-Zr. The design includes passive re-with respect to these enforcement actions, it is anticipated that actor shutdown and passive decay heat removal features. The the informatiort in tNs publication will be widely disseminated to PSER is the NRC's preliminary evaluation of the safety features managers and employees engaged in activities licer. sed by the in the PRISM design, including the projected research and de-NRC, so that actions can be taken to improve safety by avoid-velopment programs required to support the design and the pro-ing future violations similar to those described in this pub!ica*

posed testing needs. Because the NRC review was based on a tm conceptual design, the PSER did not result in an approval of NUREG 1022 Rot DR FC: EVENT REPORTING GUIDELINES the design. Instead it identified certain key safety issues, provid-10CFR50.72 AND 50.73.Second Draft For Comment.

ed some guidance on applicable licensing criteria, assessed the ALLISON.D.P.; HARPER.M.R.; ISRAEL,S.; et al. Office for Anal.

adequacy of the preapplicant's research and development pro-ysis & Evaluation of Operational Data, Director. February 1994.

grams, and concluded that no obvious impediments to licensing 182pp. 9402220125. 78192:041, the PRISM design had been identified.

Revision 1 to NUREG-1022 clartfies the immediate notifica-tion requirements of Title 10 of the Code of Federal Regula.

NUREG-1435 S03: STATUS OF SAFETY ISSUES AT LICENSED tions, Part 50, Section 50.72 (10 CFR 50.72), and the 304ay POWER PLANTS.TMI Action Plan Requirements. Unresolved wntten licensee event report (LER) requireme,ts of 10 CFR Safety issues. Generic Safety lasues.Other Multiplant Action 50.73 for nuclear power plants. This revision was initiated to im.

Issues.

• Program Management, Policy Development & Analysis prove the reporting guidelines related to 10 CFR 50.72 and Staff (Post 870411). December 1993. 165pp. 9402220173.

50.73 and to consolidate these guidelines into a single refer-78197:187.

ence document. A first draft of this document was noticed for As part of ongoing U.S. Nuclear Regulatory Commission public comment in the Federal Register on October 7,1991 (56 (NRC) efforts to ensure the quality and accountability of safety FR 50598). This document updates and supersedes NUREG-issue information, a program was established whereby an 1022 and its Supplements 1 and 2 (published in September annual NUREG report would be published on the status of li-1983, February 1984, and September 1985, respectively). It censee implementation and NRC verification of safety issues in does not change the reporting requirements of 10 CFR 50.72 major NRC requirement areas. This information was compiled j

and 50.73.

and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI)

NUREG 1100 V10: BUDGET ESTIMATES. Fiscal Year 1995.

• Di-Action Plan Requirements. Volume 2, published in May 1991, vision of Budget & Analysis (Post 890205). February 1994.

addressed me stabs of msoNed saMy issues ps).

217pp. 9402220139. 78191:075.

Volume 3, published in June 1991, addressed the implementa-This report contains the fiscal year budget justification to Con-tion and verification status of generic safety issues (GSis). Sup-Dress. The budget provides estimates for salaries and expenses Pement 1, published in December 1991 combined these vol-i and for tSe Office of the inspector General for fiscal year 1995.

umes into a single report and provided updated information as NUREG-12 4 R13: HISTORICAL DATA

SUMMARY

OF THE SYS-of September 30,1991. Supplement 2, published in December l

TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.

1992, provided updated information on TMI, USI, and GSI ALLENSPACH,F. Division of Reactor inspection & Licensee issues and included status of all other Muttiplant Actions l

l Performance (Post 921004). March 1994. 94pp. 9404110359.

(MPAs). This annual NUREG report provides updated informa-i 78851:200.

tion on TMI, USI, and GSI and other MPAs as of September 30, i

The Historical Data Summary of the Systematic Assessment 1993. ine data contained in these NUREG reports are a prod-of Licensee Performance (SALP) is produced periodically by the uct of the NRC's Safety issues Management System (SIMS) da-U.S. Nuclear Regulatory Commission. This summary provides tabase, which is maintained by the Project Management Staff in the resutts of the assessment for each facility by NRC region the Office of Nuclear Reactor Regulation and by NRC regional and is further drvided into the foHowing sect >ons: Section 1 pre-personnel. This report is to provide a comprehensive description sents the most recent SALP report ratings for facilities in oper-of the implementation and verification status of TMI Action Plan ation. Section 2 presents a chronological hsting of all SALP Requirements, USts, GSis, and other MPAs that have been re-report ratings for each operating facility since February 1,1989.

solved and involve implementation of an action or actions t e li-NUREG-1368: PREAPPLICATION SAFETY EVALUATION consees. This report makes the information available to curer REPORT FOR THE POWER REACTOR INNOVATIVE SMALL interested parties, including the public. An additional purpose of MODULE (PRISM) LIQUID-METAL REACTOR. Final Report.

this report is to serve as a follow-on to NUREG-0933, "A Priori-DONOGHUE.J.E.; DONOHEW,J N.; GOLUB.G.R.; et al. Associ-tization of Gensric Sefety lasues," which tracks safety issues up ate Director for Advanced Reactors & Licer.se Renewal (Post until requirements are afg) roved for imposition at licerced plants 910918). February 1994. 400pp. 9404010163. 78716:001.

or until the NRC issues a request for action by Ecensaes.

l l

l w___ _ __-___ - _ _ __ _ _ - __ - _

Main Citations and Abstracts 3

NURE041471: CONCEPT OF OPERATIONS WITH ORGANIZA-NUREG-1499: REASSESSMENT OF THE NRC'S PROGRAM TION CHARTS.NRC incident Response.

HIMES,J.;

FOR PROTECTING ALLEGERS AGAINST RETALIATION.

• JACKSON.K.; LOPRESTI,F. Division of Operational Assessment Ofc of the Executive Director for Operations. January 1994.

(Post 870413). Wuary 1994. 69pp. 9403140209. 78456:175.

200pp. 9402150379. 78123:349.

The U.S. Nuclear Regulatory Commission (NRC) regulates nu-On July 6, 1993, the Nuclear Regulatory Commission's clear power plants and certain other civilian nuclear facilities (NRC's) Executive Director for Operations established a review and materials to protect the public hea% and safety and to pre-team to reassess the NRC's program for protecting allegers serve environmental quality. While the foremost objective of against retaliation. The team evaluated the current system, and regulation is to prevent accidents, the NRC is also prepared to solicited comments from vanous NRC offices, other Federal help its licensees and State and local governments mitigate the agencies, former allegers, and the public. This report is subject consequences of any that might occur. This document de-to agency review. The report summarizes current processes and scribes the NRC concept, purposes, and organization for per-gives an overview of current problems. It discusses: (1) ways in forming essential functions during a Federal response to a which licensees can promote a quality-conscious work environ-severe reactor accident, with an emphasis on State and Federal ment, in which all employees feel free to raise concems without coordination, fear of retaliation; (2) ways to improve the NRC's overall han-dling of allegations; (3) the NRC's involvement in the Depart-NUREG-14CS: FINAL SAFETY EVALUATION REPORT TO Ll-ment of Labor process; (4) related NRC enforcement practices; CENSE THE CONSTRUCTION AND OPERATION OF A FACILl*

and (5) methods other than investigation and enforcement that TY TO RECEIVE, STORE AND DISPOSE OF 11E(2) BYPROD-may be useful in treating allegations of potential or actual dis-

~

UCT MATERIAL NEAR CLIVE, UTAH. Docket No. 40-8989.(En-crimination. Recomrnendations are given in each area.

virocare of Utah,Inc.) ABU-EID R ; BRUMMETT,E.; BYKOSKI L; et al. Division of Low-Level Waste Management 8. Decommis-NUREG/CP-0127: PROCEEDINGS OF THE CSNI SPECIALISTS sioning (870413-940402). January 1994.116pp. 9402220120.

MEETING ON FUEL-COOLANT INTERACTIONS.

• Organiza-78191:291.

tion for Economic Cooperation & Development. March 1994.

The Final Safety Evaluation Report (FSER) summarizes the 377pp.9404110363. NEA/CSNI/R(93)8. 78818:001.

U.S. Nuclear Regulatory Commission (NRC) staff's review of A specialists meeting on fuel-coolant interactions was held in Envirocare of Utah, Inc.'s (Envirocare's) application for a license Santa Barbara, CA from January 5-7, 1993. The meeting was to receive, store, and dispose of uranium and thorium byproduct sponsored by the United States Nuclear Regulatory Commission material (as defined in Section 11e.(2) of the Atomic Energy Act in collaboration with the Committee on the Safety of Nuclear in-of 1954, as amended) at a site near Clive, Utah. Envirocare pro-stallation (CSNI) of the OECD Nuclear Energy Agency (NEA) poses to dispose of high-volume, low-activity Section 11e.(2) by-and the Universrty of Califomia at Santa Barbara. The objectives i

product matenal in separate earthen disposal cells on a site of the neeting are to cross-fertilize on-going work, provide op-where the applicant currently disposes of naturally occurring ra-portuntties for mutual check points, seek to focus the technical dioactive material (NORM), low-level waste, and mixed waste issues on matters of practical significance and re-evaluate both under license by the Utah Department of Environmental Quality.

the objectives as well as path of future research.

The NRC staff review of the December 23,1991, license applica-tion, as revised by page changes dated July 2 and August NUREG/CR-3145 V10: GEOPHYSICAL INVESTIGATIONS OF 10,1992, April 5, 7, and 10,1993, and May 3, 6, 7,11, and 21, THE WESTERN OHIO-INDIANA REGION. Final Report, October 1993, has identified open issues in geotechnical engineering, 1986-September 1992. RUFF,L.; LAFORGE.R.; THORSON,R.;

water resources protection, radon atte,nuation, financial assur.

et al. Michigan, Univ. of, Ann Arbor, MI. February 1994.115pp.

ance, and radiological safety. The NRC will not issue a license 9403140217. 78456:242.

for the proposed action until Envirocare adequately resolves Earthquake activity in the Western Ohio-Indiana region has these open issues.

been monitored with a seismograph network consisting of nine stations located in west-central Ohio and four stations loc &ted NUREG-1491: SAFETY EVALUATION REPORT FOR THE CLAl-in Indiana. Six local and regional earthquakes have been re-BORNE ENRICHMENT CENTER. HOMER, LOUISIANA. Docket corded from October 1990 to September 1992 with magnitudes No. 70-3070, Louisiana Energy Services,LP,

• Division of Fuel ranging from 0.6 to 5.0. A total of 36 local and regional earth-Cycle Safety & Safeguards (Post 930207). January 1994.

quakes have been recorded in the past 6-year penod (October 300pp. 9402150293. 78120:017.

1986 to September 1992). Overall a total of 78 local and region-This report documents the U.S. Nuclear Regulatory Commis-al earthquakes have been recorded since the network went into sion (NRC) staff safety review and evaluation of the Louisiana operation in 1977. There was a peak in seismicity in 1986, in-Energy Services, LP. (LES, the applicant) application for a li-ciuding the July 12,1986 St. Marys' event (mb=4.5), followed cense to possess and use byproducts, source, and special nu-by an anomalously low level of seismicity for about 2 years. The clear material and to enrich natural uranium to a maximum of most unusual feature of the seismicity in the past year is the five percent U-235 by the gas centrifuge process. The plant, to occurrence of three earthquakes in Indiana. The locations of the be known as the Claiborne Enrichment Center (CEC), would be felt earthquakes are scattered across central Indiana; an area constructed near the town of Homer in Claiborne Parish, Louisi-that had been aseismic. Analysis of arrival time data accumulat-ana. At full production in a given year, the plant will receive ap-ed over the past 14 years shows that the Anna region crustal proximately 4,700 tonnes of feed UF(6), and produce 870 structure is " slower" than the average mid-continent crustal tonnes of low-enriched UF(6), and 3,830 tonnes of depleted structure. This implies that the proposed Keewenawan nft in the UF(6) tails. Facility construction, operation, and decommission-Anna region has a different structure than that of other ing are expected to last five, thirty, and seven years, respective-Keewenawan rifts in the mid-continent, fy. The objective of the review is to evaluate the potential ad-verse impacts of operation of the facility on worker and pub'ic NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCI-health and safety under both normal operating and accident DENT RISKS:

METHODOLOGY FOR THE conditions. The review also considers the management organi-CONTAINMENT, SOURCE TERM. CONSEQUENCE, AND RISK zabon, administrative programs, and hnancial qualifications pro-INTEGRATION ANALYSES. GORHAM,E.D.; BREEDING.R.J.

vided to assure safe design and operation of the facihty. The Sandia National Laboratories. HELTON,J.C.; et al. Arizona State NRC staff concludes that the applicant's desenptions, specifica-Univ., Tempe, AZ. December 1993. 279pp. 9402220215.

tions, and analyses provide an adequate basis for safety review SAND 86-1309. 78198.001.

of facility operations and that construction and operation of the NUREG-1150 examines the risk to the public from five nucle-facmty does not mse an undue risk to pubhc health and safety ar power plants. The NUREG-1150 plant studies are Level 111

\\

4 Main Citations and Abstracts probabilistic nsk assessrnents (PRAs) and, as such, they consist NUREG/CR-4674 V18: PRECURSORS TO POTENTIAL SEVERE of four analysis components: accident frequency analysis, acci.

CORE DAMAGE ACCIDENTS:

1992 A

STATUS dent progress, analysis, and source term anetysis, and conse.

REPORT. Appendices B, C, D, E F, And G. COX,D.F.;

quence analys This volume summarizes the rrethods utilized CLETCHER,J.W.; COPINGER,D.A.; et at Oak Ridge National en performing the last three components and the assembly of Laboratory. December 1993. 688pp. 9402220241. ORNL/

these analyses into an overall risk assessment. The NUREG.

NOAC-232. 78194:299.

1150 analysis approach is based on the following ideas- (1)

See NUREG/CR-4674,V17 abstract.

general and relatively fast-running models for the individual NUREG/CR-4816 R02: PR.EDB: POWER REACTOR EMBRIT-analysis components (3) use of Monte Carlo techniques togeth.

TLEMENT DATA BASE, VERSION 2. Program Description.

er with an efficient sampling procedure to propagate uncertain-STALLMANN,F.W.; WANG,J.A.: KAM,F.B.: et al. Oak Ridge Na-ties, (4) use of expert panels to develop distnbutons for impor-tional Laboratory. January 1994.122pp. 9402f 50283. ORNL/

tant pnenomenological issues, and (5) automation of the overall TM-10328. 78121:034.

analysis. Many features of the new analysis procedures were investigations of regulatory issues such as vessel integrity adopted to facihtate a cornprehensive treatment of uncertainty over plant life, vessel failure, and sufficiency of current codes, in the complete risk analysis. Uncertainties in the accident fre-Standard Review Plans (SRPs) and Guides for license renewal quency, accident progrossion and source term analyses were can be greatly expedited by the use of a well-designed comput-included in the overall uncertainty assessment. The uncertain-erized data base. Also, such a data base is essential for the val-t>es in the consequence analysis were not included in this as-dation of embnttlement prediction models by researchers. The sessment. A large effort was devoted to the development of a

e a

e 8Ma procedures for obtaining expert opinion and the execution of the comprehensive collection of data for U.S. comrnercial nuclear development of procedures for obtaining expert opinion and the reactors. The current version of the PR-EDB contains the execution of these procedures to quantify parameters and phe-Charpy test data that were irradiated in 252 capsules of 96 re.

nomena for which there k large uncertainty and divergent opi*

actors knd consists of 207 data points for heat-affected-zone ions in the reactor safety community.

(HAZ) materials (98 different HAZ), 227 data points for weld NUREG/CR 4599 V03 N2: SHORT CRACKS IN PIPING AND als (136 different base materials), including 297 plate data PIPING WELDS. Semiannual Report, October 1992 - March points (85 different plates),119 forging data points (31) different 1993. WILKOWSKI,G.M.; BRUST,F.; FRANCINI,R.; et al. Bat-forging), and 108 correlation monitor materials data points (3 telle Memorial Institute, Columbus Laboratories. March 1994.

different plates). The data files are given in dBASE format and 112pp. 9404040024. BMi-2173. 78736:256-can be accessed with any personal computer using the DOS This is the sixth semiannual report of the U.S. Nuclear Regu-operating system. " User friendly" utility programs are used to latory Commission's 4-year research program "Short Cre.cks in retrieve and select specific data, manipulate data, display data Piping and Piping Welds" which bogan in March 1990. The ob-to the screen or printer, and to fit and plot Charpy impact data.

jective is to venfy and improve fracture analyses for circumfer-The results of several studies investigated are presented in Ap-entially cracked nuclear piping with cracks sizes typically found pendix D.

dunng in-service flaw evaluations. Progress in the through-wall-cracked pire efforts involved (1) venfication of deformation NUREG/CR-4833: LARGE AREA SELF-POWERED GAMMA RAY plasticity under nonproportional loading, (2) evaluation of the DETECTOR. Phase il Development Of A Source Position Moni-effect of weld metal strength on variors J-estimation schemes, tor For Use On Industrial Radiographic Units. LEVERT,F.E.

and (3) development of new GE/EPRI functions. Surface.

K.E.M.P. Corp. January 1994. 47pp. 9402150301. 78122:053.

cracked pipe evaluations involved (1) material characterization The purpose of this research was to develop a large area of B&W C-Mn-Mc submerged arc weld metal, and (2) 3D finite.

self-Powered gamma detector (LASPGD) capable of detecting element mesh refinement study. The toughness of the bimetallic the movement of sealed radiation sources into and out of indus-weld fusion line was evaluated and showed unusual fracture be.

trial radiographic units and to construct a prototype source posi-tion monitor (SPM) for these units utilizing the LASPGD. Proto-havior based on the results of the Charpy tests. The dynamic strain aging J-R tests confirmed the screening criterion devel, type isotropic and directional LASPGDs, with solid and inert gas dielectrics, were developed and extensively tested using cali-oped earlier in the program. The results from this program to brated gamma sources (i.e., Cs-137 and Co-60). The sensitivi-date necessitated.everal additional efforts. These were initial-ties of the isotropic detectors, with inert gas dielectrics, were ed and have been reported here. Presentation of the results f und to be approximately a factor of ten greater than those from this program to tu f"M Section XI Pipe Flaw Evaluation Working Group is also m W 'ed here' tive self-powered detectors were found to exhibit a forward-to-back hemispherical sensitivity ratio of approximately 2 to 1, in-NUREG/CR-4674 V17:,

5h SORS TO POTENTIAL SEVERE dustrial radiographic units containing Ir 192 sources with differ-CORE DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Main ent activities wers used to test the performance on the SPM.

Report And Appendix A.

COX,0.F.;

CLETCHER.J.W.;

The SPM, which utilized a gas dielectric LASPGD, performed as COPINGER.D.A.; et al. Oak Ridge National Laboratory. Decem-designed. That is, the current generated in the LASPGD was bor 1993.150pp. 9402220223. ORNL/NOAC-232. 78198:280.

converted to a voltage, amplified and used to control the on/off Twenty-seven operational events with conditional probabilities state of an incandescent lamp. The incandescent lamp, which of subsequent severe core damage of 1.0 x 10E-06 or higher functions as the sourcs/out warning indicator, flashes at a rate occurring at commercial light-water reactors during 1992 are of one flash per second when the source is in use (Le. out of its considered to be precursors to potential core damage. These shield).

are desenbed along with associated significance estimates, cat-egortzation, and subsequent analyses. The report discusses (1)

NUREG/CR-5161 V02: EVALUATION OF SAMPLING Pl.ANS the general rationale for this study, (2) the se!ection and docu-FOR INSERVICE INSPECTION OF STEAM GENERATOR mentation of events as precursors,(3) the estimation and use of TUBES. Comprehensive Analytical And Monte Carlo Simulation l

Results For Several Sampling Plans.

KURTZ,R.J.;

)

conditional probabilities of subsequent severe core damage to rank precursor events, and (4) the plant models used in the HEASLER,P.G.; BAIRD,D.B. Battute Memonal Institute, Pacific Northwest Laboratory. February 1994. 72pp. 9404040034. PNL-analysis process.

6462.78736:057.

Main Citations and Abstracts 5

This report summarizes the results of three previous studies duction in shear wall st:ffness was included. In addition, an eval-to evaluate and compare the effectiveness of sampling plans uation of deterministic " design-like" structural dyrmic ca;cula-for steam generator tube inspections. An analytical evaluation tions with and without the shear stiffness t. Juctions was made.

and Monte Carlo simulaton techniques were the methods used Deterministic loads calculated for these two cases typically in-to evaluate sampling plan performance N test the parform-creased on the order of 10 to 20 percent for the affected struc-ance of candidate sampling plans under L n iety of coldteons.

tures.

ranges of inspection system reliability were considued along with different distributions of tube degradabon. Resu'ts from the NUREG/CR-5569 R01: HEALTH PHYSICS POSITIONS DATA eddy current reliability studies performed with the retired-from-BASE. KERR,G.D.; BORGES.T.; STAFFORD,R.S.; et al. Oak serv 6ce Surry 2A steam generator were utilized to guide the se-Ridge National Laboratory. February 1994.300pp.9403140176.

lection of appropriate probability of detection ard flaw sizing ORNL/TM 12067. 78453:001.

models for use in the analysis. Different distritutions of tube The Health Physics Positions (HPPOS) Data Base of the Nu-degradation were selected to span the range of condrbons that clear Regulatory Commission (NRC) is a collection of NRC staff might erAst in operating steam generators. The principal means positions on a wide range of topics involving radiation protection of evaluating sampling performance was to determine the effec-(health physics). It consists of 328 documents in the form of let-tiveness of the sampling plan for detecting and plugging defec-tive tubes. A summary of key results from the eddy current reh-tors, memoranda, and excerpts from techn. cal reports. The ability studies is presented. The analytical and Monte Carlo sim-HPPOS Data Base was developed by the NRC Head 9uarters ulabon analyses are discussed along with a synopsis of key re, and Regional Offices to help ensure ur9ormity in inspections, sults and conclusions.

enforcement, and licensing actions. Staff members of the Oak Ridge National Laboratory (ORNL) have assisted the NRC staff NUREG/CR-5314 V05: INSIGHTS FOR AGING MANAGEMENT in summanzing the documents during the preparation of this OF MAJOR LWR COMPONENTS METAL CONTAINMENTS-NUREG report. These summaries are also being made available SHAH,V.N.; SINHA,U.P. Idaho National Engineering Laborato'Y-as a " stand alone" software package for IBM and IBM-compati-SMITH,S.K. Ogden Environmental & Energy Services (Formerfy ble personal computers. The software package for this report is Multiple Dynamics Corp). March 1994, 104pp. 9404060267, called HPPOS Version 2.0. A variety of indexing schemes were e

aM Rs This port to's the available technical information and ass ciated software. The software package and the summaries field experience related to management of aging damage to m

am wnun in h coNM d,Ww m W Pad 20 light water reactor metal containments. A generic aging man-2

-2 The purpose of this NUREG report is to Egement approach is suggested for the effective and compre.

allow interested individuals to familiarize themselves with the hensive aging management of metal containments to ensure their safe operation. The major concem is corrosion of the em-contents of the HPPOS Data Base and with it's basis of many bedded porbon of the containment vessel and detection of this NRC decisions and regulations. The HPPOS summaries and damage. The electromagnetic acoustic transducer and half-cell original documents are intended to serve as a source of infor-potential measurement are potential techniques to detect corro-maton for radiaton protection programs at nuclear research soon damage in the embedded portion of the containment and power reactors, nuclear medicine, and other industries that vessel. Other corrosion-related concems include inspection of either process or use nuclear materials.

corrosion damage on the inaccessible side of BWR Mark I and il containment vessels and corrosion of the BWR Mark i torus NUREG/CR-5912: MANAGING AGING IN NUCLEAR POWER and emergency core cooling system piping that penetrates the PLANTS Insights From NRC Maintenance Team inspection Re-torus, and transgranular stress corrosion cracking of the pene.

ports. FRESCO A.; SUBUDHI,M.; GUNTHER,W.; et al. Brookha-tration bellows. Fatigue-related concems include reduction in von Nabonal Laboratory. December 1993. 204pp. 9402220158.

ths fabgue life (a) of a vessel caused by roughness of the cor.

BNL-NUREG-52309. 78196:259.

roded vessel surface and (b) of bellows because of any physical A plant's maintenance program is the principal vehicle damage. Maintenance of surface coatings and sealant at the through which age-related degradation is managed. From 1988 metal-concrete interface is the best protection against corrosion to 1991, the NRC evaluated the maintenance program of every l

of the vessel.

nuclear power plant in the United States Forty four out of a NUREG/CR-5407: ASSESSMENT OF THE IMPACT OF DE-total of 67 of the reports issued on these in-depth team inspec-GRADED SHEAR WALL STIFFNESSES ON SEISMIC PLANT tions were reviewed for insights into the strengths and weak-t RISK AND SEISMIC DESIGN LOADS. KLAMERUS,E.W.;

nesses of the programs as related to the need to understand l

BOHN,M.P. Sandia National Laboratories. JOHNSTON,J.J.; et and manage the effects of aging on nuclear plant systems, al. EOE Engineering Consultants (formerly EOE Engineering, structures, and components. Relevant information was extract-1 inc.). February 1994. 588pp. 9404010183. SAND 93-0234.

ed from these inspection reports and sorted into several cate-i 78720:042.

gones, including Specific Aging insights, Preventive Mainte-Test results sponsored by the USNRC have shown that rein-nance, Predictive Maintenance and Condition Monttoring, Post forced shear wall (Seicmic Category I) structures exhibit stifi.

Me atenance Testing. Failure Trending, Root Cause Analysis I

nesses and natural frequencies which are smaller than those an; Usage of Probabilistic Risk Assessment in the Maintenance l

calculated in the design process. The USNRC has sponsored Process. Specific examples of inspection and monitoring tech-l Sandia National Labs to perform an evaluation of the effects of naques successfully used by utilities to detect degradation due i

the reduced frequencies on several existing seismic PRAs in to aging have been identified. The information also was sorted l

order to determine the seismic risk implicabons inherent in according to systems and components, including: Auxiliary

[

these test results. This report presents the results for the re-Feedwater, Main Feedwater, High Pressure injection for both evaluation of the seismic risk for three nuclear power plants: the BWRs and PWRS, Service Water, Instrument Air, and Emergen-l Peach Bottom Atomic Power Stator'., the Zion Nuclear Power cy Diesel Generator Air Start Systems, and emergency diesel Ptunt, and Arkansas Nuclear One - Unit 1 (ANO-1) increases in generators, electrical components such as switchgear, breakers, core damage frequencies for seismic initiated events at Peach relays, ed motor control centers, motor operated valves and Bottom were 25 to 30 percent (depending on whether LLNL or check valves. This information was compared to insights gained EPRI hazard curves were used). At the ANO 1 site, the corre-from the Nucicar Plant Aging Research (NPAR) Program. At-sponding increases in plant risk were 10 percent (for each set tributes of plant maintenance programs where the NRC inspec-of hazard curves). Finally, at Zion, there was essentially no tors felt that improvement was needed to property address the change in the computed core damage frequency when the re-aging issue also are discussed

6 Main Citations and Abstracts 1

HUREG/CR-5935:

SUMMARY

OF WORK COMPLETED UNDER from the AE monitoring over the period May 1989 to March THE ENVIRONMENTAL AND DYNAMIC EQUIPMENT QUALIFl-1992 (both fuel cycles).

CATION RESEARCH PROGRAM (EDOP). STEELE.R.;

BRAMWELL.D.L.; WATKINS.J C.; et al. EG&G Idaho, Inc. Feb-NUREG/CR-5985: EVALUATION OF COMPUTER-BASED UL-ruary 1994. 79pp. 9403140229. EGG-2686. 78477:071.

TRASONIC INSERVICE INSPECTION SYSTEMS. HARRIS.R.V.;

This report documents the results of the main projects under-ANGEL,L.J.; DOCTOR,S.R.; et al. Battelle Memorial Institute, j

taken under the Environmental and Dynamic Equipment Qualifi-Pacific Northwest Laboratory. March 1994.126pp.9404040063.

I cation Research Program (EDOP) sponsored by the U.S. Nucle-PNL-8519. 78737:001, er Regulatory Commission (NRC) under FIN A6322. Lasting This report presents the principles, practices, terminology, from fiscal year 1933 to 1987, the program dealt with environ-and technology of computer-based ultrasonic testing for inserv.

mental and dynamic (including seismic) equipment quahfication ice inspection (UT/ISI) of nuclear power plants, with extensive issues for mechanical and electromechanical compon** and use of drawings, diagrams, and UT images. The presentation is systems used in nuclear power plants. The reseuch results technical but assumes limited specific knowledge of ultrasonics have since been usod by both the NRC and industry.The pro-or computers. The report is divided into 9 se,tions covering gram included seven major research projects that addressed conventional UT, computer-based UT, and evabation methodol-the following issues: (a) containment purge and vent valves per-ogy. Conventional UT topics include coordinate axes, scanning, forming under design basis loss of coolant accident loads, (b) instNment operation, RF and video signals, and A, B, and C-containment piping penetrations and isolation valves performing scans. Computer-based topics include sampling, digitization, under seismic icedings and design basis and severe accident signal analysis, image presentation, SAFT, ultrasonic hologra-containment wall displacements, (c) shaft seals for primary cool-phy, transducer arrays, and data interpretation. An evaluation ant pumps performing under station blackout conditions, (d) methodology for co' puter-based UT/ISI systems is presented, electncal cabinet internals responding to In-structure generated including questions, detailed procedures, and test block de-motion (rattling), and (e) in situ piping and valves responding to signs. Onef evaluations of several computer-based UT/ISI sys-seismic loadings. Another project investigating whether certain tems are given; supplementary volumes will provide detailed containment isolation valves will close under design basis con-evaluations of selected systems.

ditions was also started under this program. This report includes eight main sections, each of which provides a brief desenption NUREG/CR 5990: THE EFFECTS OF SOLAR-GEOMAGNETI-of one of the projects, a summary of the findings, and an over-CALLY INDUCED CURRENTS ON ELECTRICAL SYSTEMS IN view of the application of the results. A bibliography lists the NUCLEAR POWER STATIONS. SUBUDHI,M. Brookhaven Na-joumal articles, papers, and reports that document the research.

tional Laboratory. CARROLL.D.P. Florida, Univ. of, Ge.inesville, FL. KASTURI,S. MOS, Inc. January 1994.196pp. 9402150350.

NUREG/CR-5960: STEAM EXPLOSIONS: FUNDAMENTALS AND O"L^

ENGERGETIC BEHAVIOR. THEOFANOUS,T.G.; YUEN W.W.;

Th e e

e e ults of a study to evaluate the po-iforn a Univ of, Santa Barbara, CA. Jan-tential effects of geomagnetically induced currents (GICs) ry 9 2 90 This rrport presents the results of a rbultifaceted research caused by the solar disturbances on the in-plant electrical distri-bution system and equipment in nuclear power stations. The effort in the field of steam explosions. The scope ranges from plant specific electrical distribution system for a typical nuclear the fundamentals to assessing the energetics in applications rel-plant is modeled using the Electromagnetic Transient Program evant to Severe Accidents in Light Water Reactors. The consid-(EMTP). The computer model simulates online equipment and eration of fundamentals is budt around two key ideas: the water loads from the station transformer in the switchyard of the depletion phenomenon during premixing and the microinterac-power station to the safety-buses at 120 volts to which all elec-tions, including fragmentatinn kinetics, dunng propagation. The tronic devices are connected for plant monitoring. The analytical application to reactor conditions includes consideration of in-model of the plant's electrical distnbution system is studied to vessel steam explosions in PWRs and ex vessel explosions in all five containment designs in current phnts (in the USA). The identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides re-report is structured in three parts, dealing with premixing, propa-suits of the voltage harmonics levels that have been noted at gation, and energetics, respectively.

various electrical buses inside the planL The emergency circuits NUREG/CR 5963: CONTINUOUS AE CRACK MONITORING OF appear to be more susceptible to high harmonics due to the A DISSIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

normally light load conditions. In addit on to steady state ana!y-HUTTON.P.H.: FRIESEL,M.A.; DAWSON.J F. Battelle Memonal sis, this model was further analyzed simulating various plant Institute, Pacific Northwest Laboratory. December 1993.100pp.

transient conditions (e.g., loss of load or large motor start-up) 9402220168. PNL-8844. 78197:095.

occurring during GlC events. Detail models of the plant's pro-Acoustic emission (AE) technology for continuous surveillance tective relaying system employed in bus transfer application of a reactor component (s) to detect crack initiation and/or crack were included in this model to study the effects of the harmonic growth has been developed at Pacific Northwest Laboratory distortion of the voltage input. Potential harmonic effects on the (PNL), operated by Battelle Memorial Institute, under support uninterruptable power system (UPS) are qualitatively discussed from the U.S. Nuclear Regulatory Commission, Office of Nuclear as well Regulatory Research (U.S. NRC-RES). The technology was vali-dated off-reactor in several major tests, but it had not been vali-NUREG/CR-6042: PERSPECTIVES ON REACTOR SAFETY.

dated by monitoring crack growth on an operating reactor HASKIN,F E.

New Mexico, Univ. of, Albuquerque, NM.

system. A flaw indication was identified during normal inservice CAMP,A.L. Sandia National Laboratories. March 1994. 589pp.

inspcchon of piping at Philadelphia Electnc Company (PECO) 9404110335 SAND 93 0971. 78820:001.

Limenck Unit t reactor dunng the 1989 refueling outage. Eval-The U.S. Nuclear Regulatory Commission (NRC) maintains a uation of the flaw indication showed that it could remain in technical training conter at Chattanooga, Tennessee to provide place dunng the subsequent fuel cycle without compromising appropriate tra ning to both new and experienced NRC employ-safety. The existence of this flaw indication offered a long ees. This document describes a one-week course in reactor sought opportunity to validate AE surveillance to detect and nafety concepts. The course consists of five modules: (1) histor-evaluate crack growth during reactor operation. Through the co-ical perspective; (2) accident sequences; (3) accident progres-operation and support of PECO and the U.S. NRC-RES, AE in-sion in the reactor vessel; (4) containment characteristics and strumentation was installed by BNW and PECO under PECO design bases; and (5) source terms and offsite consequences.

Mod. No. 043-002 to monitor the flaw indication dunng two The course text is accompanied by slides and videos during the complete fuel cycles. This report discusses the results obtained actual presentation of the course.

=

Main Citations and Abstracts 7

NUREG/CR-6063: INTRAVAL PHASE 11 MODEL TESTING AT NUREG/CR-6077: DATA

SUMMARY

REPORT FOR FISSION THE LAS CRUCES TRENCH SITE. HILLS,R.G. New Mexico PRODUCT RELEASE TEST VI-6.

OSBORNE.M.F.;

State Univ., Las Cruces, NM. WlERENGA P.J. Arizona, Univ. of, LORENZ,R.A.; TRAVIS,J.R,; et al. Oak Ridge National Laborato-Tucson, AZ. LUIS,S.; et al. Massachusetts institute of Technolo-ry. March 1994. 67pp. 9404080092. ORNL/TM-12416.

gy, Cambridge, MA. January 1994. 143pp. 9402150366.

78794:197.

Test VI-6 was the sixth test in the VI series conducted in the 78123:209.

vertical fumace. The fuel specimen was a 15.2-cm-long section Several field expenments have been performed by scientists from the University of Anzona and New Mexico State University of a fuel rod from the BR3 reactor in Belgium.,The fuel had ex-perienced a burnup of ~42 MWrukg. with inert gas release at the Las Cruces Trench Site to provide data to test determi-during irradiation of ~2%. The fuel specimen was heated in an nistic and stochastic models for water flow and solute transport.

induction furnace at 2300 K for 60 min, initially in hydrogen, These expenments were performed in collaboration with INTRA.

then in a steam atmosphere. The released fission products VAL, an international effort toward validation of geosphere wwe cow in Wee segetiaHy opwated cohchon trass models for the transport of radionuclides. During Phase i of IN-designed to facilitate sampling and analysis. The fission product TRAVAL, quahtative comparisons between experimental data inventories in the fuel were measured directly by gamma-ray and model predictions were made using contour plots of water spectrometry, where possible, and were calculated by contents and solute concentrations. Detailed quantitative com-ORIGEN2. Integral releases were 75% for (85)Kr, 67% for parisons were not made. To provide data for more rigorous (129)l, 64% for (125)Sb, 80% for both (134)Cs and (137)CS, model testing, a third Las Cruces Trench experiment was de-14% for (154)Eu,63% for Te, 32% for Ba,13% for Mo, and

~

signed by scientists from the University of Arizona and New 5.8% for Sr. Of the totals released from the fuel,43% of the Mexico State University. Modelers frorn the Center for Nuclear Cs,32% of the Sb, and 98% of the Eu were deposited in the Waste Regulatory Analysis Massachusetts institute of Technol-outlet end of the furnace. During the heatup in hydrogen, the ogy, New Mexico State University, Pacific Northwest Laboratory, Zircaloy cladding melted, rar, down and reacted with some of and the University of Texas provided predictions of water flow the UO(2) and fission poducts, especially Te and Sb The total and tntium transport to New Mexico State University for analy-mass released from the tarnace to the collection system, includ-sis. Tha corresponding models assumed soil characterizations ing fesion products, fuel, and structural materials, was 0.57 g, j

ranging from uniform to deterministically heterogeneous to sto-almost equally divided between thermal gradient tubes and fil-t chastic. This report presents detailed quantitative comparisons ters. The release behaviors for the most volatile elements, Kr to field data.

and Cs,. vere in good agreement with the ORNL Diffusion Model.

NUREG/CR-6076: TR-EDB; TEST REACTOR EMBRITTLEMENT NUREG/CR-6088:

SUMMARY

OF 1991-1992 MISADMINISTRA-DATA BASE, VERSION 1.

STALLMANN,F.W - WANG,J. A..

TlON EVENT INVESTIGATIONS. OSTROM.L.T.; LEAHY,T.J.:

KAM.F.B. Oak Ridge National Laboratory. Januarh 1994.119pp NOVAK,S.D. EG&G Idaho, Inc. March 1994.61pp.9404040060.

9403140311. ORNL/TM-12415. 78516:001.

27 The Test Reactor Embattlement Data Base (TR-EDB) is a

, t g t on te s composed of representatives of the Idaho collection of results from irradiations in matenals test reactors. It National Engineering Laboratory (INEL), the U.S. Nuclear Regu-complements the Power Reactor Embntilement Data Base (PR-latory Commission (NRC), and subcontractors investigated and EDB), whose data are restricted to the results from the analysis analyzed seven misadministration events selected by the NRC of surveillance capsules in commercial power reactors. The ra-conceming medical radioisotopes. Each team was led by an tionale behind this restriction was the assumption that the re-INEL member and, depending on the nature of the event, in-sults of test reactor experiments may not be applicable to cluded three or more team members with appropriate expertise power reactors and could, therefore, be challenged if such data n radiation oncology, medical physics, nuclear medicine tech-were included. For this very reason the embnttlement predic-nology, risk analysis, and human factors. The investigations fo-Mns in the Reg Guide 1.99, Rev. 2 were based exclusively on cused on causes of the event, consequences, mitigating ac-power reactor data. However, test reactor experiments are able tions, and corrective actions. The investigation produced seven to cover a much wider range of materials and irradiation condi-major findings: 1) many misadministrations occurred primari'y tions that are needed to oxplon more fully a variety of models because procedures did not exist or because existing proce-for prediction of irradiation emt: ttlement. These data are also duras that were not sufficiently detailed, comprehensive, specif.

needed for the study of effects of annealing for hfe extension of ic, or clearly wntten; 2) although the NRC's quality management reactor pressure vessels that are difficult to obtain from surveil-(OM) rule can prevent many misadministrations, most licensees lance capsule results. The current data collection of the TR, in this study had not effectively implemented their OM pro.

EDB contains primanly Charpy test data, which are accompa.

grams; 3) the lack of substantial, direct involvement by radiation nied in most cases by tensile tests for the same irradiation con.

safety officers and authonzed users was often a direct cause of ditions. Information is available for 1,230 different irradiated misadministration; 4) a change in routine or the advent of a sets,797 of which are from base material (plates and forgings),

unique condition often predisposed misadministration; 5) hard-378 from welds, and 55 from heat-affectedqone materials. The ware failures, though rare, had severe consequences, particular-chemistnes of the investigated materials Span also a fairly wide ly when operating procedures, staff training, or other factors were not well implemented; 6) licensees

• corrective actions range, partcularly in the content of copper and nickel, which are were often narrow in focus; 7) the licensees lacked systematic considered the most important contributors to embnttlement methods for detecting and mitigating a misadministration once sensitivity, Complete chemistry information is available for 1,095 an error occurred.

t of the 1,230 samples (after discarding the HAZ information).

THe architecture of the TR-EDB is fully compatible with that of NUREG/CR-6103: PRIORITIZATION OF REACTOR CONTROL the PR-EDB so that the data from both databases can be easily COMPONENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CON.

merged if desired The data files are given in dBASE format and SEQUENCE OF AGING. LOWRY,W.; VIRGIL,R. Science & En-can be accessed with any personal computer using the DOS gineering Associates, Inc. NOWLEN,S. Sandia National Labora-operating system. " User friendly" utility programs have been tones. January 1994. 45pp. 9402150009. SAND 93-7107.

wntten to investigate the radiation embnttlement using this data 78122:333.

base. The utility programs are used to retneve and select spe-The Fire Vulnerability of Aged Electrical Components Test cite data, manipulate data, display data to the screen or pnnter, Program is to identify and assess issues of plant aging that and to fit and plot Charpy impact data.

could lead to an increase in nuclear power plant risk because of I

8 Main Citations and Abstracts fires. Histoncal component data and pnor analyses are used to staffing decisions for plant safety. The focus of this report is on prioritize a list of components with respect to aging erd fire vul-driving forces that have led to changes in staffing levels and to nerability and the consequences of their failure on plant safety the establishment of new positions between the mid-1980s and systems. The component hst emphasizes safety system control the early 1990s. Processes used at utihties and nuclear power components, but excludes cables, large equipment, and devices plants to make and implement these staffing decisions are also encompassed in the Equipment Qualification (EO) program. The discussed in the report. While general trends affecting the plant test program selected components identifred in a utility survey as a whole are presented, the major emphasis of this report is and developed test and fire conditions necessary to maximize on staffing changes and practices in the operations department, the effectiveness of the test program. Fire damage consider-includinq the operations shift crew. The findings in this report ations were hmited to purely thermal effects.

are based on interviews conducted at seven nuclear power lP ants and their parent utilities. A discussion of the key findings NUREG/CR-6107:

SUMMARY

OF MELCOR 1.8.2 CALCULA-l TlONS FOR THREE LOCA SEQUENCES (AG,S2D & S3D) AT is followed by a summary of the implications of staffing issues THE SURRY PLANT. KMETYK,L. Sarx.ha National Laboratones.

for plant safety.

SMITH.L. Geo Centers, Inc. March 1994. 200pp. 9404080073.

NUREG/CR-6123: AN INTERNATIONAL COMPARISON OF SAND 93 2042. 78794:001.

COMMERCIAL NUCLEAR POWER PLANT STAFFING REGU-Activities involving regulatory implementation of updated LATIONS AND PRACTICE.1980-1990. MELBER,0.; HAUTH,J.:

source term information were pursued. These activities include TERRILLE.; et al. Battelle Human Affairs Research Centers.

the identification of the source term, the identification of the March 1994. 70pp. 9404040052. PNL-8564. 78736:123.

chemical form of iodine in the source term, and the timing of A review of nuclear power plant staffing regulatory and indus-the source term's entrance into containment. These activities try practices en Canada, France, Gennany, Japan, Sweden, and are intended to support a more realistic source term for licens-the United Kingdom is presented in this report. International ing nuclear power plants than the current TID-14844 source trends in staffing regulatory approaches, industry practices, and term and current licensing assumptions. MELCOR calculations issues of concem that have potential relevance for the contin-were performed to support the technical basis for the updated ved development of nuclear power plant staffing policy in the source term. This report presents the results from three United States are highlighted. The 1980s were marked by signif.

MELCOR calculations of nuclear power plant accident se-icant growth in nuclear power operations internationally; howev-quences and presents compansons with Source Term Code er, growth of nuclear power is not expected to continue in the Package (STCP) calculations for the same sequences. The 1990s except in France and Japan. A continuum of regulatory three low-pressure sequences were analyzed to identify the ma-approaches was identified, ranging from prescriptive regulations terials which enter containment (source terms) and are available applied to all licensees to staffing requirements agreed to in the for release to the environment, and to obtain timing of so-plant operating licenses. Most of the changes observed in staff-i quence events. The source terms include fission products and ing regulations and practices in the early 1980s were made in other matenals such a6 those generated by core-concrete inter-response to the accident at the Three Mile Island Unit 2 nuclear actions. All three calculations, for both MELCOR and STCP.

power plant in 1979. These changes included widespread issu-analyzed the Surry plant, a pressurized water reactor (PWR) ance of new operator and licensing requirements and the estab-with a subatmospheric containment design.

I shment of natonal training centers. A period of relative stabihty NUREG/CR-6112 DRF FC: IMPACT OF REDUCED DOSE LIMITS followed these changes. Changes in tne latter half of the 1980s ON NRC LICENSED ACTIVITIES. Major issues in The imple-focused on continuing improvements and additions to training mentation Of ICRP/NCRP Dose Limit Recommendations. Draft curricula and methoos, most notably increased reliance on sim-Report For Comment. MEINHOLD,C.B. Brookhaven National ulator training.

Laboratory January 1994. 75pp. 9402220146. BNL-NUREG.

52394. 78191:001.

NUREG/CR-6132: BIAXIAL LOADING AND SHALLOW-FLAW EF-FECTS ON CRACK-TIP CONSTRAINT AND FRACTURE This report summarizes information required to estimate, at TOUGHNESS. BASS,B.R.; BRYSON.J.W.; THEISS,T.J.; et al.

least in qualitative terms, the potential impacts of reducing or Oak Ridge National Laboratory. January 1994. 74pp.

cupational dose hmits below those given in 10 CFR 20 (Re-9403140303. ORNL/TM 12498. 78477:001.

visod). The data from a questionnaire developed for this project and data from existing surveys were used to estimate the A program to develop and evaluate fracture methodologies impact of three dose limit options; 10 mSv yr(-1),20 mSv yr( 1) for the assessment of crack-tip constraint effects on fracture and a combination of an annual limit of 50 mSv yr( 1) coupled' toughness of reactor pressure vessel (RPV) steels has been ini-with a cumulative hmit in tem equal to age in years. The overall tiated in the Heavy-Section Steel Technology (HSST) Program.

conclusions of the study are: (1) Although 10 mSv yr( 1) is a Crack-tip constraint is an issue that significantly impacts fracture reasonable hmit for many licensees, such a hmit could be ex-mechanics technologies employed in safety assessment proce-traordinanly difficult and potentially destructive to some (2) dures for commercially licensed nuclear RPVs. The focus of studies described herein is on the evaluatxm of two stressed-Twenty mSv yr(-1) as a kmit is possible for some of the latter groups, but for others it would prove difficult, (3) Fifty mSv yr( 1) based methodologies for quantifying crack-tip constraint (i.e., J-and age in 10's of mSv would appear acceptable both in terms O theory and a micromechanical scaling model based on critical of the related hfetime risk of cancer and severe genetic effects Jtressed volumes) through apphcations to experimental and fractographic data. Data were utshzed from single-edge notch to the most highly exposed and in terms of practicality of oper-ation This acceptability in some segments of the industry is bend (SENB) specimens and HSST-developed cruciform beam specimens that were tested in HSST shallow-crack and biaxial based on the adoption of a " grandfather ct&use' for those ex-ceeding the cumulative limit.

testing programs. Resutts from applications indicate that both the J-O methodology and the micromechanical scahng model NUREG/CR-6122: STAFFING DECISION PROCESSES AND can be used successfully to interpret expenmental data from ISSUES Case Studies Of Seven U.S. Nuclear Power Plants.

the shallow and deep-crack SENB specimen tests. When ap-MELDER.B.; ROUSSEL,A; BAKER,K.; et al. Batt3lle Human Af-phed to the uniaxially and biaxially loaded cruciform specimens, fairs Research Centers. March 1994. 53pp. 9404040039. PNL-the two methodologies showod some promising features, but 8428. 78736:001.

also raised several questions conceming the interpretation of The objective of this report is to ident fy how decisions are constraint conditions in the specimen based on near tip stress made regarding staffing levels and positions for U.S. nuclear fields. Fractographic data taken from the fracture surfaces of power plants. In this report, a framework is provided for under-the SEN8 and cruciform specimens are used to aasess the rel-standsng the major forces dnving staffing and the implications of evance of stress-based fracture characterizations to conditions l

1

Main Citations and Abstracts 9

at cleavaga snitiation artes Unresolved issues identified from mens. Charpy V-notch specimens irradiated in the same cap-these analyses require resolutson as part of a validation process sules as the crack-arrest specimens were also tested, and a 41-for biarial loading applications. This report is designated as J transition temperature shift was determined from these speci.

HSST Repor1 No.142.

mens. "Mean" curves of the same form as the ASME K(la)

NUREG/CR 6133: FRAGMENTATION AND OUENCH BEHAVIOR curve were fit to all the data with only the reference tempera-OF CORIUM MELT STREAMS IN WATER, SPENCER.B.W.;

ture as a parameter lhe shift between the mean curves agrees well with the 41-J transition temperature shift obtained from the WANG.Ka BLOMOUIST,C.A.; et al. Argonne National Laborato-Charpy V notch specimen tests.

ry. February 1994. 407pp. 9404010160. ANL-93/32. 78717:066.

The inteiaction of molten core matenals with water has been NUREG/CR-6142: TENSILE-PROPERTY CHARACTERIZATION investigated for the pour stream mixing mode. This interaction OF THERMALLY AGED CAST STAINLESS STEELS.

plays a crucial role dunng the later stages of in-vessel core melt MICHAUD,W.F.; TOBEN P.T.; SOPPET,W.K ; et al. Argonne Na-progression inside a light water reactor such as during the TMI-tional Laboratory. February 1994. 257pp. 9402250117. ANL-93/

2 accident. The key issues which anse during the molten core

35. 78278:001, relocation include: i) the thermal attack and possible damage to The effect of thermal aging on tensile properties of cast stain-the RPV lower head from the impinging molten fuel stream and/

less steels during service in light water reactors has been evalu-or the debris bed, ii) the molten fuel relocation pathways includ-ated. Tensile data for several experimental and commercial ing the effects of redistnbution due to core support structure heats of cast stainless steels are presented. Thermal aging in-and the reactor lower internals, iii) the quench rate of the creases the tensile strength of these steels. The high-C Mo-molten fuel through the water in the lower plenum, iv) the steam beanng CF-8M steels are more susceptible to thermal aging generation and hydrogen generation dunng the interaction, v) than the Mo-free CF-3 or CF-8 steels. A procedure and correla-the transient pressurization of the pnmary system, and vi) the tions are presented for predicting the change in tensile flow and possibility of a steam explosion. In order to understand these yield stresses and engineering stress-vs-strain curve of cast issues, a series of six expenments (designated CCM-1 through -

stainless steel as a function of time and temperature of service.

6) was performed in which molten corium passed through a The tensile properties of aged cast stainless steel are estimated deep pool of water in a long, slender pour stream mode. Re-from known material information, i.e., chemical composition and sults discussed include the transient temperatures and pres-the initial tensile strength of the steel. The correlations de-sures, the rate and magnitude of steam / hydrogen generation, scnbed in this report may be used for assessing thermal embnt-and the postlest debris characteristics, tiement of cast stainless steel components.

KUREG/CH-6138: USER'S GUIDE FOR SIMPLIFIED COMPUTER MODELS FOR THE ESTIMATION OF LONG-TERM PERFORM.

NUREG/CR-6145: VERIFICATION AND VALIDATION OF THE SAPHIRE VERSION 4.0 PRA SOFTWARE PACKAGE.

ANCE OF CEMENT-BASED MATERIALS. PLANSKY,L E.;

SEITZ,R.R.

EG&G Idaho, Inc. February 1994. 94pp.

BOLANDER,T.W.; CALLEY,M.B4 CAPPS.E.L.; et al. Idaho Na-9403140184. EGG-2719. 78458:092.

tional Engineenng Laboratory. February 1994. 331pp.

9404010225. EGG-2713. 78722:289.

This report documents user instructions for several simplified subroutines and driver programs that can be used to estimate A venfication and validation (V8V) process has been per-various aspects of the long-term performance of cement-based formed for the System Analysis Programs for Hands-on Integrat-barriert used in low-level radioactive waste disposal facilities ed Reliability Evaluation (SAPHIRE). SAPHIRE is a set of four The subroutines are prepared in a modular fashion to allow computer programs that the Nuclear Regulatory Commission flexibility for a vanety of applications Three levels of codes are (NRC) developed to perform probabilistic risk assessments provided. the individual subroutines, interactive drivers for each (PRAs). These programs allow an analyst to crea3. quantify, of the subroutines, and an interactive main driver, CEMENT, and evaluate the risk associated with a facility or process being that calls each of the individual dnvers. The individual subrou, analyzed. The programs included in this set are Integrated Reli-tines for the different models may be taken independently and ability and Risk Analysis System (IRRAS), System Arealysis and used in larger programs, or the dnver modules can be used to Risk Assessment (SARA), Models and Results Database (MAR-execute the subroutines separately or as a part of the main D), and Fault Tree / Event Tree /Diping and Instrumentation Dia-driver routine. A bnef program description is included and user-gram (FEP) graphical editor. The V&V steps included a V&V interface instructions for the individual subroutines are docu-plan to desenbe the process and enteria by which the VaV mented in the main report. These are intended to be used when wou!d be performed, a software requirements documentation the subroutines ar9 used as subroutines in a larger computer review to determine the correctness, completeness, and tracea-code. User instructions for the drivers and example interactive bility of the requirements; a user survey to determine the useful-screens for the main drivers are provided in Appendm A. Exam-ness of the user docurrentation, identification and testing of ples showing the use of the individual driver routines to execute vital and non-vital features, and documentation of the test re-suits.

the different subroutines and test data are included in Appendix B. Programmer notes are provided in Appendix C and the con.

NUREG/CR-6147 V01: CHARACTERIZATION OF CLASS A figuration control system is discussed in Appendix D.

LOW-LEVEL RADIOACTIVE WASTE 1986-1990.Executrve Sum-NUREG/CR-6139: CRACK ARREST TESTS ON TWO IRRADIAT.

mary. DEHMEL.J-C.; LOOMIS,D.; MAURO.J.; et at. S. Cohen &

ED HIGH-COPPER WELDS. Phase 11: Results Of Duplex Type Associates, Inc. January 1994. 92pp. 9403140342. 78456:001.

Specimens. ISKANDER,S.Ka CORWIN,W.R.; NANSTAD,R K.

This report describes the physical, chemical, and radiological Oak Ridge National Laboratory. March 1994. 138pp.

properties of Class A low-level radioactive waste using data 9403140206. ORNL/TM-12513. 78476:176.

contained in the Manifest Information Management System The objective of the Heavy-Section Steel Irradiation Program (MIMS). Other sources of information include reports prepared Sixth irradiation Series is to determine the effect of neutron irra-by the NRC, DOE, low level waste Compacts and States, and diation on the shift and shape of the lower-bound curve to trade industries. The database characterizes low-level waste crack-arrest toughness data. Two submerged-arc welds with shipped for disposal from 1986 to 1990. A computer program copper contents of 0.23 and 0 31 wt % were commercially fab-was developed to analyze the data, with the results summarized ricated in 200 mm-thick plate. Crack-arrest specimens fabricat-in tap histograms, and cumulative distribution curves pre-ed from these wolds were irradiated at a nominal temperature sen'

. Jionuclide concentration distnbutions in Class A waste of 288 degrees C to an average fluence of 1.9 x 10(19) neu-as t

,ction of waste streams, waste generators, and by re-trons/cm(2)(>1 MeV) This is the second report giving the re-gion=. The report also provides information charactercing the suits of the tests on irradiated duplex. type crack-arrest speci-methods and facilities used to treat and dispose of non-radioac-

10 Main Citations and Abstracts tive waste, including industrial, municipal, and hazardous waste were held in Washington, DC., San Francisco, CA, Oklahoma regulated under Subparts C and D of RCRA. The information in-City, OK, and Cleveland, OH. Related comments from these cludes a list of disposal options, the geographical locations of meetings were reviewed and comments which differed substan-such facihties, and a descnption of such processing and dispos-tially from those from the workshops are also summarized in the al facilities.

body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

NUREG/CR-6147 V02: CHARACTERIZATION OF CLASS A LOW-LEVEL RADIOACTIVE WASTE 1986-1990. Main Report-NUREG/CR-6158: IMPLICATIONS FOR ACCIDENT MANAGE-Part A. DEHMEL,J-C.; LOOMIS D.; MAURO,J.; et al. S. Cohen &

MENT OF ADDING WATER TO A DEGRADING REACTOR Associates, Inc. January 1994. 300pp. 9403140349 78455:001, CORE. KUAN,P.; HANSON,D.J.; PAFFORD.D.J.; et al. EG&G See NUREG/CR.6147,V01 abstract.

Idaho, Inc. February 1994. 220pp. 9404010230. EGG-2644.

78723:256.

NUREG/CR-6147 V03: CHARACTERIZATION OF CLASS A This report evaluates both the positive and negative conse-LOW-LEVEL RADIOACTIVE WASTE 1986-1990. Main Report-quences of adding water to a degraded reactor core during a Part B. DEHMEL,J-C.; LOOMIS.D.; MAURO J.; et al. S. Cohen &

severe accident. The evaluation discusses the earliest possible Associates, Inc. January 1994. 300pp. 9403140351. 78452:001.

stage at which an accident can be terminated and how plant See NUREG/CR.6147,V01 abstract.

personnel can best respond to undesired results. Specifically NUREG/CR-6147 V04: CHARACTERIZATION OF CLASS A discussed are (a) the potential for plant personnel to add water LOW. LEVEL RADIOACTIVE WASTE 1986-1990. Appendices A-for a range of severe accidents, (b) the time available for plant E. DEHMEL,J-C.; LOOMIS,D.; MAURO J.; et al. S. Cohen & As-personnel to act, (c) possible plant responses to water added sociates, Inc. January 1994. 300pp. 9403140353. 78475:001.

during the various stages of core degradation, (d) plant instru-See NUREG/CR-6147,V01 abstract.

mentation available to understand the core condition and (e) the

[tages of severe acc de s NUREG/CR-6147 V05: CHARACTERIZATION OF CLASS A LOW. LEVEL RADIOACTIVE WASTE 1986-1990. Appendix F.

DEHMEL,J-C.; LOOMIS,D.; MAURO.J.; et af. S. Cohen & Asso-NUREG/CR-6169:

RELAY TEST PROGRAM. Series 11 ciates, Inc. January 1994. 600pp. 9403140355. 78473:012.

Tests. Integral Testing Of Relays And Circuit Breakers.

See NUREG/CR-6147,V01 abstract.

BANDYOPADHYAY,K; KUNKEL.C.; SHTEYNGART,S. Brookha-b ary 1994.176pp. 9403140191.

NUREG/CR-6147 V06: CHARACTERIZATION OF CLASS A BN NU E 24 78 76 LOW LEVEL RADIOACTIVE WASTE 1986-1190. Appendices G-This report presents the results of a relay test program con-J. DEHMEL J-C.; LOOMIS.D.; MAURO,J.; et al. S. Cohen & As-ducted by Brookhaven National Laboratory (BNL) under the sociates, Inc. January 1994. 500pp. 9403140360. 78471:114.

sponsorship of the U.S. Nuclear Regulatory Commission (NRC).

See NUREG/CR.6147,V01 abstract.

The program is a continuation of an earlier test program the re-NUREG/CR-6147 V07: CHARACTERIZATION OF CLASS A sults of which were published in NUREG/CR-4867. The current LOW-LEVEL RADIOACTIVE WASTE 1986-1990. Appendices K-program was carried out in two phases: electrical testing and vi-P. DEHMEL,J-C.; LOOMIS,D.; MAURO,J.; et al. S. Cohen & As-bration testing. The objective was primarily to focus on the elec-sociates, Inc. January 1994. 400pp. 9403140364. 78470:005.

trical discontinuity or continuity of relays subject to electrical See NUREG/CR-6147,V01 abstract.

pulses and vibration loads. The electrical testing was conducted by KEMA-Powertest Company and the vibration testing was per-NUREG/CR-6149: APPLICATIONS OF FIBER OPTICS IN PHYSI-formed at Wyle Laboratones, Huntsville, Alabama. This report CAL PROTECTION BUCKLE,T.H. Sandia National Laboratories.

discusses the test procedures, presents the test data, includes March 1994. 51pp. 9404080104. SAND 93-2478. 78794:261, an analysis of the data and provides recommendations regard-The purpose of this report is to provide technical information ing reliable relay testing.

useful for the development of fiber-optic communications and intrusion detection subsystems relevant to physical protection.

NUREG/CR-6194: METALLOGRAPHIC AND HARDNESS EXAMI-There are major sections on fiber-optic technology and applica-NATIONS OF TMI-2 LOWER PRESSURE VESSEL HEAD SAM-tions. Other topics include fiber-optic system components and PLES. KORTH.G.E. EG&G Idaho, Inc. March 1994. 124pp.

systems engineering. This document also contains a glossary, a 9404110355. TMI V(92)EG01, 78817:224.

list of standards and specifications, and a list of fiber-optic ven-Fifteen steel samples were removed from the lower pressure dors.

vessel head of the damaged TMI-2 nuclear reactor to assess P*

NUREG/CR-6156:

SUMMARY

OF COMMENTS RECEIVED 9

FROM WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DE-sections of thirteen of the samples and partial sections of the COMMISSIONING. CAPLIN.J.; PAGE G.; SMITH,D.; et al. Ad-other two samples underwent hardness and metallographic ex-vanced Systems Technology, Inc. January 1994. 200pp, aminations at the Idaho National Engineering Laboratory. These 9402150306. 78122:101.

examinations have shown that eleven of the fifteen samples did The Nuclear Regulatory Commission (NRC) is conducting an not exceed the ferrite-austenite transformation temperature of enhanced participatory rulemaking to establish radiological ente-727 degrees C during the accident. The remaining four samples ria for site cleanup and decommissioning of NRC-licensed facili-did show evidence of having a much more severe thermal histo-ties. Open public meetings were held during 1993 in Chicago, ry. The samples from core grid positions F-10 and G-8 are be-IL, San Francisco, CA Boston, MA, Dallas, TX, Philadelphia lieved to have experienced temperatures of 1,040 to 1,060 de-PA, Atlanta, GA, and Washington, DC. Interested parties were' grees C for about 30 minutes. Samples from positions E-8 and invited to provide input on the rulemaking issues before the E 6 appear to have been subjected to 1,075 to 1,100 degrees C NRC staff develops a draft proposed rule. This report summa-for approximately 30 minutes.

nzes 3.635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed let-NUREG/CR-6196: CALCULATIONS TO ESTIMATE THE MARGIN ters from individuals and organizations. No analysis or response TO FAILURE IN THE TMI2 VESSEL. STICKLER,L.A.;

to the comrnents is included. The comments refiect a broad REMPE.J.L.; CHAVEZ,S.A.; et al EG&G Idaho, Inc. March spectrum of view. points on the issues related to radiological cri-1994. 300pp. 9404060281. TMI V(93)EG01, 78759:001.

teria for site cleanup and decommissioning. The NRC also held As part of the OECD-sponsored Three Mile island Unrt 2 public meetings on the scope of the Generic Environmental (TMI-2) Vessel Investigation Pro,ect (VIP), margin-to-failure cal-impact Statement (GEIS) during July 1993. The GEIS meetings cutations for mechanisms having the potential to threate. the

Main Citations and Abstracts 11 integrity of the vessel were performed to improve understanding A seismic probabilistic risk assessment (PRA) of a nuclear of events that occurred dunng the TMI-2 accident. Anatyses plant requires identification and information regarding the seis-considered four failure me.chanisms: tube rupture, tube electon, mic hazard at the plant site, dorninant accident sequences lead-global vessel failure, and localized vessol failure. Calculatonal ing to core damage, and structure and equipment fragihties. Un-input was based on data from the TMI-2 VIP examinations of certainties are associated with each of these ingredients of a the vessel steel samples, the instrument tube nozzles, and sam-PRA. The sensitivity of accident sequence probabikties and pies of the hard layer or debns found on the TMI 2 vessel lower hrgh-confidence, low probabihty of failure (HCLPF) plant fragili-head. Sensstrvity studies were performed to investigate the un.

ties to seismic hazard and fragihty modeling assumptions was certainties in key parameters for these analyses.

examinod for three nuclear power plants. Mean accident se-quence probabihties were found to be relatively insensstrve (by a NUREQ/CR-6198: THi-2 INSTRUMENT NOZZLE EXAMINA-factor of two or less) to: uncertainty in the coefficient of vana-TlONS PERFORMED AT THE INEL.

AKERS.D.W.;

tion (loganthmic standard deviation) desenbing inherent random-SCHUETZ.D.K. EG&G idaho, Inc. March 1994. 130pp.

ness in cornponent fragility; truncaten of lower tail of fragility; 9404010249. EGG-2735. 78728.034.

uncertainty in random (non-seismic) equipment failures (e.g.,

As part of the Three Mile Island Unit 2 (TMI-2) Vessel Investe diesel generators); correlation between component capacities; Gation Project, under the auspices of the Organization for Eco-and functional form of fragility family. Accident sequence prob-nomic Cooperation and Development, examinations were per-abilities, expressed in the form of a frequency distribution, are formed at the Idaho Natonal Engineonng Laboratory on eight affected significantly by the seismic hazard modeling. When the nozzles and one guide tube from the TMI-2 reactor vessel. This fragility modeling and plant logic are effectively uncoupled from document desenbes the examination methodology, summarizes the seismic hazard analysis in a seismic margin study, the influ-the examination results, and presents interpretstons of the re-ence of the large uncertainty in the seismic hazard is elimhat-sults as they relate to the damage to the reactor vessel and to ed. In seismic margin studies, uncertainties in fragility modehng the development of a core relocation scenano. Not all examina-assume a different significance than they do in seismic PRA tions onginally proposed as part of tnis program were complet-studies. Gross design and construction errors and ther impact ed due to facihty problems at the INEL. Consequently, only the on estimates of seismic risk are dealt with in approximahon by results of completed aspects of the examination program are postulating various error scenanos and their effect on compo-presented.

nent fragilities and recalculating the core damage probabihties.

Plausible design /constructon errors appear to have little effect NUREG/CR-6209: MEMPHIS AREA RE"alONAL SEISMIC on mean core damage probabihties.

NETWORK. Final Report, October 1986 - September 1992.

CHlU,J M.; JOHNSTON,A.C. Memphis State Univ., Memphis, NUREG/lA-0114: ASSESSMENT OF RELAPS/ MOD 3 WITH THE TN March 1994. 69pp 9404110348. 78831:143.

LOFT L91/L3-3 EXPERIMENT SIMULATING AN ANTICIPAT.

The Memphis Area Rogional Seismic Network (MARSN) has ED TRANSIENT WITH MULTIPLE FAILURES. BANG,Y.S.;

provided emportant southern coverage of the New Madnd seis.

SEUL,K.W.; KIM,H.J. Korea Institute of Nuclear Safety. February mic zone (NMSZ) The network helped to identify the Cntienden 1994.112pp. 9404010254. ICAP00196. 78728.155.

County fault zone located east of and parallel to the SW seg.

The RELAPS/ MOD 3 Sm5 code was assessed using the L91/

ment of the NMSZ. MARSN data has also tKen added into a L3-3 test carned out in the LOFT facihty, a 1/60-scaled experi-database obtained by the PANDA expenment for a comprehen-mental reactor, simulating a loss of feedwater accident with sive seismological study of the NMSZ. Results demonstrate that multiple failures and the sequentially-induced small break loss-earthquakes in the NMSZ are mainly contined within depths of-coolant accident. The code predictability was evaluated for ing from 3 to 15km. The SW, NW, and NE segments of the the four separated sub-penods with respect to the system re-rang'SZ are characterized by narrow vertical stnke-shp faults. The sponst initial heatup phase, spray and PORV cychng phase, NM central NMSZ, however, is very comphcated. The northcentral blowdown phase and recovery phase. Based on the compari-section is charactonzed by a well-defined planar feature dipping sons of the results from the calculaton with the expenment

~31 degrees SW which shows dominantly normal faulting. The data, it is shown that the overall thermal-hydraulic behavior im-southcentral section shows a ~48 degrees SW dipping fault portant to the scenario such as a heat removal batween the pn-with dominantly reverse faulting. Although the E W regional mary side and the secondary side and a system depressuriza-stress may play an important role in fault movements in the tion was well-predicted and that the code could be apphed to NMSZ, the comphcaton in focal mechanisms suggests that the full-scale nuclear power plant for an anticipated transient other factors including postseismic relaxation by the 1811-1812 with multiple failures within a reasonable accuracy. The minor earthquakes, anterachons between adjacent fault segments, or discrepancies between the predicton and the experiment were features sud as the right-lateral stnke-shp Cratenden County identified in reactor scram time, post-scram behavior in the ini-fauft cannot be overlooked in future tectonic studies of the tial heatup phase, excessive heatup rate in the cychng phase, NMSZ.

insufficient energy convected out the PORV under the hot leg stratrfied condition in the saturated blowdown phase and void NUREG/GR 0008: VAllDATION OF SEISMIC PROBABILISTIC distributon in secondary side in the recovery phase. This may RISK ASSESSMENTS OF NUCLEAR POWER PLANTS.

come from the code uncertainties in predicting the spray mass ELLINGWOOD,B. Johns Hopkins Univ., Baltimore, MD. January flow rate, the associated condensaton in pressurizer and junc-1994.134pp 9403150302. 78501.001.

tion fluid density under stratified conditen.

i 1

4 e._

m.-

t_

.L, e

a

l l

Secondary Report Number index This index lists, in alphabetical order, the performing organization issued report codes for the NRC contractor and international agreement reports iii 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 NUMBER SECONDARY REPORT NUMBER F.EPORT NUMBER ANL-93/32 NUREG/CR-6133 ORNL/NOAC-232 NUREG/CR-4674 V18 ANL-93/35 NUREG/CR-6142 ORNL/TM 10328 NUREG/CR4816 R02 OMI-2173 NUREG/CR 4509 V03 N2 fh:

hkhh 5 RO1 BNL-NUREG-52309 NUREG/CR-5812 ORNL/TM-12416 NUREG/CR-6077 BNL -NUREG-52359 NUREG/CR-5990 ORNL/TM-12498 NUREG/CR-6132 DNL-NUREG-52394 NUREG/CR-6112 DAF FC ORNL/TM-12513 NUREG/CR-6139 BNL-NUREG-52406 NUREG/CR-6169 PNL4462 NUREG/CR-5161 V02 EGG 2562 NUREG/CR-5314 VOS PNL-8428 NUREG/CR4122 kig$

hkhfhh:$

EGG 2644 NUREG/CR-6158 EGG 2636 NUREG/CR-5935 PNL-8919 NUREG/CR-5985 EGG 2707 NUREG/CR-6088 SAND 861309 NUREG/CR-4551 V01 R1 E GG-2713 NUREG/CR4145 SAND 93-0234 NUREG/CR-5407 EGG 2719 NUREG/GR-6138 SAND 93-0971 NUREG/CR4042 EGG-2731 NUREG/CR 6194 N

D93

/

EGG 2735 NUREG/CR4198 SAND 93-7107 NUREG/CR-6103 ICAP00196 NUREG/lA.0114 1MI V EG01 NUREG/CR4194 NEA/CSNI/R(93)8 NUREG/CP-0127 TMIV EG01 NUREG/CR4196 ORNL/NOAC 232 NUREG/CR-4674 V17 TMIV EG01 NUREG/CR4198 13

s a

^------------ -

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.

ABU-EID,R.

BOLANDER,T.W.

NUREG-1486: FINAL SAFETY EVALUATION REPORT TO LICENSE NUREG/CR-6145: VERIFICATION AND VALIDATION OF THE SAPHIRE THE CONSTRUCTION AND OPERATION OF A FACILITY TO VERSION 4.0 PRA SOFTWARE PACKAGE.

RECEIVE. STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NEAR CLtVE, UTAH Docket No. 40 8989-(Envirocare of Utah,lnc )

BORGES,T, NUREG/CR.5569 R01: HEALTH PHYSICS POSITIONS DATA BASE.

AKERS,D.W.

NUREG/CR4198. TMI.? INSTRUMENT NOZZLE EXAMJNATIONS PER.

BRAMWELL.D.L FORMED AT THE INEL.

NUHEG/CFI 5935:

SUMMARY

OF WORK COMPLETED UNDER THE ENVIRONMENTAL AND DYNAMIC EOUlPMENT QUALIFICATION RE.

ALLENSPACH,F.

SEARCH PROGRAM (EDOP).

NUREG.1214 R13: HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

IC ASSESSMENT OF LICENSEE PERFORMANCE.

BREEDING,R.J.

NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCOENT ALLISON,0.P.

RISKS-METHODOLOGY FOR THE CONTAINMENT, SOURCE NUREG-1022 RO1 DR FC: EVENT REPOR11NG GUIDELINES TERM. CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

)

10CFR50.72 AND 50.73 Second Draft For Cornment.

NU

/CR-4551 V01 R1: EVALUATION OF SEVERE ACCOENT UR G R5 STEAM EXFtOSIONS: FUNDAMENTALS AND EN-R'SKS: METHODOLOGY FOR THE CONTAINMENT SOURCE GERGETIC BEHAVIOR' TERM, CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

ANGEL.LJ.

NUREG/CR-5985. EVALUATION OF COMPUTER. BASED ULTRASONIC BRUMMETT,E.

INSERVICE INSPECTON SYSTEMS.

NUREG 1486: FINAL SAFETY EVALUATION REPORT TO LICENSE THE CONSTRUCTION AND OPERATION OF A FACILITY TO ANGELINI,S.

RECEIVE, STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NUREG/CR-5960 STEAM EXPLOSIONS-FUNDAMENTALS AND EN-NEAR CLIVE, UTAH Docket No. 40-8989.(Envirocare of Utah,Inc.)

GERGETIC BEHAVIOR.

BRUS T,F, l

ASFURA,A.P.

NOREGiCR-4590 V03 N2; SHORT CRACKS IN PIPING AND PIPING NUREG/CR 5407: ASSESSMENT OF THE IMPACT OF DEGRADED WELDS Senuannual Report October 1992 March 1993.

SHEAR WALL STIFFNESSES ON SEISMIC PLANT HISK AND SEIS-Mic DESON LOADS.

BR YSON,J.W.

NUREG/CR-6132: BIAXIAL LOADING AND SHALLOW-FLAW EFFECTS d CR 5101 V02: EVALUATION OF SAMPLING PLANS FOR IN-i SERVICE INSPECTION OF STEAM GENERATOR BUCKLE.T.H.

TUBES Cornprehensive Analyteal And Monte Carlo Sarnulatoon Results NUREG/CR-6149: APPLICATIONS OF FIBER OPTICS IN PHYSICAL For Several Sarnplin0 Plans.

PROTECTION.

BAKER,K.

gygoggi,L NUREG/CR-6122:

STAFFING DECISION PROCESSES AND NUREG-1486 FINAL SAFETY EVALUATION REPORT TO LICENSE ISSUES. Case Studies Of Seven U.S. Nuclear Power Plants-THE CONSTRUCTON AND OPERATION OF A FACILITY TO BANDYOPADHYAY K RECEIVE. STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NUREG/CR4169I RELAY TFST PROGRAM. Series 11 Tests. Integral Test.

NEAR CLIVE, UTAH Docket No. 40-8989(Envrocare of Utah,Inc.)

6ng Of Relays And Crcuit Breakers.

CALLE Y,M.8.

BANO,Y.S.

NUREG/CR4145: VERIFICATION AND VALIDATION OF THE SAPHIRE NUREG/lA 0114: ASSESSMENT OF RELAP5/MOC3 WITH THE LOFT VERSION 4.0 PRA SOFTWARE PACKAGE.

L9-1/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRANSIENT CA WITH MULTIPLE FAILURES.

NUR G CR-0042: PERSPECTIVES ON REACTOR SAFETY, SASS.B.R.

NUREG/CR.6132: BIAXIAL LOADING AND SHALLOW-FLAW EFFECTS CAPLIN.J.

ON CRACK.TIP CONSTRAINT AND FRACTURE TOUGHNESS.

NUREG/CR4156:

SUMMARY

OF COMMENTS RECEIVED FROM WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSON-I BERK.B.

ING.

4 NUREG/CR 6123. AN INTERNATONAL COMPARISON OF COMMER.

CIAL NUCLEAR POWER PLANT STAFFING REGULATONS AND CAPPS.E.L PRACTICE.19801990.

NUREG/CA.6145: VERIFICATION AND VALIDATON OF THE SAPHIRE VERSION 4 0 PRA SOFTWARE PACKAGE.

BLOMoutST,C A.

NUREG/CR 6133 FRAGMENTATON AND OUENCH BEHAVIOR OF' CARROLL.D.P.

CORIUM MELT STREAMS IN WATER NUREG/CR-5990: THE EFFECTS OF SOLAR GEOMAGNETICALLY IN-DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR BOHN,M.P.

POWER STATIONS.

r NUREG/CR-540't; ASSESSMENT OF THE IMPACT OF DEGRADED SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS.

CARTER,D.

MIC DESIGN LOADS NUREG/CR-5569 R01: HEAL 1H PHYSICS POSITIONS DATA BASE.

15

16 Personal Author index CHAVEZ,S.A.

DOCTOR,S.R.

NUREG/CR41% CALCULATIONS TO ESTIMATE THE MARGIN TO NUREG/CR-5905: EVALUATON OF COMPUTER-BASED ULTRASONIC FAILURE IN THE TMI 2 VESSEL INSERVICE INSPECTION SYSTEMS.

CHEN,X.

DOLAN,B.W.

NUREG/CR-5960 STEAM EXPLOSIONS: FUNDAMENTALS AND EN-NUREG/CR-4674 V17. PRECURSORS TO POTENTIAL SEVERE CORE GERGETIC BEHAVIOR.

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Main Report And Appendix A.

CHlu,J.M-NUREG/CR 4674 V18: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR.6209 MEMPHIS AREA REGIONAL SEISMIC DAMAGE ACCOENTS: 1992 A STATUS REPORT. Appendices B. C, D, NETWORK.Fmal Report. October 1986. Septernber 1992 E, F, And G.

CHOPRA,0.K.

DONOGHUE,J.E.

NUREG/CR-6142: TENSILE PROPERTY CHARACTERl2ATION OF NUREG 1368: PREAPPLICATION SAFETY EVALUATION REPORT FOR THERMALLY AGED CAST STAINLESS STEELS.

THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

LOUID-METAL REACTOR. Final Report.

CLETCHER,J.W.

NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE DONOHEW,J.N PREAPPtl CAT ON SAFETY EVALUATION REPORT FOR DAMA ACCIDENTS: 1992 A STATUS REPORT. Main Report And NUREG-1368 NUREG/CR-4'674 V18 PRECURSORS TO POTENTIAL SEVERE CORE THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

LOUID-METAL REACTOR Final Report.

DAMAGE ACCIDENTS 1992 A STATUS REPORT. Appendices B, C, D, E.E And &

DOYLE,D.J.

NUREG/CR-5407: ASSESSMENT OF THE IMPACT OF DEGRADED COLLINS,J.L SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-NUREG/CR 6077: DATA

SUMMARY

REPORT FOR FISSION PRODUCT RELEASE TEST VI-6.

MIC DESIGN LOADS.

COPINGER,D A.

DURBIN,N.

NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-6122:

STAFFING DECISION PROCESSES AND DAMAGE ACCIDENTS 1992 A STATUS REPORT. Main Report And ISSUES. Case Studies Of Seven U.S. Nuclear Power Plants.

Appenden A.

NUREG/CR 4674 V18 PRECURSORS TO POTENTIAL SEVERE CORE ELLINGWOOD,B.

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices B, C, D.

NUREG/GR 0008. VALIDATION OF SEISMIC PROBABILISTIC RISK AS-E, F, And G.

SESSMENTS OF NUCLEAR POWER PLANTS.

CORRADINI.M.L.

FLIEGEL,M.

NUREG/CR 6196_ CALCULATIONS TO ESTIMATE THE MARGIN TO NUREG 1486: FINAL SAFETY EVALUATION REPORT TO LICENSE FAILURE IN THE TMI-2 VESSEL THE CONSTRUCTION AND OPERATION OF A FACILITY TO RECEIVE. STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL CORWIN,WA NEAR CLIVE, UTAH. Docket No. 40-8989 (Envirocare of Utah,inc.)

NUREG/CR 6139' CRACK-ARREST TESTS ON TWO IRRADIATED HIGH-COPPER WELDS. Phase ll. Results Of Duplex Type Specirnens.

FORSLUND,C.

NUREG/CR-6122:

STAFFING DECISION PROCESSES AND COX.D.F.

ISSUES Case Studies Of Seven U.S. Nuclear Power Plants.

I NUREG/CR-4674 V17. PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCOENTS: 1992 A STATUS REPORT.Mam Report And FRANCINI,R.

Appendix A.

NUREG/CR 4599 V03 N2: SHORT CRACKS IN PIPtNG AND PIPING NUREG/CR-4674 V18. PRECURSORS TO POTENTIAL SEVERE CORE WELDS Semiannual Report October 1992 - March 1993.

DAMAGE ACCIDENTS.1992 A ST ATUS REPORT. Appendices B, C, D, E F, And G.

FRESCO,A.

NUREG/CR-5812: MANAGING AGING IN NUCLEAR POWER NUR /C 6 4 V17. PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCOENTS: 1992 A STATUS REPORT.Mam Report And FRIESEL,M.A.

Appendu A-NUREG/CR-5963: CONTINUOUS AE CRACK MONITORING OF A dis-NUREG/CR-4674 V18. PRECURSORS TO POTENTIAL SEVERE CORE SIMtLAR METAL WELDMENT AT LIMERICK UNIT 1.

DAMAGE ACCIDENTS.1992 A STATUS REPORT.Appereces B, C, D, E F. And G.

GALYEAN,W.J.

NUREG/CR 8145 VERIFICATON AND VALIDATON OF THE SAPHIRE NUR 5963. CONTINUOUS AE CRACK MONITORING OF A DIS.

SIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

GARCIA,P.

NUREG 1486. FINAL SAFETY EVALUATON REPORT TO LICENSE DEHMEL,J C.

THE CONSTRUCTION AND OPERATION OF A FACILITY TO NUREG/CR4147 V01: CHARACTERtZATION OF CLASS A LOW LEVEL RECEIVE, STORE AND DISFOSE OF 11E(2) BYPRODUCT MATERIAL RADIOACTIVE WASTE 19861990 Executive Summary.

NEAR CLIVE. UTAH. Docket No. 40-8989 (Envvocare of Utah,Inc.)

NUREG/CR-6147 V02: CHARACTERl2ATION OF CLASS A LOW LEVEL RADOACTIVE WASTE 1986-1990 Mam Report Part A.

GHADIALI*N' NUREG/CR 6147 V03: CHARACTERl2ATION OF CLASS A LOW-LEVEL NUREG/CR-4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING RADIOACTIVE WASTE 1986-1990 Mam Report-Part B.

NUREG/CR 6147 YO4 CHARACTERIZATON OF CLASS A LOW-LEVEL WELDS Semiannual Report, October 1992. March 1993.

RADIOACTIVE W ASTE 1986-1990 Appendices A E.

NUREG/CR 6147 V05: CHARACTERIZATION OF CLASS A LOW-LEVEL GOLUB,0.R.

NUREG 1368: PREAPPLICATION SAFETY EVALUATION REPORT FOR RADIOACTIVE WASTE 1986-1990. Appendix F.

NUREG/CR-6147 V06. CHARACTERIZATION OF CLASS A LOW-LEVEL THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

RADOACTIVE WASTE 19861190 Appendices G-J LlOUO-METAL REACTOR Final Report NUREG/CR 6147 V07: CHARACTERl2ATON OF CLASS A LOW-LEVEL RAD 60 ACTIVE WASTE 19861990 Appendices K-P.

GORE,B.

NUREG/CR4122: STAFFING DECISION PROCESSES AND i

DE W ALL,K.G.

ISSUES Case Studies Of Seven U S. Nuclear Power Plants.

NUREG/CR-5935^

SUMMARY

OF WORK COMPLETED UNDER THE NUREG/CR-6123: AN INTERNATIONAL COMPARISON OF COMMER-ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUAllFICATION RE.

CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND SEARCH PROGRAM (EDO').

PRACTICE.1980-1990.

l l

Personal Author index 17 GORHAMED.

ISKANDER,S.K.

NUREG/CR-4551 V01 R1: EVALUATON OF SEVERE ACCIDENT NUREG/CR-6139: CRACK ARREST TESTS ON TWO IRRADIATED RISKS: METHODOLOGY FOR THE CONTAINMENT. SOURCE HIGH COPPER WELDS Phase 11: Results Of Duplex-Type Specimens.

TERM. CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

ISRAEL,S.

GOUDAEN.F.

NUREG 1022 RO1 DR FC: EVENT REPORTING GUIDELINES NUREG/CR-3145 VIO: GEOPHYSICAL INVESTIGATIONS OF THE 10CFR50 72 AND 50 73 Second Draft For Comment.

WESTERN OHIO-INDIANA REGION Final Report, October 1986-Sep-tember 1992.

JACKSON,K.

NUREG 1471: CONCEPT OF OPERATIONS WITH ORGANIZATON GROVE,E CHARTS.NRC inckjent Response.

NUREGICR 5812. MANAGING AGING IN NUCLEAR POWER PLANTS Inwghts From NRC Maintenance Team inspection Reports' JANSE N,J.M.

GUNTHER,W.

NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-5812 MANAGING AGING IN NUCLEAR POWER DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Main Report And PLANTS Inseghts From NRC Maintenance Team inspection Reports.

Appendix A.

NUREG/CR4674 V18: PRECURSORS TO POTENTIAL SEVERE CORE HAMDAN,L DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices 8. C, D.

NUFiEG 1486. FINAL SAFETY EVALUATION REPORT TO LICENSE E, F, And G.

THE CONSTRUCTION AND OPERATION OF A FACILITY TO RECEIVE. STORE AND DISPOSE OF 11E(2) DYPRODUCT MATERIAL JOHNSON,T.L NEAR CLIVE, UTAH Docket No. 40-8989 (Envrocare of Utah,Inc.)

NL9EG-1486: FINAL SAFETY EVALUATION REPORT TO LICENSE THE CONSTRUCTIC:4 AND OPERATION OF A FACILITY TO l

HANSON.D.J.

RECEIVE, STORE ANO DISPOSE OF 11E(2) BYPRODUCT MATERIAL I

NUREG/CH 6158 IMPLICATIONS FOR ACCIDENT MANAGEMENT OF NEAR CLIVE. UTAH Docket No. 40-8989 (Envrocare of Utah,Inc.)

ADDING WATER TO A DEGRADING REACTOR CORE.

JOHNSTON,A.C.

NUREG/CR4209.

MEMPHIS AREA REGIONAL SEISMIC NU Ed C 4551 V01 RI: EVALUATION OF SEVERE ACCIDENT NETWORK. Final Report October 1986 - September 1992.

RISKS METHODOLOGY FOR THE CONTAINMENT. SOURCE TERM. CONSEQUENCE, AND RISK IN1EORATION ANALYSES.

JOHNSTONJ.J.

NUREG/CR 5407: ASSESSMENT OF THE IMPACT OF DEGRADED HARPER,M R NUREG-1022 ROI DR FC: EVENT REPORTING GUIDELINES SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-10CFR50 72 AND 50 73 Second Draft For Comment.

MIC DESIGN LOADS.

HARRIS,R.V.

JONES,J.L NUHEG/CR-5985' EVALUATION OF COMPUTER.8ASED ULTRASONIC NUREG/CR-6145: VERIFICATION AND VAllDATION OF THE SAPHIRE INSERVICE INSPECTION SYSTEMS.

VERSION 4.0 PRA SOFTWARE PACKAGE.

HARTFIELD.R.A.

JONES,W.R.

NUREG-0020 V18 LICENSED OPERATING REACTORS STATUS SUM-NUREG 1022 R01 DR FC: EVENT REPORTING GUIDELINES MARY REPORT.Dota As Of December 31,1993 (Gray Book 1) 10CFR50.72 AND 50 73 Second Draft For Comment H ASKIN,F.E.

JOY,D.R.

NUREG/CR4042 PERSPECTIVES ON REACTOR SAFETY.

NUREG-0430 V13:

LICENSED FUEL FACILITY STATUS HAUTH.J.

REPORT. Inventory Difference Data. July 1,1992 June 30,1993.(Gray NUREG/CR-6122:

ST AFFING DECISION PROCESSES AND Book q ISSUES Case Studies Of Seven U S. Nuclear Power Plants.

KAM,F.B.

NUREG/CR-6123. AN INTERNATIONAL COMPARISON OF COMMER-CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND NUREG/CR 4816 R02: PR-EDO POWER REACTOR EMBRITTLEMENT PRACTICE.1980-1990~

DATA BASE. VERSION 2. Program Desenption.

NUREG/CR-6076: TR-EDB. TEST REACTOR EMBRITTLEMENT DATA HEASLER.P.G.

BASE.VER$10N 1.

NUREG/CR-5161 V02-EVALUATION OF SAMPLING PLANS FOR IN-SERVICE INSPECTION OF STEAM GENERATOR KAPLAN,M.

TUBES Comprehensive Analytical And Monte Carlo Simulation Results NUREG/CR 6147 V01: CHARACTER 12ATON OF CLASS A LOW LEVEL For Several Sampling Plans.

RADIOACTIVE WASTE 1986-1990. Executive Summary.

NUREGICR-6147 V02: CHARACTER 12ATION OF CLASS A LOW-LEVEL HELTONJ.C.

RADIOACTIVE WASTE 19861990. Main Report Part A.

NUREG/CR-4551 V01 Rt. EVALUATION OF SEVERE ACCIDENT NUREG/CR-6147 V03: CHARACTERl2ATION CF CLASS A LOW-LEVEL RISKS. METHODOLOGY FOR THE CONTAINMENT, SOURCE RADIOACTIVE WASTE 1986-1990 Main Report-Par 18.

TERM, CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

NUREG/CR-6147 V04. CHARACTERl2ATION OF CLASS A LOW LEVEL RADIOACTIVE WASTE 1986-1990. Appendices A-E.

HILLS.R.G.

NUREG/CR4147 V05: CHARACTER 12ATION OF CLASS A LOW-LEVEL NUREG/CR4063: INTRAVAL PHASE 11 MODEL TESTING AT THE LAS RADIOACTIVE WASTE 1986-1990. Appendix F.

CRUCES TRENCH SITE.

NUREG/CR-6147 V06: CHARACTER 12ATION OF CLASS A LOW-LEVEL RADIOACTIVE WASTE 19861190. Appendices G J.

NUR G 1471: CONCEPT OF OPERATIONS WITH ORGANIZATION RAD CT E WA T 1986 9 ces K P CHARTS NRC incuient Response KASTURI.S.

HORA.S.C NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCOENT NUREG/CR-5990. THE EFFECTS OF SOLAR GEOMAGNETICALLY IN-DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR RISKS. METHODOLOGY FOR THE CONTAINMENT. SOURCE POWER ST ATONS.

TERM,CONSEOUENCE, AND RISK INTEGRATION ANALYSES HUNT.P.

KE NNEALLY,R.M.

NUREG/CR 6122:

STAFFING DECISON PROCESSES AND NUREG-1368. PREAPPLICATON SAFETY EVALUATION REPORT FOR ISSUES Case Stud cs Of Seven U S Nuclear Power Plants THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

LIQUID METAL REACTOR Final Report.

NUREC/CR 5963 CONTINUOUS AE CRACK MONITORING OF A DIS.

KERR G.D.

SIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

NUREG/CR-5569 R01. HEALTH PHYSICS POSITIONS DATA BASE.

18 Personal Author Index CILINSKl,T, LORENZ,R.A.

NUREG/CR4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING NUREG/CR 6077: DATA

SUMMARY

REPORT FOR FISSION PRODUCT WELDS Semiannual Report, October 1992 March 1991 RELEASE TEST VI 6 MIM,H.J.

LOWRY,W.

NUREG/lA-0114. ASSESSMENT OF RELAPS/ MOD 3 WITH THE LOFT NUREG/CR-6103 PRIORITIZATION OF REACTOR CONTROL COMPO-L9-1/L3 3 EXPERIMENT SIMULATING AN ANTICIPATED TRANSIENT NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF WITH MULTIPLE FAILURES AGING.

K LAME RUS.E.W.

LU,P.Y.

NUREG/CR-5407. ASSESSMENT OF THE IMPACT OF DEGRADED NUREG/CR 5569 RO1: HEALTH PHYSICS POSITIONS DATA BASE.

SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-MIC DESIGN LOADS.

LUIS,S.

NUREG/CR-6063 INTRAVAL PHASE 11 MODEL TESTING AT THE LAS QMETYK L CRUCES TRENCH SITE.

NUREG/CR-6107:

SUMMARY

OF MELCOR 18 2 CALCULATIONS FOR THREE LOCA SEOUENCES (AG,S2D & S3D) AT THE SURRY PLANT.

M AC KINNON,J.D.

NUREG-1022 801 DR FC: EVENT REPORTING GUIDELINES NURE / R-6194. METALLOGRAPHIC AND HARDNESS EXAMiNA-TIONS OF TMI-2 LOWER PRESSURE VESSEL HEAD SAMPLES.

MARSCHALL,C, NUREG/CR-4599 V03 N2: SHORT CAACKS IN PIPING AND PIPING WELDS. Semiannual Report, October 1992 - March 1993.

N R G/CR-6196 CALCULATIONS TO ESTIMATE THE MARGIN TO FAILURE IN THE TMI-2 VESSEL.

MAURO J.

NUREG/CR 6147 V01: CHARACTERIZATION OF CLASS A LOW-LEVEL K RISHN ASW AM f,P.

RADIOACTIVE WASTE 1986-1990 Executwe Summary.

NUREG/CH-4599 V03 N2. SHORT CRACKS IN PIPING AND PIPING NUREG/CR-6147 V02-CHARACTERIZATION OF CLASS A LOW LEVEL WELDS Semiannual Report. October 1992 - March 1993.

RADIOAChVE WASTE 1986-1990,Mwn Report-Part A.

NUREG/CR-6147 V03: CHARACTERIZATION OF CLASS A LOW LEVEL KUAN,P.

RADIOACTIVE WASTE 1986-1990. Main Report Part B NUREG/CR-6158. IMPLICATIONS FOR ACCIDEN1 MANAGEMENT OF NUREG/CR-6147 V04: CHARACTERIZATION OF CLASS A LOW-LEVEL ADDING WATER TO A DEGRADING REAOTOR CORE.

RADIOACTIVE WASTE 1986-1990 Appendices A-E.

NUREG/CR-6147 V05 CHARACTERIZATION OF CLASS A LOW-LEVEL KUNKEL C' R-6169 RELAY TEST PROGRAM Senes 11 Tests integral Test.

NURE b/C NURE C V

H Z

"^ ^

^

P

' CLASS A LOW-LEVEL F

ing Of Relays And Circuit Dreakers RADIOACTIVE WASTE 1986-1190 Appendices G-J.

NUREG/CR-6147 V07: CMRACTERIZATION OF CLASS A LOW-LEVEL KURTZ,R.J RADIOACTIVE WASTE 19861990.Appendicer K-P.

NUREG/CR-5161 V02: EVALUATION OF SAMPLING PLANS FOR IN.

SE RVICE INSPECTION OF STEAM GENERATOR MCLAUGHLIN.D.

TUBES Comprehenswe Anaiytical And Monte Cado Simulation Results NUREG/CF.-6063. INTRAVAL PHASE 11 MODEL TESTING AT THE LAS For Several Sampling Plans CRUCES TRENCH SITE.

LAFORGE,R.

MCUMBER,L M NUREG/CR 3145 V10- GEOPHYSICAL INVESTIGATIONS OF THE NUREG/CR$133. FRAGMENTATION AND OUENCH BEHAVIOR OF WESTERN OHIO-INDIANA REGION Final Report, October 1986 Sep CORIUM MELT STREAMS IN WATER.

1 ember 1992.

MEDHEKAR,S.

LAU,W NUREG/CR 5960: STEAM EXPLOSIONS: FUNDAMENTALS AND EN-NUREG/CR-4674 V17 PRECURSORS TO POTENTIAL SEVERE CORE ERGETIC BEHAVIOR-DAMAGE ACCIDENTS 1992 A STATUS REPORT. Main Report And Appendix A-MEINHOLD,C.B NUREG/CR4674 V18. PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 112 DRF FC: IMPACT OF REDUCED DOSE LIMITS ON DAMAGE ACCIDENTS 1992 A STATUS REPORT Appendices B, C, D.

NRC LICENSED ACTIVITIES. Maior issues In The implementation Of E F, And G ICRP/NCRP Dose Limit Recommendatons Draft Report For Comment LEAHY,T J.

NUR /CR 88 S MARY OF 1991 1992 MISADMINISTRATION NUREE R-6122:

STAFFING DE CISION PROCESSES AND ISSUES Case studies of seven U.S. Puclear Power Plants.

NUREG/CR-6123: AN INTERNATIONAL "OMPARISON OF COMMER-LEVERT,F.E.

CIAL NUCLEAR POWER PLANT STAFi!NG REGULATIONS AND NUREG/CR4833: LARGE AREA SELF-POWERED GAMMA RAY PRACTICE.1980-1990.

DETECTOR. Phase 11 Development Of A Source Position Monitor For Use On industnal Radiographic Unrts MICH AUD.W.F.

LOOMIS.D.

NUREG/CR-6142: TENSILE PROPERTY CHARACTERIZATION OF NUREG/CR4147 VOI: CHARACTERIZAllON OF CLASS A LOW. LEVEL THERMALLY AGED CAST STAINLESS STEELS.

RADIOACTIVE WASTE 1986-1990 Executwe Summa.

NUF JG/CR 6147 V02. CHARACTERIZATION OF CLA S A LOW LEVEL MINARICK,J.W-NUREG/CR-4674 V17. PRECURSORS TO POTENTIAL SEVERE CORE RADIOACTIVE WASTE 19861990 Main Report-Part A.

NUREG/CR.6147 V03 CHARACTERIZATION OF CLASS A LOW-LEVEL DAMAGE ACCIDENTS-1992 A STATUS REPORT. Main Report And RADIOACTIVE WASTE 1986-1990 Main Report-Part B.

Appendex A.

NURE.G/CH 6147 V04 CHARACTEHl2ATION OF CLASS A LOW-LEVEL NUREG/CR-4674 Vt8 PRECURSORS TO POTENTIAL SEVERE CORE RADIOACTIVE WASTE 19841990 Appendices A.E.

DAMAGE ACCIDENTS.1992 A STATUS REPORTAppendices B, C, D, NUREG/CH4147 V05. CHARACTERIZATION OF CLASS A LOW-LEVEL E. F, And G RADIOACTIVE WASTE 1986-1990 Apper4x F.

NUREG/CR 6147 V06 CHARACTER 12ATION OF CLASS A LOW-L'iVEL MOHAN,R.

RADIOACTIVE WASTE 19861190. Appendices G4 NUREG/CR-4599 V03 N2: SHCRT CRACKS IN PIPING AND PIPING NUREG/CH-6147 V07: CHARACTERl2ATION OF CLASS A LOW LEVEL WELDS Semiannual Report October 1992 March 1993.

RADIOACTIVE WASTE 19841990 Appereces K-P.

MOORE,P.D.

LOPRESTI,F, NUREG-1308. PREAPPLICATION SAFETY EVALUATION REPORT FOR NUREG-1471. CONCEPT OF OPERATIONS WITH ORGANIZATION THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

CHARTS NRC incident Response.

LIOUlD-MET AL REACTOR. Final Report

Personal Author indsx 19 MORRIS,R.H.

ROSENFIELD A.

NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SFi/ERE CORE NUREG/CR 4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING DAMAGE ACCIDENTS: 1992 A STATUS REPORT Mon Report And WELDS Semiannual Report October 1992 March 1993.

A >crg1m A NU < G/CR-4674 Vf B PRECURSORS TO POTENTIA'. SEVERE CORE ROUSSEL,A.

DAMA'*E ACCIDENTS 1992 A S1 ATUS REPORT Appereces B, C, D, NUREG/CR-6122:

STAFFING DECISION PROCESSES AND E,F.And G.

ISSUES Case Studies Of Seven U S. Nuclear P)wer Plants.

MUHF M,W.B.

RUFF,L NURE G/CH-4551 V01 R1: EVALUATION N SEVERE ACCIDENT NUREG/CR 3145 VIO: GEOPHYSICAL INVESTIGATIONS OF THE RISKS METHODOLOGY FOR THE CONTAINMENT, SOURCE WESTERN OHIO INDIANA REGION Final Report, October 1986-Sep.

TERM. CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

tomber 1992.

HANSTAD.R.K, SALVER,W.D.

NUREGICH.6139. CRACK-ARREST 1ESTS ON TWO IRRADIATED NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE HIGH-COPPER WELDS Pnase 11: Fesults Of Duplex-Type Specwnens.

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Main Report And Appenda A NOVAK,5.D-NUREG/CR.4674 V18: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 6088 SUMMAR Y OF 1991 1992 MISADMINISTRATION DAMAGE ACCIDENTS.1992 A STATUS REPORT.Appendicos B, C, D, EVENT INVESTIGATIOM E' F' And G~

NUHEG/CR 6145-VERIFICATION AND VAUDATION OF THE SAPHIRE VE RSION 4 0 PRA SOFTWARE PACKAGE-SANDIN S.

NUREG-1022 ROI DR FC: EVENT REPOR TING GUlOEUNES NOWLEN)S 10CFR50.72 AND 50.73 Second Draft For Cornrnent.

NUREG CR 6103 PRIORlil2ATION OF REACTOR CONTROL COMPO-NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF SANDS,S.P.

AGING NUREG.1368 PREAPPLICATION SAFETY EVALUATION REPORT FOR THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

OSBORNE.M.F NUREGICR bO77 DATA

SUMMARY

REPORT FOR FISSION PRODUCT IJOUID. METAL REACTOR Final Report RELEASE TES1 VI-6 SCANLON.B.

NUREG/CR-6063. INTRAVAL PHASE 11 MODEL TESTING AT THE LAS OSTROM LT CRUCES TRENCH SITE.

NUREG/GR 6008 SUMMAR Y OF 1991-1992 MISADMINtSTRATION EVEN I INVESTIGATIONS SCHNEIDER.J.P.

NUREG/CR 6133 FRAGMENTATION AND OUENCH BEHAVIOR OF PAFF0FID,D.J.

NUREG/GR 6158 IMPLICATIONS FOR ACCIDENT MANAGEMENT OF CORIUM MELT STREAMS IN WATER.

ADDING WATER TO A DEGRADING REACTOR CORE.

SCHUETZ,B.K.

NUREG/CR-6198. TMI-2 INSTRUMENT NOZ2LE EXAMINATIONS PER-P AGE.G.

NUREG/CR 6156

SUMMARY

OF COMMENTS RECEIVED FROM FORMED AT THE INEL RASHOPS ON RADIOLOGICAL GRl1ERIA FOR DECOMMISSION' SCHUSTER,G.J.

NUREG/CR-5985: EVALUATION OF COMPUTER-DASED ULTRASONIC PARK WA INSERVICE INSPECTION SYSTEMS.

NUR[G/CR 5985 EVALUATION OF COMPUTER BASED ULTRASONIC INSUMCE INSPECTION SYSTEMS NU G/CR 4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING PITTIGLIO L WELDS Semiannual Report, October 1992. March 1993.

NUREG 1466. FINAL SAFETY EVALUATION REPORT TO LICENSE THE CONSTRUCTION AND OPERATION OF A FACiUTY TO SEU'M NUREG/CR 6138: USER'S GUIDE FOR SIMPLIFIED COMPUTER RECEIVE. STORE AND DISPOSE Of-11E(2) BYPRODUCT MATERIAL MODELS FOR THE ESilMATION OF LONG. TERM PERFORMANCE NEAR CUVE.UT AH Docket No. 40~8989.(Envwocare of Utah,Inc )

OF CEMENT BASED MATERIALS.

PLANSKY,LE.

NUREG/CH 6139 USER S GUIDE FOR SIMPUFIED COMPUTER SEUL,K.W.

MODELS FOR THE ESTIMAllON OF LONG-TERM PERFORMANCE NUREG/lA 0114. ASSESSMENT OF RELAP5/ MOD 3 WITH THE LOFT OF CEMENT-DASED MATERIALS.

L9-1/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRANSIENT WITH MULTIPLE FAILURES.

QUICK,K.S.

NUREG/CR 6158. IMPLICATIONS FOR ACCIDENT MANAGEMENT OF SHAH,V,N.

ADDING WATER 10 A DEGRADING REACTOH CORE.

NUREG/CR-5314 VOS: INSIGHTS FOR AGING MANAGEMENT OF MAJOR LWR COMPONENTS METAL CONTAINMENTS.

R AHJ AN S.

NURf G/CR-4599 V03 N2-SHORT CRACKS IN PIPING AND DiPING SHTEYNGART,S.

WELDS. Semiannual Report. October 1992 - March 1993 NUREGICR-6169. RELAY TEST PROGRAM.Senes 11 Tests integral Test-ing Of Relays And Crcuit Breakers.

R AO,M C.

NUREG/CR 6132 Bl. AXIAL LOADING AND SHALLOW-FLAW EFFECTS SINHA.U.P.

ON CRACK.TIP CONSTRAINT AND FRACTURE TOUGHNESS NUREG/CR.5314 VOS: INSIGHTS FOR AGING MANAGEMENT OF MAJOR LWR COMPONENTS METAL CONTAINMENTS.

RE MPE,J.L NUREG/CR 6196. CALCULATIONS TO ESTIMATE THE MARGIN TO SMITH,C.L F AILURE IN 1HE TMI 2 VESSEL NUREG/CR-6145: VERIFICAllON AND VAUDATION OF THE SAPHIRE VERSION 4.0 PRA SOFTWARE PACKAGE.

ROCKHOLD,M.

NUREG/CR4063. INTRAVAL PHASE 11 MODEL TESTING AT THE LAS SMITH,D.

CRUCES 1RLNCH S11E.

NUREG/CR G156:

SUMMARY

OF COMMENTS RECEIVED FROM WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION.

ROM.D.

ING NUREG 1486-FINAL SAFETY EVALUATION REPORT TO tlCENSE 1HE CONSTRUCilON AND OPERATION OF A F ACillTY TO SMITH L RECEIVE. STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NUREG/CR-6107.

SUMMARY

OF MELCOR 1.8.2 CALCULATIONS FOR NEAR CUVE, UTAH Docket No 40-8969 (Enytocare of Utah.Inc )

THREE LOCA SEOUENCES (AG,S2D & S3D) AT THE SURRY PLANT.

20 Personal Author Index SMITH.S K.

TOBEN,P.T.

NURE G/CR 5314 V05 INSIGHTS FOR AGING MANAGEMEN1 OF NUREG/CR 6142: TENSILE-PROPERTY CHARACTERl2ATION OF MAJOR LWR COMPONENTS METAL CONTAINMENTS THERMAL

• V AGED CAST STAINLESS STEELS.

SNOW,S 0.

TRAVIS,J.R.

NUHEG/CR-6196 CALCULATIONS TO ESTIMATE THE MARGIN TO NUREN('R-6077. DATA

SUMMARY

REPORT FOR FISSION PRODUCT FAILURE IN THE TMI-2 VESSEL.

RELEASE TEST VI-6 SOPPE T,W.K-TRUSTY,A.D.

NUREG/CD 6142. TENSILE-PROPERT Y CHARACTERIZATION OF NUREG/CR-6145: VERIFICATION AND VALIDATION OF THE SAPHIRE THERMALLY AGED CAST STAINLESS STEELS.

VERSION 4.0 PRA SOFTWARE PACKAGE.

NU E CR 133. I'1AGMENTATION AND OUENCH BEHAVIOR OF NUREG CR 4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE conlUM MELT STREAMS IN WATER DAMAGE ACCIDENTS: 1992 A STATUS REPORT Mem Report And Appendix A.

ST AFFORD.R.S.

NUREG/CR-4674 V18 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-5569 ROI: HEALTH PHYSICS POSITIONS DATA BASE.

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices B, C, D.

STALLMANN.F.W.

E.F.And G.

NURE G/CR-4816 R02-PR EDB. POWER REACTOR EMBRITTLEMENT VANHORN R.L DAT A BASE,VE RSION 2. Program Descnption.

NURE G/CR.6076 TR.EDB TEST REACTOR EMBRITTLEMENT DATA NUREG/CR 6145. VERIFICATION AND VALIDATION OF THE SAPHIRE B ASE, VERSION 1.

VERSION 4 0 PRA SOFTWARE PACKAGE.

STEELE.R.

VIRGIL,R.

NUREG/CR 5935

SUMMARY

OF WORK COMPLETED UNDER THE NUREG/CR-6103. PRIORITIZATION OF REACTOR CONTROL COMPO-ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUAllRCATION RE.

NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF SEARCH PROGRAM (EDOP).

AGING.

STICKLER,LA.

WAGNER,T.

NUREG/CR 6196-CALCULAllONS TO ESTIMATE THE MARGIN TO NUREG/CR-3145 V10: GEOPHYSICAL INVESTIGATIONS OF THE F AILURE IN THE TMI 2 VESSEL.

WESTERN OHIO-INDIANA REGION Fmal Report October 1986-Sep-tember 1992.

STRUCK ME YE R,R.

NUREG-On17 V13 N04. NRC TLD DIRECT RADIATION MONITORING WANG J.A.

NETWORK. Progress Report. October-December 1993-NUREG/CR-4816 R02: PR-EDB: POWER REACTOR EMBRITTLEMENT DAT A BASE, VERSION 2. Program Descreon.

SUBUDHI,M.

NUREG/CR-6076. TR EDB. TEST REACTOR EMBRITTLEMENT DATA NUREG/CR-5812: MANAGING AGING IN NUCLEAR POWER BASE VERSION 1.

PLANTS Inschts From NRC Mantenance Team Inspect on Repor1s NUREG/C4 5990 THE EFFECTS OF SOLAR-GEOMAGNETICALLY IN-W A NG,K.

DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NUREG/CR-6133 FRAGMENTATION AND OUENCH BEHAVIOR OF POWER STATIONS.

CORIUM MELT STAEAMS IN WATER.

TAYLOR,B.J.

NUR G 1 86: FINAL SAFETY EVALUATION REPORT TO LICENSE O TAEA E ER ION 2 ogra D THE CONST RUCTION AND OPERATION OF A FACILITY TO TAYLOR,J.

RECEIVE. STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NUREG/CR 5012: MANAGING AGING IN NUCLEAR POWER NEAR CLIVE, UTAH. Docket No. 40-8981(Envirocare of Utah,Inc.)

PLANTS Insghts From NRC Maintenance Team inspecten Reports.

TAYLOR.T.T.

NUREG/CR-5935:

SUMMARY

OF WORK COMPLETED UNDER THE NUREG/CR 5985: EVALUATION OF COMPUTER. BASED ULTRASONIC ENVIRONMENTAL AND DYNAMIC EOUIPMENT OUAllFICATION RE.

INSLRVICE INSPECTION SYSTEMS.

SEARCH PROGRAM (EDOP).

TERRILL,E..

AND NUREG 1486 FINAL SAFETY EVALUATION REPORT TO LICENSE WEBER.M.

NUREG/CR-6122:

STAFFING DECISION PROCESSES ISSUE S Case Studies Of Seven U S Nuclear Power Plants-THE CONSTRUCTION AND OPERATION OF A FACILITY TO NUREG/CR4123: AN INTERNATIONAL COMPARISON OF COMMER-RECElVE. STORE AND DISPOSE OF itE(2) BYPRODUCT MATERIAL CIAL NUCLEAR POWER PLANT STAFFING REGULARONS AND NEAR CLIVE. UTAH Docket No. 40-8989.(Envirocare of Utah.inc )

PRACTICE 1960-1990 WEBSTER,C.S.

E CR-6132: BIAX1AL LOADING AND SHALLOW. FLAW EFFECTS R

SE ES ON CRACK-TIO CONSTRAINT AND FRACTURE TOUGHNESS.

WWEL,B.A.

THEOF ANOUS T.G.

RW368. PREAPPLICATION SAFETY EVALUATION REPORT FOR NUREG/CR 5960: STEAM EXPLOSIONS FUNDAMENTALS AND EN-THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

GERGETIC BEHAVIOR' LIOUID-METAL REACTOR Final Report.

THINNES,GL NUREG/GR 6196 CALCULATIONS TO ESTIMATE THE MARGIN TO WlBLIN,C.

NUREG/CR 6156:

SUMMARY

OF COMMENTS RECEIVED FROM F AILURE IN THE TMI-2 VESSEL.'

WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-THORSON,R.

ING.

NUREG/CR-3145 V10: GEOPHYSICAL INVESTIGATIONS OF THE WESTERN OHIOINDIANA REGION F)nal Report. October 1986-Sep.

WlERENGA,P.J.

tember 1992.

NUREG/CH-6063 INTRAVAL PHASE 11 MODEL TESTING AT THE LAS CRUCES TRENCH SITE.

THRCM,LD.

NUREG-1368. PREAPPLICATION SAFETY EVALUATION REPORT FOR WILKOWSKl,0.M.

THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

NUREG/OR.4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING LIOUID METAL REACTOR Final Report.

WELDS Semiannual Report, October 1992. March 1993

=

Personal Author index 21 WITY,RJ, XIANO,J.

NUREG/CR-6196: CALCULATIONS TO ESTIMATE THE MARGIN TO NUREG/CR 6063 INTRAVAL PHASE il MODEL TESTING AT THE LAS FAILURE IN THE TMI-2 VESSEL CRUCES TRENCH SITE, WITTWEYER,0.

YUEN,W.W.

NUREG/CR-6063 INTRAVAL PHASE il MODEL TESilNG AT THE LAS NUREG/CR4960: STEAM EXPLOSIONS: FUNDAMENTALS AND EN-CRUCES TRENCH SITE, GERGETIC BEHAVIOR.

WOtf RAM,LM.

ZElGLER.S.L NUREG/CR4145: VERIFICATION AND VALIDATION OF THE SAPHIRE NUREG/CR4145: Ventr' CATION AND VALIDATION OF THE SAPHIRE VERSION 4.0 PRA SOFTWAPE PACKAGE VERSION 4 0 PRA SOFTWARE PACKAGE.

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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.

A533 Grade B Class 1 Steel Crustal Structure NUREG/CR 6132; BIAXlAL LOADING AND SHALOW-FLAW EFFECTS NUREG/CR-3145 V10: GEOPHYSICAL INVESTIGATIONS OF THE ON CRACK TlP CONSTRAINT AND FRACTURE TOUGHNESS WESTERN OHO-INDIANA REGION Final Report, October 1986-Sep-Acc6 dent Management NUREG/CP-0127: PROCEEDINGS OF THE CSNI SPECIALISTS MEET-Data Base NUREGICR-4o16 R02: PR-EDB POWER REACTOR EMBRITTLEMENT NL

/

I O

FOR A IDENT MANAGEMENT OF DATA BASE,VERSON 2. Program Desenption.

ADDING WATER TO A DEGRADING REACTOR CORE.

Data Transmission System Occ6 dent Sequence NUREG/CR4149 APPLICATIONS OF FIBER OPTICS IN PHYSICAL NUREG/CR-4674 V17; PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS.1992 A STATUS REPORT Main Report And PROTECTION NU R 4674 V18: PRECURSORS TO POTENTIAL SEVERE CORE Decommissioning DAMAGE ACCIDENTS.1992 A STATUS REPORT. Appendices B, C. O, NUREG/CR-6156.

SUMMARY

OF COMMENTS RECEIVED FROM WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-E, F, And G ING.

Acoustic Emlesion NUREG/CR 5963. CONTINUOUS AE CRACK MONITOR!NG OF A DIS-Degraded Core SIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

NUREG/CR-6158 IMPLICATIONS FOR ACCIDENT MANAGEMENT OF ADDING WATER TO A DEGRADING REACTOR CORE.

NUREG/CR4314 V05: INSIGHTS FOR AGING MANAGEMENT OF Dissir M1ar Metal Weldment NiiREG/CR-5963: CONTINUOUS AE CRACK MONITORING OF A DIF NL HE /

1 NA G AGI IN NU EAR POWER blMILAR METAL WELDMENT AT LIMERICK UNIT 1.

Pt ANTS Insights From NRC Masntenance Team inspecton Reports NUREG/CR 6103 PRIORITIZATION OF REACTOR UUNTROL COMPO-Dy NTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF NU GC 3

SUMMARY

OF WORK COMPLETED UNDER THE ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUALIFICATON RE.

SEARCH PROGRAM (EDOP)

Alleger NUREG 1499 REASSESSMENT OF THE NRC'S PROGRAM FOR PRO-TECTING ALLEGERS AGAINST RETAllATION Earthquake NUREG/GR-0008: VAllOATON OF SEISMIC PROBABILISTIC RISK AS-Anticipated Trenelent SESSMENTS OF NUCLEAR POWER PLANTS-NUREG/lA-0114: ASSESSMENT OF RELAP5/ MOD 3 WITH THE LOFT L91/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRANSIENT Electrical Component WITH MULTIPLE FAILURES.

NUREG/CR4103: PRIORIT12ATON OF REACTOR CONTROL COMPO.

NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEOVENCE OF Blaulat Loading AGING' NUREGICR 6132 BIAXIAL LOADING AND SHALLOW-FLAW EFFECTS ON CHACK TIP CONSTRAINT AND FRACTURE TOUGHNESS-Electrical System NUREG/CR 5990: THE EFFECTS OF SOLAR-GEOMAGNETICALLY IN-Budge DUCEO CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NUREG-1100 V10: BUDGET ESTIMATES Fiscal Year 1995 POWER STATONS.

Cast Stainlese Steel NUREG/CR4142. TENSILE. PROPERTY CHARACTERIZATON OF Electromagnetic Radiation THERMALLY AGED CAST STAINLESS STEELS.

NUREG/CR-5990 THE EFFECTS OF SOLAR GEOMAGNETICALLY IN-DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR Circuit Breaker POWER STATONS.

NUREG/CR416A RELAY TEST PROGRAM Senes il Tests. integral Test.

Ing Of Relays And Cercuit Breakers-Embrittlement NUREG/CR4816 R02; PR-EDB: POWER REACTOR EMBRITTLEMENT Concrete Barrier NUREG/CR4576: TR EDd: Program Desenption. TEST REACTOR EMB DATA BASE VERSION 2 NUREG/CR-6138 USER'S GUIDE FOR $1MPLIFIED COMPUTER MODELS FOR THE ESTIMATION OF LONG TERM PERFORMANCE BASE' VERSION 1.

OF CEMENT-BASED MATERIALS Enforcement Action NUREG.0940 V12 NO3' ENFORCEMENT ACTIONS: SIGNIFICANT AC-REG /CR 6133. FRAGMENTATON AND QUENCH DEHAVIOR OF TONS RESOLVED Ouarterly Progress Report Juty-September 1993.

CORIUM MELT STREAMS IN WATER-NUREG-0940 V12 NO4: ENFORCEMENT ACTONS: SIGNIFICANT AC-TIONS RESOLVED.Ouarterty Progress Report,0ctoberoecomber Crack NUREG/CR4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING 1993.

WELDS. Semiannual Report, October 1992. March 1993.

Crack Arrest NUREG/C45935:

SUMMARY

OF WORK COMPLETED UNDER THE NUREG/CR4139 CRACK-ARREST TESTS ON TWO IRRADIATED ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUALIFICATON RE-HIGH. COPPER WELDS Phase 11: Results Of Duplex Type Spacemens.

SEARCH PROGRAM (EDOP).

23

24 Subj3ct indsx Event Reporting Guideline TUBES Comprehensive Analytical And Monte Carlo Simulation Results NUREG 1022 RO1 DR FC: EVLNT REPORTING GUIDELINES For Several Sampling Plans 10CFR50 72 AND 50 73 Second Uraft For Comrnent.

NUREG/CR 5965: EVALUATON OF COMPUTER-BASED ULTRASONIC INSERVICE INSPECTION SYSTEMS.

Fiber Optic NUREG/CR-6149 APPLICAlONS OF FIBER OPTICS IN PHYSICAL inspection Repo,1 PROTECTION.

NUREG/CR-5812; MANAGING AGING IN NUCLEAR POWER Final Safety Evaluation Report NUREG-1486: FINAL SAFETY EVALUATON REPORT TO LICENSE instrument Nozzle THE CONSTRUCTON AND OPERATION OF A FACILITY TO NUREG/CR--6198. TMI 2 INSTRUMENT NOZZLE EXAMINATIONS PER-RECElVE.STORF AND DISPOSE OF itE(2) BYPRODUCT MATERIAL FORMED AT THE INEL NEAR CLIVE. UTAH Docket No. 40-8989 (Envrocare of Utah,Inc.)

Intergranular Stress Corrosion Cracking Fire Damage NUREG/CR-5314 V05: INSIGHTS FOR AGING MANAGEMENT OF NUREG/CR 6103. PRIORITIZATION OF REACTOR CONTROL COMPO-MAJOR LWR COMPONENTS METAL CONTAINMENTS.

NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF AGING.

Investigation NUREG/CR-6088:

SUMMARY

OF 1991-1992 MISADMINISTRATON Fiscal Year EVENT INVESilGATONS.

NUREG-1100 V10 BUDGET ESTIMATES Fmcal Year 1995.

Irradiated H6gh-Copper Weld Fiselon Product NUREG/CR-6139: CRACK ARREST TESTS ON TWO IRRADIATED NUREG/CR-6077. DATA

SUMMARY

REPORT FOR FISSION PRODUCT hiGH-COPPER WELDS Phase 11: Results Of Duplex Type Spectnens.

RELEASE TEST VI-6.

LOCA Fracture Mechanics NUREG/CR-6107:

SUMMARY

OF MELCOR 18.2 CALCULATIONS FOR NUREG/CH-4599 V03 N2; SHORT CRACKS IN PIPING AND PIPING THREE LOCA SEQUENCES (AG.S2D & S3D) AT THE SURRY PLANT.

WELDS Semaanrual Report, October 1992 March 1993.

LWR Fracture Toughness NUREG/CR-5314 V05: INSIGHTS FOR AGING MANAGEMENT OF NUREG/CR 6132-BIAX1AL LOADING AND SHALLOW-FLAW EFF.ECTS MAJOR LWR COMPONENTS METAL CONTAINMENTS' ON CRACK TIP CONSTRAINT AND FRACTURE TOUGHNESS.

NUREG/CR 6139: CRACK-ARREST TESTS ON TWO IRRADIATED Las Cruces Trench HIGH COPPER WELDS. Phase 11 Results Of Duplex Type Spectnens.

NUREG/CR-6063: INTRAVAL PHASE il MODEL TESTING AT THE LAS CRUCES TRENCH SITE.

Fragmentation NUREG/CR-6133 FRAGMENTATION AND OUENCH BEHAVIOR OF CORIUM MELT STREAMS IN WATER.

g 4 V38 101: INDEXES TO NUCLEAR REGULATORY COM-Fuel Damag, MISSION ISSUANCES July-September 1993.

NUREG-0750 V38 NOS: NUULEAR REGULATORY COMMISSION IS-NUREG/CR 6077. DATA

SUMMARY

REPORT FOR FISSION PRODUCT RE~ LEASE TEST VI6 SUANCES FOR NOVEMBER 1993. Pages 187 288.

NUREG-0750 V38 N06: NUCLEAR REGULATORY COMMISSON IS-Fuel Coolant interaction SUANCES FOR DECEMBER 1993. Pages 289-391.

NUREG/CP 0127: PROCEEDINGS OF THE CSNI SPECIALISTS MEET-Licensed Fuel Facility Status Report ING ON FUEL-COOLANT INTERACTONS.

NUREG-0430 V13:

LICENSED FUEL FACILITY STATUS Gamma Ray Detector REPORT. inventory Difference Data. July 1,1992 - June 30,1993 (Gray NUREG/CR4833: LARGE AREA SELF-POWERED GAMMA RAY Book I!)

DETECTOR. Phase 11 Development Of A Source Position Monitor For Licensed Operating Reactors Use On Industnal Radiographic Units' NUREGo020 V18: LICENSED OPERATING REACTORS STATUS SUM-Geomagnetic Radiation MARY REPORT. Data As Of December 31,1993.(Gray Book 1)

NUREG/CR-6990. THE EFFECTS OF SOLAR GEOMAGNETICALLY IN-Uc ED ARENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NU GC 467 7: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS.1992 A STATUS REPORT. Main Report And Geophysical investigation Appendix A.

hdREQ/CR 3145 V10 GEOPHYSICAL INVESTIGATONS Of' THE NUREG/CR-4674 V18: PRECURSORS TO POTENTIAL SEVERE CORE WESTERN OHIO-INDIANA REGION F6nal Report, October 1986-Sep_

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices B, C, D, tember 1992 E, F, And G.

Health Phys 6c Light Water Reactor NUREG/CR-55ti9 ROI: HEALTH PHYSICS POSITIONS DATA BASE.

NUREG/CR-5314 VOS: INSIGHTS FOR AGING MANAGEMENT OF MAJOR LWR COMPONENTS METAL CONTAINMENTS.

ICAP Program NUREG/lA.0114 ASSESSMENT OF RELAPS/ MOD 3 WITH THE LOFT Liquld-Metal Reactor L9-1/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRANSIENT NUREG-1368: PREAPPLICATION SAFETY EVALUATION REPORT FOR WITH MULTIPLE FAILURES.

THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

LIQUID METAL REACTOR Final Report.

INTRAVAL NUREG/CR4063 INTRAVAL PHASE 11 MODEL TESTING AT THE LAS LonD-Term Performance CRUCES TRENCH SITE NUREG/CR-6138. USER'S GUIDE FOR SIMPLIFIED COMPUTER MODELS FOR THE ESilMATION OF LONG. TERM PERFORMANCE IRRAS OF CEMENT BASED MATERIALS.

NUREG/CR 6145. VERIFICATION AND VALIDATON OF THE SAPHIRE VERSION 4 0 PRA SOFTWARE PACKAGE.

Low-Level Rad 6oactive Waste NUREG/CR-6147 V01: CHARACTERIZATION OF CLASS A LOW LEVEL l

Inc6 dent Response RADCACTIVE WASTE 19861990 Executive Summary.

NURE G-14 71. CONCEPT OF OPERATIONS WITH ORGANIZATION NUREG/CA-6147 V02. CHARACTERIZATION OF CLASS A LOW-LEVEL CHARTS NRC inc dent Response RADIOACTIVE WASTE 1986-1990 Main Report-Part A.

NUREG/CfL6147 YO3. CHARACTERl2ATION OF CLASS A LOW LEVEL inserv6ce Inspection RADIOACTIVE WASTE 1986-1990. Main Report-Part B.

- NUREGICR-5161 V02: EVALUATON OF SAMPLING PLANS FOR IN-

. NUREG/CR4147 V04: CHARACTERIZATION OF CLASS A LOW-LEVEL SERVICE INSPECTON OF STEAM GENERATOR RADIOACTIVE WASTE 1986-1990 Appendices A E.

_ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

a Subject Index 25 l

NUREG/CR6147 VOS. CHARACTERIZATION OF CLASS A LOW-LEVEL Petitions For Rulemaklng RADIOACTIVE W ASTE 19861990 Appendix F.

NUREG 0936 V12 N04: NRC REGULATORY AGENDA Ouarterly NUREG/CR-6147 V06: CHARACTERl2ATION OF CLASS A LOW-LEVEL Report, October-December 1993.

RADIOACTIVE WASTE 1986-1190 Appendices G4 NUREG/CR6147 V07. CHARACTERIZATION OF CLASS A LOW LEVEL Physical Protect 6on RADIOACTIVE WASTE 19861990, Appendices k P.

NUREG/CR 6149. APPLICATIONS OF FIBER OPTICS IN FHYSICAL l

Lower Pressure Vessel Head NUREGICR-6194. METALLOGRAPHIC AND HARDNESS EXAMINA-Pipe TIONS OF TMi-2 LOWER PRESSURE VESSEL HEAD SAMPLES NUREG/CR-4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING WELDS Semiannual Report, October 1992 March 1993.

NUREG/CR-6107.

SUMMARY

OF MELCOR 1 P 2 CALCULATIONS FOR Piping THREE LOCA SEQUENCES (AG.S2D & S3D) AT THE SURRY PLANT.

NUREG/CR 5935:

SUMMARY

OF WORK COMPLETED UNDER THE ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUALIFICATION RE-C0aintenance Program SEARCH PROGRAM (EDOP).

NUREG/CR-5812: MANAGING AGING IN NUCLEAR POWER PLANTS Insights From NRC Maintenar'ce Team inspecton Reports Plant Organization NUREG/CR4122.

STAFFING DECISION PROCESSES AND Metallography ISSUES. Case Studies Of Seven U S Nuclear Power Plants NUREG/CR-6194 METALLOGRAPHIC AND HARDNESS EXAMINA-T)ONS OF TMI-2 LOWER PRESSURE VESSEL HEAD SAMPLES Power Reactor

[

NUREG/CR-4816 R02: PR-EDO: POWER REACTOR EMBRITTLEMENT f

M6sadmmistration Event DATA BASE, VERSION 2. Program Desenptort NUREG/CR 608&

SUMMARY

OF 1991-1992 MISADMINISTRAT ON Preapplication Safety Evaluation Report EVENT INVESTIGATIONS NUREG-1368: PREAPPUCATION SAFETY EVALUATION REPORT FOR Motten Core THE POWER REACTOR INNOVATIVE SMALL MODULE (PnlSM)

NUREGICR 6133 FRAGMENTATION AND OVENCH BEHnVIOR OF LIOUID-METAL REACTOR Final Report.

COR!UM MELT STRE AMS IN WATER.

Probabilistic Risk Assessment Muttiptant Action issue NUREG/CR-4551 V01 Rt: EVALUATION OF SEVERE ACCIDENT NUREG-1435 S03. STATUS OF SAFETY ISSUES AT LICENSED RISKS: METHODOLOGY FOR THE CONTAINMENT, SOURCE POWER PLANTS TMi Acton Plan Requirements Unresolved Safety TERM. CONSEQUENCE, AND RISK INTEGRATION ANALYSES NUREG/CR-5407. ASSESSMENT OF THE IMPACT OF DEGRADED Issues Genenc Safety issues Othor Multiplant Action issues.

SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-NRC's Program mig DESIGN LOADS.

NUREG-1499 REASSESSMENT OF THE NRC'S PROGRAM FOR PRO-NUREG/CR-6145: VERIFICATION AND VAllDATION OF THE SAPHIRE TECTING ALLEGERS AGAINST RETALIATION.

VERSION 4.0 PRA SOFTWARE PACKAGE.

NUREG/GR4008. VALIDATION OF SEISMIC PROBABILISTIC R!SK AS-Neutron Fluence SESSMENTS OF NUCLEAR POWER PLANTS.

NUREGICR 6139 CRACK-ARREST TESTS ON TWO IRRADIATED HIGH COPPER WELDS Phase li. Results Of Duplex-Type Specimens HELAPS/ MOD 3 NUREG/lA-0114. ASSESSMENT OF RELAPS/ MOD 3 WITH THE LOFT Nondestructive Evaluation L91/L3-3 EXPERIMENT S!MULATING AN ANTICIPATED TRANSIENT NUREG/CR-5985 EVALUATION OF COMPUTER-BASED ULTRASONIC WITH MULTIPLE FAILURES.

INSERVICE INSPECTION SYSTEMS.

Radiation Monitoring Nondestructive Testing NUREG/CR 6112 DRF FC. IMPACT OF REDUCED DOSE LIMITS ON NUREG/CR 5963 CONTINUOUS AE CRACK MONITORING OF A DIS-NRC LICENSED ACTIVITIES. Major Issues in The implementaton Of SIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

ICAP/NCRP Dose Limit Recommendttions. Draft Report For Comment.

Nuclear Power Plant Radiation Protection NUREG/GR 0008 VALIDATION OF SEISMIC PROBABillSTIC RISK AS-NUREG/CR-5569 RO1: HEALTH PHYSICS POSITIONS DATA BASE.

SESSMENTS OF NUCLEAR POWER PLANTS Radiation Therapy Occupational Esposure NUREG/CR-6088

SUMMARY

OF 1901 1992 MISADMINISTRATION NUREG/CR.6112 DRF FC: IMPACT OF REDUCED DOSE LIMITS ON EVENT INVESTIGATIONS.

NRC LICENSED ACTIVITIES Major lasues in The implementation Of ICRP/NCRP Dose Urrut Recommendations Draft Report For Comment Radiographic NUREG/CR 4833: LARGE AREA SELF-POWERED GAMMA RAY Operational Event DETECTOR, Phase il Development Of A Source Pos# tion Monitor For NUREG/CR-4674 VIT: PRECURSORS TO POTENTIAL SEVERE CORE Use On industnal Radiographic Uruts.

DAMAGE ACCIDENTS.1992 A STATUS REPORT Main Report And Appendiu A.

Radiolog6 cal Criterta NUREG/CR-4874 V18. PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 6156.

SUMMARY

OF COMMENTS RECElVED FROM DAMAGE ACCIDENTS.1992 A STATUS REPORT. Appendices B. C, D, WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-i E, F, And G ING Orgentration Chart Rad 6onuclide NUREG-1471: CONCEPT OF OPERATIONS WITH ORGANt2ATION NUREG/CR-6063: INTRAVAL PHASE 11 MODEL TESTING AT THE LAS CHARTS NRC incx1ent Response CRUCES TRENCH SITE-PRISM Reactor Component NUREG 1368 PREAPPLICATION SAFETY EVALUATION REPORT FOR NUREG/CR-5812. MANAGING AGING IN NUCLEAR POWER l

THE POWER REACTOR INNOVATIVE SMALL MODULE (PRISM)

PLANTS Insights From NRC Maintenance Team inspection Reports.

LIQUID MET AL RE ACTOR Final Report.

Reactor Control NUREG/CR4103: PRIORITIZATION OF REACTOR CONTROL COMPO-Performance History NUREG 1214 R13 HISTORICAL DAT A

SUMMARY

OF THE SYSTEMA 1 NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF IC ASSESSMENT OF LICENSEE PERFORMANCE.

AGING Performance Testing Reactor Maternal interaction NUREG/CR-6169 RELAY TEST PROGRAM Senes ll Tests Integral Test-NUREG/CR-6198 TMI-2 tNSTRUMENT NO2ZLE EXAMINATIONS PER-l Ing Of Relays And Circuit Breakers-FORMED AT THE INEL.

I

26 Subject index Reactor Operator Severe Accident NUHEG/CR-6122:

ST AF FING DECISION PROCESSES AND NUREG/CR 4551 V01 RI. EVALUATION OF SEVERE ACCIDENT ISSUE S Case Studios Of Seven U S Nuclear Power Plants RISKS: METHODOLOGY FOR THE CONTAINMENT, SOURCE NUREG/CR4123. AN INTERNATlONAL COMPARISON OF COMMER-TERM. CONSEQUENCE. AND RISK INTEGRATION ANALYSES.

i CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND NUREG/CR4107:

SUMMARY

OF MELCOR 1.8.2 CALCULATIONS FOR PRACTICE 1980 1990.

THREE LOCA SEQUENCES (AG.S2D & S3D) AT THE SURRY PLANT, NUREG/CR-6158: IMPLICATIONS FOR ACCIDENT MANAGEMENT OF

^

^

^

fun G/ 4551 V01 R1-EVALUATION OF SEVERE ACCfDENT RISKS-METHODOLOGY FOR THE CONTAINMENT. SOURCE Severe Core Damage TERM, CONSEQUENCE, AND RISK INTEGRATION ANALYSES-NUREG/CR-4874 V17: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-6042 PERSPECTIVES ON REACTOR SAFETY, DAMAGE ACCIDENTS.1992 A STATUS REPORT. Main Report And Reduced Dose Limit Appendix A.

NUREG/CR6112 DRF FC. IMPACT OF REDUCED DOSE LIMITS ON NUREG/CH 4674 VIB PRECURSORS TO POTENTIAL SEVERE CORE NRC LICENSFD ACTIVITIES Maior issues in The implementaten Of DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices 8, C, D, ICRP/NCRP Dose Limet Recommendations Draft Report For Comment.

E, F. And G.

Regional Stress Shear Wall NUREG/CR 4209-MEMPHIS AREA REGIONAL SEISMIC NUREG/CR-5407: ASSESSMENT OF THE IMPACT OF DEGRADED NETWORK Final Report. October 1986 September 1992 SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-MIC DESIGN LOADS.

Regulatory Agenda NUREG 0936 V12 N04: NRC REGULATORY AGENDA.Ouarterly Shift Composition Report, October December 1993 NUREG/CR 6122; STAFFING DECISION PROCESSES AND ISSUES Case Studies Of Seven U S. Nuclear Power Plants.

Relay NUREG/CR-6123. AN INTERNATIONAL COMPARISON OF COMMER-NUREG/CR-6169. RELAY TEST PROGRAM Sones 11 Tests integra! Test-CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND ing Of Relays And Circuit Breakers.

PRACTICE.1980-1990.

RetanaHon Shock Wave NUREG-1499-REASSESSMENT OF THE NRC'S PROGRAM FOR PRO.

NUREG/CR 5960: STEAM EXPLOSIONS FUNDAMENTALS AND EN-TECTING ALLEGERS AGAINST RETAllATION GERGETIC BEHAVIOR Risk Assessment NUREG/CR4112 DRF FC. IMPACT OF REDUCED DOSE LIMITS ON N REG /

833 LARGE AREA SELF-POWERED GAMMA RAY NRC LICENSED ACTIVITIES Major issues in The implementation Of ICRP/NCRP Dose Limit Recommendations Draft 1eport For Comment.

DETECTOR Phase il Development Of A Source Positen Monitor For Use On Industnal Radiographic Units.

Rutee NUREG O936 V12 N04 NRC REGULATORY AGENDA Ouarterty Staffing Report. October December 1993.

NUREG/CR-6122:

STAFFING DECISION PROCESSES AND ISSUES Case Studies Of Seven U S. Nuclear Power Plants.

SAPH!RE Version 4 NUREG/CR4145. VERIFICATION AND VALIDATION OF THE SAPHIRE Staffing Regulation VE RSION 4 0 PRA SOFTWARE PACKAGE.

NUREG/CR-6123. AN INTERNATIONAL COMPARISON OF COMMER-CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND Safety Evaluation Report PRACTICE.19801990.

NUREG-1491: SAFETY EVALUATION REPORT FOR THE CLAIBORNE ENRICHMENT CENTER. HOMER. LOUISIANA Docket No. 70 3070 Lou-Steam Esplosion r$iana Energy SerwcesLP NUREG/CP-0127; PROCEEDINGS OF THE CSNI SPECIALISTS MEET-ING ON FUEL COOLANT INTERACTIONS.

Safety lasu*

NUREG/CR 5960; STEAM EXPLOSIONS: FUNDAMENTALS AND EN-NUREG 1435 S03 STATUS OF SAFETY ISSUES AT LICENSED GERGETIC BEHAVIOR.

POWER PLANTS.TMl Acton Plan RequirementsUnresolved Safety issues Genenc Safety laaues Other Multiplant Action issues-Steam Generator Tube NUREG/CR-5161 V02: EVALUATION OF SAMPLING PLANS FOR IN-Sampnn0 Pisn SERVICE INSPECTION OF STEAM GENERATOR NUREG/CR-5161 V02; EVALUATION OF SAMPLING Pt.ANS FOR IN' TUDES Comprehensive Analytical And Monte Carlo Simulation Results SERVICE INSPECTION OF STEAM GENERATOR For Several Samphng Plans.

TUBES Comprehensive Analytical And Monte Carto Simulaton Results For Several Samphng Plana-Systematic Assessment Of Licensee Performance NUREG-1214 R13-HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

IC ASSESSMENT OF LICENSEE PERFORMANCE I

U EG C 407 ASSESSMENT OF THE IMPACT OF DEGRADED l

SHEAR WALL STif FNESSES ON SEISMIC PLANT RISK AND SEIS-TLD l

MIC DESIGN LOADS-NUREG-0837 V13 N04 NRC TLD DIRECT RADIATION MONITORING Seismic Effect NETWORK. Progress Report October-December 1993.

NUREG/CH-6t09 RELAY T EST PROGRAM Senes ll Tests integral Test ~

TMI Action Plan ing Of Relays And Circuit Breakers ~

NUREG-1435 S03. STATUS OF SAFETY ISSUES AT LICENSED Se6smec Network POWER PLANTS TMl Acton Plan Requirements unresolved Safety NUREO /CR-6209.

ME MPHtS AREA REGIONAL SEISMIC issues Generic Safety issucs Other Multiplant Acton Issues.

NETWORK Final Report, October 1986 September 1992.

Seism 6c Testing NUREG/CR 6198: TMI-2 INSTRUMENT NO72LE EXAMINATIONS PER.

NUREG/CR-5935'

SUMMARY

OF WORK COMPLETED UNDER THE FORMED AT THE INEL ENVtRONMENTAL AND DYNAMIC EQUIPMENT GUALIFICATION RE-SEARCH PROGRAM LEDOP).

Technical Train 6ng Center NUREG/CR 6042: PERSPECTIVES ON REACTOR SAFETY.

Selsmicity NUREG/CR 3145 VIO: GEOPHYSICAL INVESTIGATIONS OF 1HE Tensile-Property WESTERN OHIOwlNDIANA REGION Final Report. October 1986 Sep-NUREG/CR 6142: TENSILE-PROPERTY CHARACTERilATION OF l

tomber 1992.

THERMALLY AGED CAST STAINLESS STEELS.

l

l Subject Index 27 Test Reactor Vessel NUREG/CR-6076: TR-EDB: TEST REACTOR EMBRITTLEMENT DATA NUREG/CR4196. CALCULATONS TO ESTIMATE THE MARGIN TO

(

BASE, VERSION 1.

FAILURE IN THE TMI 2 VESSEL Thermat Ag6ng Weste Compact NUREG/CR6142: TENSILE-PROPERTY CHARACTER 12ATION OF NUREG/CR 6147 V01: CHARACTERi2ATION OF CLASS A LOW-LEVEL THERMALLY AGED CAST STAINLESS STEELS.

RADIOACTIVE WASTE 1986-1990 Executwe Summary.

NUREG/CR 6147 V02: CHARACTER 12ATON OF CLASS A LOW-LEVEL Thermal Damage RADIOACTIVE WASTE 19861990 Main Report Part A.

NUREG/CR-6194-METALLOGRAPHIC AND HARDNESS EXAMINA.

NUREG/CR4147 V03. CHARACTERIZATION OF CLASS A LOW-LEVEL TONd OF TMI-2 LOWER PRESSURE VESSEL HEAD SAMPLES.

RADIOACTIVE WASTE 1986-1990. Main Report-Part B.

t NUREG/CR-6147 V04: CHARACTERIZATION OF CLASS A LOW LEVEL Thermal Detonation RADCACTIVE WASTE 19861990 Apperxices A.E.

NUREG/CR-5960: STEAM EXPLOSIONS: FUNDAMENTALS AND EN-NUREG/CR-6147 V05: CHARACTERIZATION OF CLASS A LOW LEVEL GERGETIC BEHAVIOR-RADIOACTIVE WASTE 19861990.Apperwix F.

NUREG/CR4147 V06. CHARACTERl2ATION OF CLASS A LOW-LEVEL Thermal Embrittlement RADIOACTIVE WASTE 19861190.Apperutces G-J NUREG/CR-6142-TENSILE-PROPERTY CHARACTERIZATION OF NUREG/CR-6147 V07: CHARACTERIZATON OF CLASS A LOW-LEVEL THERMALLY AGED CAST STAINLESS STEELS RADtvACTIVE WASTE 19861990.Appendees K-P.

Thermal Response RE /

47 VOI: CHARACTER 12ATION OF CLASS A LOW-LEVEL LU E N THE TMI 2 5 RADIOACTIVE WASTE 1986-1990.Executwo Summary NUREG/CR-6147 V02: CHARACTERIZATION OF CLASS A LOW-LEVEL Thermoluminescent Dosimeter NUREG 0837 V13 N04: NRC TLD DIRECT RADIATON MONITORING RADIOACTIVE WASTE 1986-1990.Masn Report-Part A.

NUREG/CR4147 V03: CHARACTERl2ATION OF CLASS A LOW. LEVEL NETWORK. Progress Report. October Decemter 1993.

RADIOACTIVE WASTE 1988-1990. Main Report-Part B.

Title List NUREG/CR 6147 V04: CHARACTERIZATION OF CLASS A LOW-LEVEL NUREG-0540 V15 Nil. TITLE LIST OF DOCUMENTS MADE PUBLICLY RADIOACTIVE WASTE 1986-1990.Appendees A E.

NUREG/CR-6147 V05. CHARACTER 12ATION OF CLASS A LOW LEVEL AVAILABLE November 1-30.1993_

NUREG-0540 V15 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY RADIOACTIVE WASTE 19861990. Appendix F.

AVAILABLE. December 1-31,1993.

NUREG/CR-6147 V06: CHARACTERIZATION OF CLASS A LOW-LEVEL NUREG 0540 V16 Not: TITLE LIST OF DOCUMENTS MADE PUBLICLY RADIOACTIVE WASTE 1986-1190 Appendcas G J AVAILAULE. January 1-31,1994.

NUREG/CR4147 V07: CHARACTERIZATION OF CLASS A LOW-LEVEL RADIOACTIVE WASTE 19861990.Appendees K P.

Tube Failure NUREG/CR6196. CALCULATIONS TO ESTIMATE THE MARGIN TO Water Flow FAILURE IN THE TMI-2 VESSEL.

NUREG/CR4063: INTRAVAL PHASE 11 MODEL TESTING AT THE LAS I

CRUCES TRENCH SITE.

Valve NUREG/CR-5935

SUMMARY

OF WORK COMPLETED UNDER THE Whistleblower ENVIRONMENTAL AND DYNAMIC EQUIPMENT QUALIFICATION RE-NUREG-1499: REASSESSMENT OF THE NRC'S PROGRAM FOR PRO-SE ARCH PROGRAM (EDOP)

TECTING ALLEGERS AGAINST RETAllATION.

Vendor inspection Workshop NUREG 0040 V17 N04: LICENSEE CONTRACTOR AND VENDOR IN.

NUREG/CR4156*

SUMMARY

OF COMMENTS RECEIVED FROM SPECTION STATUS REPORT. Quarterly ReportOctober-December WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-1993 (White Book)

ING.

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=

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.

OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)

EDO OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM OFC OF THE EXECUTIVE DIRECTOR FOR OPERATIONS NUREG-1499 REASSESSMENT OF THE NRC'S PROGRAM FOR OF(POST 861109)

FICE OF INFORMATION RESOURCES MANAGEMENT (POST PROTECTING ALLEGERS AGAINST RETALIATON.

890205)

REGION 1 (POST 820201)

NUREG-0020 V18: LICENSED OPERATING REACTORS STATUS NUREG4837 Vl3 N04: NRC TLD DtRECT RADIATION MONITORING

SUMMARY

REPORT.Deta As Of December 31,1993.(Gray Book l) m NETWORK Progress Report October-December 1993.

OFC OF ENFORCEMENT (POST 870413)

EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG-0940 V12 NO3 ENFORCEMENT ACTONS-SIGNIFICANT AC-OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS TiONS RESOLVED.Ouarteriy Progress Report July-September 1993.

NUREG-0430 V13: LICENSED FUEL FACILITY STATUS NUREG-0940 V12 N04 ENFORCEMENT ACTONS. SIGNIFICANT AC-REPORT. Inventory Defterence Data. July 1,

1992. June 30, TONS RESOLVED.Ouarterly Progress Report, October-December 1993 (Gray Book 11) 1993.

DIVISION OF LOW LEVEL WASTE MANAGEMENT & DECOMMISSION-ING (870413-940402 EDO. Of FICE OF ADMINISTRATION (PRE 870413 & POST 890205)

NUREG-1486. FINAL SAFETY EVALUATION REPORT TO LICENSE DIVISION OF FREEDOM OF INFORMATON & PUBLICATIONS SERV-THE CONSTRUCTION AND OPERATION OF A FACILITY TO ICES (POST 890205 RECEIVE, STORE AND DISPOSE OF 11E(2) BYPRODUCT MATERI-NUREG-0540 V15 N11: TITLE LIST OF DOCUMENTS MADE PUBUC-AL NEAR CLIVE UTAH Docket No. 448989(Envirocare of Utah.Inc.)

LY AVAILABLE November 1-30,1993.

OfVISION OF FUEL CYCLE SAFETY & SAFEGUARDS (POST 930207)

NUREG-0540 V15 N12. TITLE LIST OF DOCUMENTS MADE PUBLIC-NUREG-1491: SAFETY EVALUATION REPORT FOR THd CLAl-LY AVAILABLE December 1 31. 1993.

BORNE ERICHMENT CENTER. HOMER. LOUISIANA. Docket No.

NUREG4540 V16 N01: TITLE LIST OF DOCUMENTS MADE PUBLIC-70 3070,L aana Energy Services.LP.

LY AVAILABLE. January 1-31,1994.

NUREG 0750 V38101: INDEXES TO NUCLEAR REGULATORY COM-EDO. OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

MISSION ISSUANCES July-September 1993.

OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 860720)

NUREG 0750 V38 N05: NUCLEAR REGULATORY COMMISSION IS.

NUREG/CR-5569 R01: HEALTH PHYSICS POSITIONS DATA BASE.

A NA E T

CY VE T

A LY IS A

F DE EMB 3 Pa 8 3 NUREGO936 V12 N04. NRC REG ATORY AGENDA Ouarterty gkA[f[Sh8]'1 S

T

& MW mm M We Report.Or.tober December 1993 POWER PLANTS.TMI Action Plan Requirements. Unresolved Safety EDO OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205) issues Genenc Safety lasues Other Multipiant Action issues.

ASSOCIATE DIRECTOR FOR ADVANCED REACTORS & UCENSE RE-OtVISION OF BUDGET & ANALYSIS (POST 890205)

NUREG-1100 VIO DVDGET ESTIMATES Fracal Year 1995.

NEW S 91 EDO. OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL FOR THE POWER REACTOR INNOVATIVE SMALL MODULE

")ATA (PRISM) LIOUID-METAL REACTOR. Final Report.

OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA, DI-DIVISION OF REACTOR INSPECTON & LICENSEE PERFORMANCE RECTOR (POST 921004)

NURE G-1022 R01 DR FC: EVENT REPORTING GUIDELINES NUREG-0040 V17 N04: LICENSEE CONTRACTOR AND VENDOR IN-10CF RSO 72 AND 50.73 Second Draft For Comment.

SPECTION STATUS REPORT. Quarterly Report,0ctober-December OlVISION OF OPERATIONAL ASSESSMENT (POST 870413) 1993 (White Book)

NUREG 1471: CONCEPT OF OPERATIONS WITH ORGANIZATION NUREG-1214 R13. HtSTORICAL DATA

SUMMARY

OF THE SYSTEM-CHARTS NRC incident Response.

ATIC ASSESSMENT OF LICENSEE PERFORMANCE.

29

E

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.

OF F I.E F NUC E PEG TORY 'E SE AF H S

720 NUREG/lA-0114 ASSESSMENT OF RELAPS/MO WITH THE LOFT L91/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRAN-SIENT WITH MULTIPLE FAILURES l

31

-u..-.

1

)

i P

I i

)

i l

)

i 1

)

l i

m----.

+

e

(-

p

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) prepared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.

EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR4190: TMI-2 INSTRUMENT NOZZLE EXAMINATIONS DATA PERFORMED AT THE INEL DIVISION OF SAFETY PROGR AMS (POST 870413)

NUREG/CR-6209:

MEMPHIS AREA REGIONAL SEISMIC NUREG/CR-4674 V17. PRECURSORS TO POTENTIAL SEVERE NETWORK. Final Report, October 1986 - September 1992.

CORE DAMAGE ACCIDENTS 1992 A STATUS REPORT. Main DIVISION OF REGULATORY APPLICATIONS (POST B70413) -

Report And Apperda A.

NUREG/CR-4833: LARGE AREA SELF-POWERED GAMMA RAY NUREG/CR-4874 V18 PRECURSORS TO POTENTIAL SEVERE DETECTORPhase !! Development Of A Source Poortion Mordtor For CORE DAMAGE ACCIDENTS-1992 A

STATUS Use On Industnal Radographic Uruts.

REPO'1T.Appendees B, C D, E. F, And G NUREG/CR-5569 R01: HEALTH PHYSICS POSITIONS DATA BASE.

NUREG/CR 6063: INTRAVAL PHASE il MODEL TESTING AT THE EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS LAS CRUCES TRENCH SITE DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NUREG/CR4112 DRF FC: IMPACT OF REDUCED DOSE LIMITS ON NUI G R4088 SUMMAR( OF 1991-1992 MISADMINISTRATION One ecommendehons&an Repod 6 Com-EVENT INVESTIGATIONS.

I NU

/CR4138: USER'S GUIDE FOR SIMPLIFIED COMPUTER U EG/CR 4 PL CA 10 S F I Tl S HYI Al MODELS FOR THE ESTIMATION OF LONG TERM PERFORM-PROTECTION.

ANCE OF CEMENT BASED MATERIALS.

EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

NUREG/CR4147 VO1: CHARACTERIZATION OF CLASS A LOW-DIVISION OF ENGINEERING (POST 870413)

LEVEL RADIOACTIVE WASTE 19861990. Executive Summary.

NUREG/CH-3145 V10. GEOPHYSICAL INVESTIGATIONS OF THE NUREG/CR-6147 V02: CHARACTERIZATION OF CLASS A LOW-WESTERN OHIO' INDIANA REGION Final Report, October 1986-LEVEL RADIOACTIVE WASTE 1986-1990. Main Report-Part A.

September 1992.

NUREG/CR4147 V03: CHARACTERIZATION OF CLASS A LOW-NUREG/CR-4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING LEVEL RADIOACTIVE WASTE 1986-1990. Main Report-Part B.

WELDS Serrmannual Report, October 1992 - March 1993.

NUREG/CR4147 V04: CHARACTERIZATION OF CLASS A LOW-NUREG/CR-4816 R02: PR-EDB: POWER REACTOR EMBRITTLE-LEVEL RADIOACTIVE WASTE 19861990.Appendees A-E.

MENT DATA BASE. VERSION 2. Program Descnption.

NUREG/CR4147 V05: CHARACTERIZATION OF CLASS A LOW-NUREG/CR-5161 V02: EVALUATION OF SAMPLING PLANS FOR IN-LEVEL RADIOACTIVE WASTE 1986-1990. Appends F.

SERVICE INSPECTION OF STEAM GENERATOR NUREG/CR4147 V06: CHARACTER 12ATION OF CLASS A LOW-TUBES Comprehenswe Analytical And Monte Carlo Simulahon Re-LEVEL RADIOACTIVE WASTE 19861190.Appendcas G J.

suits For Several Samplino Plans.

NUREG/CR4147 V07: CHARACTERIZATION OF CLASS A LOW.

NUHEG/CR-5314 V05: IN$1GHTS FOR AGING MANAGEMENT OF LEVEL RADIOACTIVE WASTE 19861990.Appendees K-P.

MAJOR L WR COMPONENTS METAL CONTAINMENTS NUREG/CR4156:

SUMMARY

OF COMMENTS RECEIVED FROM NUREG/CR4407: ASSESSMENT OF THE IMPACT OF DEGRADED WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMIS-SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-SIONING.

MIC DESIGN LOADS DIVISION OF SAFETY ISSUE RESOLUTION (POST 880717)

NUREG/CR 5812: MANAGING AGING IN NUCLEAR POWER NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCIDENT l

PLANTS Insights From NRC Maintenance Team inspection Reports.

RISKS: METHODOLOGY FOR THE CONTAINMENT, SOURCE NUREG/CR-5935:

SUMMARY

OF WORK COMPLETLD UNDER THE TERM, CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

I ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUALIFICATION NUREG/CR4042: PERSPECTIVES ON REACTOR SAFETY.

I RESEARCH PROGRAM (EDOP)

NUREGICR4107:

SUMMARY

OF MELCOR 1.8.2 CALCULATIONS

(

NUREG/CR-5963. CONTINUOUS AE CRACK MONfTORING OF A FOR THREE LOCA SEQUENCES (AG,S2D & S30) AT THE SURRY DISS!MILAR METAL WELDMENT AT LIMERICK UNIT 1.

PLANT.

NUREG/CR 5985 EVALUATION OF COMPUTER-BASED ULTRA-NUREG/CR4145: VERIFICATION AND VAUDATION OF THE SA.

SONIC INSERVICE INSPECTION SYSTEMS.

PHIRE VERSION 4.0 PAA SOFTWARE PACKAGE.

NUREG/CR 5990. THE EFFECTS OF SOLAR-GEOMAGNEDCALLY DIVISION OF SYSTEMS RESEARCH (POST 880717)

INDUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NUREG/CR-5960: STEAM EXPLOSIONS: FUNDAMENTALS AND EN.

POWER STATIONS GERGETIC BEHAVIOR.

NUREG/CR.6076: TR-EDB: TEST REACTOR EMBRITTLEMENT NUREG/CR4077: DATA

SUMMARY

REPORT FOR FISSION PROD-DATA BASE. VERSION 1.

UCT RELEASE TEST V14.

NUREG/CR4103. PRIORITIZATION OF REACTOR CONTROL COM-NUREG/CR4122: STAFFING DECISION PROCESSES AND PONENTS SUSCEPTIDLE TO FIRE DAMAGE AS A CONSE-ISSUES. Case Studies Of Seven U.S. Nuclear Power Plants.

QUENCE OF AGING NUREG/CR4123: AN INTERNATIONAL COMPARISON OF COM-NUREG/CR4132. BIAxlAL LOADING AND SHALLOW-FLAW EF.

MERCIAL NUCLEAR POWER PLANT STAFFING REGULATIONS FECTS ON CRACK TIP CONSTRAINT AND FRACTURE TOUGH-AND PRACTICE.1980-1990.

NESS NUREG/CR-6133. FRAGMENTATION AND QUENCH BEHAVIOR OF PUREG/CR-6139 CRACK-ARREST TESTS ON TWO 1RRADIATED CORIUM MELT STREAMS IN WATER.

HIGH COPPER WELDS Phase 11. Results Of Duplen. Type Speci-NUREG/CR4158: IMPLICATIONS FOR ACCIDENT MANAGEMENT OF ADDING WATER TO A DEGRADING REACTOR CORE.

mens NUREG/CR-6142: TENSILE-PROPERTY CHARACTERIZATION OF NUREG/CR4194: METALLOGRAPHIC AND HAADNESS EXAMINA-THERMALLY AGED CAST STAINLESS STEELS.

TlONS OF TMI-2 LOWER PRESSURE VESSEL HEAD SAMPLES.

NUREG/CR4169 RELAY TEST PROGRAM.Senes 11 Tests. Integral NUREG/CR4196: CALCULATIONS TO ESTIMATE THE MARGIN TO Testing Of Relays And Crcuit Breakers.

FAILURE IN THE TMi-2 VESSEL 33

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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 f

NUREG/CR number.

l ADVANCED SYSTEMS TECHNOLOGY,INC.

EASTERN RESEARCH GROUP,INC.

NUREG/CR 6156.

SUMMARY

OF COMMENTS RECEIVED FROM NUREG/CR4147 V01: CHARACTERIZATION OF CLASS A LOW-LEVEL WORKSHOPS ON RADIOLOGICAL CRITERIA FOR DECOMMISSION-RADIOACTIVE WASTE 19861990.Executwe Summary ING.

NUREG/CR-6147 V02: CHARACTERIZATION OF CLASS A LOW LEVEL RADIOACTIVE WASTE 1986-1990. Main Repor1 Part A ARGONNE NATIONAL LABORATOHY NUREG/CH-6147 V03: CHARACTERIZATION OF CLASS A LOW-LEVEL NUREG/CR 6133 FRAGMENTATION AND OUENCH BEHAVIOR OF RADIOACTIVE WASTE 19861990 Main Report-Part B.

CORIUM MELT STREAMS IN WATER NUREG/CR-6147 V04. CHARACTERIZATION OF CLASS A LOW LEVEL NUREG/CR 6142: TENSILE PROPERTY CHARACTERIZATION OF RADIOACTIVE WASTE 1986-1990. Appendices A E.

THERMALLY AGED CAST STAINLESS STEELS.

NUREG/CR4147 V05: CHARACTERIZATION OF CLASS A s%-LEVEL RADIOACTIVE WASTE 19861990.Apperdx F.

ARIZONA STATE UNIV, TEMPE, AZ NUREG/CR-6147 V06: CHARACTERIZATON OF CLASS A LOW-LEVEL NUREG/CR-4551 V01 R1. EVALUATION OF SEVERE ACCIDENT RADIOACTIVE WASTE 1986-1190. Appendices G-J.

RIE.(S METHODOLOGY FOR THE CONTAINMENT, SOURCE NUREG/CR 6147 V07: CHARACTERIZATION OF CLASS A LOW-LEVEL TERM.CONSEOVENCE. AND RISK INTEGRATION ANALYSES-RADIOACTIVE WASTE 1986-1990. Appendices K P.

ARIZONA, UNIV. OF, TUCSON, AZ EG&G IDAHO, INC.

NUREG/CR6063. INTRAVAL PHASE il MODEL TESTING AT THE LAS NUREG/CR-5935:

SUMMARY

OF WORK COMPLETED UNDER THE CRUCES TRENCH SITE.

ENVIRONMENTAL AND DYNAMIC EQUIPMENT OUALIFICATION RE-SEARCH PROGRAM (EDOP)

BATTELLE HUMAN AFFAIRS RESEARCH CENTERS NUREG/CR-6088-

SUMMARY

OF 1991 1992 MISADMINISTRATION NUREG/CR 6122: STAFFING DECISION PROCESSES AND EVENT INVESTIGATIONS.

ISSUES Case Studies Of Seven U S Nuclear Power Plants.

NUREG/CR-6138. USER'S GUIDE FOR SIMPLIFIED COMPUTER 7

NUREG/CH-6123 AN INTERNATONAL COMPARISON OF COMMER.

MODELS FOR THE ESTIMATION OF LONG-TERM PERFORMANCE i

l CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND OF CEMENT-BASED MATERIALS PRACTICE.19801990.

NUREG/CR-6158; IMPLICATIONS FOR ACCIDENT MANAGEMENT OF ADDING WATER TO A DEGRADING REACTOR CORE.

BATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES CRW CM M WAWHMMS N M NUREG/CR-4599 V03 N2: SHORT CRACKS IN PIPING AND PIPING TONS OF TMI-2 LOWER PRESSURE VESSEL HEAD SAMPLES.

WELDS Semiannual Report. October 1992 March 1993 NUREG/CR4196: CALCULATIONS TO ESTIMATE THE MARGIN TO FA LURE IN THE T MI 2 V E

EATT LLE EMORIAL INSTITUTE, PACIFIC NORTHWEST FORMED AT THE INEL NUREG/CR 5161 V02: EVALUATION OF SAMPLING PLANS FOR IN-TU E e

An tytcal Monte rio Simu a Resu C

NUREG/CR-5407; ASSESSMENT OF THE IMPACT OF DEGRADED NUREG T UOUS AE CRACK MONPORING OF A DIS-SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-SIMILAR METAL WELDMENT AT LIMERICK UNIT 1.

MIC DESIGN LOADS-NUREG/CR 5985: EVALUATION OF COMPUTER-BASED ULTRASONIC INSERVICE INSPECTON SYSTEMS.

O A

^ 8V NU E /CR NT AVAL PHASE 11 MODEL TESTING AT THE LAS R

kH FF SOLAR-GEOMAGNETICALLY IN-DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NUREG/CR 6122: STAFFING DECISION PROCESSES AND POWER STATIONS.

ISSUES Case Studies Of Seven U S. Nuclear Power Plants.

NUREG/CR 6123: AN INTERNATIONAL COMPARISON OF COMMER-GEO-CENTERS,1NC.

CIAL NUCLEAR POWER PLANT STAFFING REGULATIONS AND NUREG/CR-6107:

SUMMARY

OF MELCOR 1.8.2 CALCULATIONS FOR PRACTICE.19801990.

THREE LOCA SEQUENCES (AG,S2D & S3D) AT THE SURRY PLANT.

BROOKHAVEN NATIONAL LABORATORY NUREG/CR=5812: MANAGING AGING IN NUCLEAR POWER HAWAll, UNIV. OF, HILO, HI PLANTS Insghts From NRC Maintenance Team inspection Reports NUREG/CR 4551 VC1 R1: EVALUATION OF SEVERE ACCIDENT NUREG/CR.5990. THE EFFECTS OF SOLAR-GEOMAGNETICALLY IN-RISKS: METHODOLOGY FOR THE CONTAINMENT, SOURCE DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR TERM. CONSEQUENCE. AND RISK INTEGRATION ANALYSES.

POWER STATIONS.

NUREG/CR4112 DRF FC: IMPACT OF REDUCED DOSE LIMITS ON IDAHO NATIONAL ENGINEERING LABORATORY NRC LICENSED ACTIVITIES. Maior issues in The implementaten Of NUREG/CR-5314 VOS: INSIGHTS FOR AGtNG MANAGEMENT OF ICRP/NCRP Dose let RecommendationsSaft Report For Commert MAJOR LWR COMPONENTS METAL CONTAINMENTS.

NUREG/CR 6169 RELAY TEST PROGRAM Seres 11 Tests. Integral Test-NUREG/CH 6145: VERIFFATION AND VAllDATION OF THE SAPHIRE eng Of Relays And Crcuit Breakers.

VERSION 4.0 PRA SOFTWARE PACKAGE-CALIFORNIA, UNIV. OF, SANTA BARBARA, CA ILLINOIS, UNIV. OF, URBANA, IL NUREG/CR-5960: STEAM EXPLOSIONS: FUNDAMENTALS AND EN-NUREG/CR4133: FRAGMENTATION AND OUENCH BEHAVIOR OF GERGETIC BEHAVIOR.

CORIUM MELT STREAMS IN WATER.

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES JOHNS HOPKINS UNIV, BALTIMORE, MD NUREG/CR-6063: INTRAVAL PHASE 11 MODEL TESTING AT THE LAS NUREG/GR-0008. VALIDATION OF SEISMIC PROBADILISTIC RISK AS-CRUCES TRENCH SITE-SESSMENTS OF NUCLEAR POWER PLANTS.

35 l

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36 Contractor index K.E..M.P. CORP, NUREG/CR-4674 V18. PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 4833: LARGE AREA SELF-POWERED GAMMA RAY DAMAGE ACCIDENTS.1992 A STATUS REPORT. Appendices B, C, D, DETECTOR Phase ll Deve6opment Of A Source Posstion Monitor For E, F And G.

Use On industnal RadiograpNc Units.

MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE, MA NUREG/CR 6147 V01: CHARACTERIZATION OF CLASS A LOW LEVEL NUREG/CR-6063 INTRAVAL PHASE il MODEL TESTING AT THE LAS RADIOACTIVE WASTE 1986-1990 Executive Summary.

CRUCES TRENCH SITE.

NUREGICR-6147 702: CHARACTERIZATION OF CLASS A LOW-LEVEL RADIOACTIVE WASTE 1986-1990 Main Repor1-Part A.

MEMPHIS STATE UNIV., MEMPHIS TN NUREG/CR-6147 V03. CHARACTERIZATION OF CLASS A LOW-LEVEL NUREG/CR 6209 MEMPHIS AREA REGIONAL SE:SMIC RADIOACTIVE WASTE 1986-1990 Main Report-Part B.

NETWORK Final Report, October 1986 September 1992.

NUREG/CR4147 V04: CHARACTERl2ATION OF CLASS A LOW-LEVEL RADIOACTIVE WASTE 1986-1990.

A-E.

MICHIGAN, UNIV. OF, ANN ARBOR, MI NUREG/CR4147 V05: CHARACTERI ATION OF CLASS A LOW LEVEL NUREG/CR 3145 V10. GEOPHYSICAL INVESTIGATIONS OF THE RADIOACTIVE WASTE 1986-1990 Appendm F.

WESTERN OHIO-INDIANA REGION Final Report, October 1986-Sep.

NUREG/CR4147 V06: CHARACTERIZATION OF CLASS A LOW-LEVEL tember 1992.

RAD 60 ACTIVE WASTE 19861190. Appendices GJ NUREG/CR-6147 V07: CHARACTERIZATION OF CLASS A LOW-LEVEL MOS, INC.

RADIOACTIVE WASTE 19861990. Appendices K-P.

NUREG/CR 5990: THE EtTECTS OF SOLAR-GEOMAGNETICALLY IN-SANDIA NATIONAL LABORATORIES DUCED CURRENTS ON ELECTRICAL SYSTEMS IN NUCLEAR NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCIDENT POMR STATIONS.

RISKS: METHODOLOGY FOR THE CONTAINMENT SOURCE NEW MEXICO STATE UNIV., LA1 CRUCES, NM TERM, CONSEQUENCE, AND RISK INTEGRATION ANALYSES.

NUREG/CR4063. INTRAVAL PHASE 11 MODEL TESTING AT THE LAS NUREG/CR-5407: ASSESSMENT OF THE IMPACT OF DEGRADED CRUCES TRENCH SITE, SHEAR WALL STIFFNESSES ON SEISMIC PLANT RISK AND SEIS-MIC DESIGN LOADS.

NEW MEXICO, UNIV. OF, A1 GUQUEROUE, NM NUREG/CR-6042: PERSPECTIVES ON REACTOR SAFETY.

NUREG/CR 6042 PERPECTIVES ON REACTOR SAFETY.

NUREG/CR-6103. PRIORITIZATION OF REACTOR CONTROL COMPO-NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF OAK RIDGE NATIONAL. LABORATORY AGING NUREG/CR-4674 V11. PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-6107:

SUMMARY

OF MELCOR 1.8.2 CALCULATIONS FOR DAMAGE ACCIDE NTS: 1992 A STATUS REPORT. Main Report And THREE LOCA SEQUENCES (AG,S2D & S3D) AT THE SURRY PLANT.

Ao NUREG/CR-6149. APPLICATIONS OF FIBER OPTICS IN PHYSICAL NUkpendixA.

EG/CR-4674 Vit PRECURSORS TO POTENTIAL SEVERE CORE PROTECTION DAMAGE ACCIDENTS.1992 A STATUS REPORT. Appendices B, C D, SCIENCE & ENGINEER!NG ASSOCIATES,INC.

NUREG/CR-4816 R02. PR-EDB. POWER REACTOR EMBRITTLEMENT NUREG/CR4103: PRIORITIZATION OF REACTOR CONTROL COMPO-DATA BASE. VERSION 2. Program Desenption.

NENTS SUSCEPTIBLE TO FIRE DAMAGE AS A CONSEQUENCE OF NUREG/CR-5569 RO1: HEALTH PHYSICS POSITIONS DATA BASE AGING.

NUREG/CR4076: TR-EDB TEST REACTOR EMBRITTLEMENT DATA BASE, VERSION 1.

SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY NUREG/CR 6077: DATA

SUMMARY

REPORT FOR FISS4ON PRODUCT SCIENCE APPLICATIONS, RELEASE TEST VI-6.

NUREG/CR-4674 V17: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-6132: DIAXIAL LOADING AND SHALLOW-FLAW EFFECTS DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Main Report And ON CRACK TIP CMSTRAINT AND FRACTURE TOUGHNESS.

Appenda A.

NUREG/CR 613v t f./,CK-ARREST TESTS ON TWO IRRADIATED NUREG/CR-4674 V18. PRECURSORS TO POTENTIAL SEVERE CORE HIGH40PPER WELDS Phase 11. Results Of Duplex-Type Specimens.

DAMAGE ACCIDENTS: 1992 A STATUS REPORT. Appendices B, C, D.

OODEN ENYlRONMENTAL & ENERGY SERYlCES (FORMERLY MULTIPLE DYNAMICS CORP) 1ECHNADYNE ENGINEERING CONSULTANTS,INC.

NUREG/CR-5314 V05' INSIGHTS FOR AGING MANAGEMENT OF NUREG/CR-4551 V01 R1: EVALUATION OF SEVERE ACCIDENT MAJOR LWR COMPONENTS METAL CONTAINMENTS.

RISKS: METHODOLOGY FOR THE CONTAINMENT. SOURCE ORGANIZATION FOR ECONOMIC COOPERATION & DEVELOPMENT l

NUREG/CP 0127: PROCEEDINGS OF THE CSNI SPECIALISTS MEET.

TEXAS, UNIV. OF, AUSTIN, TX ING ON FUEL-COOLANT INTERACTIONS.

NUREG/CR-6063-INTRAVAL PHASE 11 MODEL TESTING AT THE LAS CRUCES TRENCH S;TE.

REllADILITY AND PERFORMANCE ASSOCIATES NUREG/CR-4674 V17: PRFCURSORS TO POTENTIAL SEVERE CORE WISCONSIN. UNIV. 0F, MAOISON, W1 DAMAGE ACCIDENTS.1992 A STATUS REPORT Main Report And NUREG/Ct' 6196 CALCULJTIONS TO ESTIMATE THE MARGIN TO Appernlix A.

FAILURE IN THE TMI-2 VEb.'TL.

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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 inscr-mation is needed, refer to the main citation by the NUREG/lA number.

RE 4

S NT F ELAPS / MOD 3 WITH THE LOFT L41/L3-3 EXPERIMENT SIMULATING AN ANTICIPATED TRAN-SIENT WITH MULTIPLE FAILURES.

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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.

4 8989 Enwouro of Utan. Inc, San Lake Cay. UT, NUREG-1486 S 320 Three We island Nucles Staton, Und 2.

NUREG/CR 6194 Suny ta on,

1. r UR / 4:07 S 320 ~

Thr Nucipw Staton, Unn 2, NUREG/CR4196

% 281 Surry Power Stanon, Und 2, Vrprus Elecinc & NUREG/CR4107 2 320 Thr Nuclew Staton, Und 2, NUREG/CR4196 se, Co.

Gena. U J

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_n 7F4C FORM 335

' U.S. NUCLEAR REGULATORY COMMISSION

1. REPORT NUMBER (2-60)

( Assigned by NRC, Add Vol..

NRCM 1102, Supp., Rev., and Addendum Num.

32ci,32o2 BIBLIOGRAPHIC DATA SHEET b*"-

" *aY 3 '

tsee instructions on t; reverso)

NUREG-0304 Vol.19, No.1

2. mLE AND SUBMLE

3. DATE REPORT PUBUSHED Regulatory and Technical Reports (Abstract Index Journal)

MONTH YEAR Compilation for First Quarter 1994 June 1994 January - March

4. rtN OR GRANT NUMBER

b. AU[HQR(S)

6. TYPE OF REPORT Reference

7. PERIOD COVERED (inclusive Dates)

January-March 1994

8. f%RFORMING ORGANIZAT40N - NAME AND ADDRESS (if NRC, provide On sion, Office or Region, U.S. Nuclear Regulatory Comm6ssion and h

rnailing address; if contractor, provide name and malling address.)

Division of Freedom of Information and Publications Services Office of Administration

' U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

9. Sf ONSOHING OHGAN14ATION - NAME AND ADDRESS (if NRC, type "Same as above'; af contractor, provide NRC Division, Office or Region.

U 'S. Nuclear Regulatory Commission, and mailing address.)

Same as 8, above.

a 10 SUPF'LEMENT AHY NOTES

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, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, sectmdary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

I k

12. KEY WORDS,OESCRIPTORS (List words or phr;..es wat will assist researchers in locating the report.)

13. AVAILABluTY STATEMENT Unlimited

14. SECURITY CLASSIFICATION Compilation

(. This Page) abstract index Unclassified (This Report)

Unclassified

16. NUMBER OF PAGES 16, PRICE o

O NRC FORM 335 (2-89)

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