ML20135E818

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Third Quarter 1996,July-September

ML20135E818
Person / Time
Issue date:	02/28/1997
From:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
To:
References
NUREG-0304, NUREG-0304-V21-N03, NUREG-304, NUREG-304-V21-N3, NUDOCS 9703100239
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i NUREG-0304 l

Vol. 21, No. 3

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

1.

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

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

The National Technical Information Service, Springfield, VA 22161-0002 i

Although the listing that follows represents the majority of documents cited in NRC publica-l tions, it is not intended to be exhaustive.

Refen:,nced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda: NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence: Commission papers; and applicant and licensee docu-ments and correspondence.

The following d6cuments in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, grantee reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, kad Nuclear Regulatory Commission Issuances.

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

Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.

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

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

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North.11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National l

Standards, from the American National Standards Institute,1430 Broadway, New York, NY I

10018-3308.

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NUREG-0304 Vol. 21, No. 3 1

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Regulatory and Technical Reports (Abstract Index Journal)

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Compilation for Third Quarter 1996 July - September Date Published: February 1997 M. A. Sheehan, Project Manager Publications Branch Office ofInformation Resources Management U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 pm,u s.....

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l CONTENTS Preface v

index Tab Main Citations and Abstracts.

1 Staff Reports e

e Conference Proceedings Contractor Reports e

e Grant Reports Intemational Agreement Reports e

Secondary Report Number index..

2 Personal Authorindex 3

Subject index 4

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

8 Intemational Organization index 9

Ucensed Facility index 10 ill

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 cc ractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be appreciated. Please send them to:

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

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

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor Index (Contractor Reports)

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

The bibliographic elements of the main citations are the following:

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

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

Conference Report i

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

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

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

v

l Contr:ctor Report NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, RR. Sandia Labo-ratories. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.

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

or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-j trol System accession number, (8) the report number of the originating organization (if given), (9) the micro-fiche address (for NRC internal use).

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

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

1 International Agreement Report NUREG/lA-00'11: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUP /NN, U. Kraftweek Union. August 1986. 223 pp. 8608270424. 37659:138.

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

l 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 7

4 Availebility of NRC Publications 1

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

d Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 j

Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202) 512-2249 or (202) 512-2171. Non-U.S. customers must make payment in ad-vance 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.

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NRC R? port Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated re-port Contractor-prepared formal NRC reports carrythe report code NUREG/CR-XXXX. This type ofidentifi-cation replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being re-ported.

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

I Allthese report codes are controlled and assigned bythe staff of the Publications Branch of the NRC Office l

of Information Resources Management.

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Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is

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an 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 report. The bibliographic information (see Preface for details) is followed by a brief abstract of this report.

i NUREG-0040 V20 NO2: LICENSEE CONTRACTOR AND This document is a monthly publication containing descrip-VENDOR INSPECTION STATUS REPCRT. Quarterly tions of information received c nd generated by the U.S. Nuclear Report, April-June 1996.(White Book)

• Office of Nuclear Reac-Regulatory Commission (NRG). This information includes (1) tor Regulation (Post 941001). August 1996. 224pp.

docketed material associated with civibn nuclear power plants 9609100272. 89604:009.

and other uses of radioactive rnaterials, and (2) nondocketed This periodical covers the results of inspections performed by material received and generated by NRC pertinent to its role as the NRC's Special Inspection Branch, Vendor inspection Sec-a regulatory agency. The following indexes are included: Per-tion, that have been distributed to the inspected organizations sonal Author, Corporate Source, Report Number, and Cross during the period from April through June 1996.

Reference of Enclosures to Pnncipal Documents.

NUREG-0304 V21 N32: REGULATORY AND TECHNICAL RE-PORTS (ADSTRACT INDEX JOURNAL). Compilation For NUREG-0540 V18 N06: TITLE LIST OF DOCUMENTS MADE Second Quarter 1996, April-June.

• Division of Freedom of infor-PUBLICLY AVAILABLE. June 1 30, 1996.

• Division of Freedom mation & Publications Services (Post 940714). August 1996.

of information & Publications Services (Post 940714). August 42pp. 9609100247. 83600:307, 1996. 300pp. 9609030364. 89546:001.

This journal includes all formal reports in the NUREG series See NUREG-0540,V18 N05 ab* tract.

prepared by the NRC staff and contractors, proceedings of con-ferences and workshops, grants, and international agreement HUREG-0654 ROI S03: CRITERIA FOR PREPARATION AND reports.1he entries in this compilation are indexed for access EVALUATION OF RADIOLOGIG\\L EMERGENCY RESPONSE I

by title and abstract, secondary report number, personal author, PLANS AND PREPAREDNESS N SUPPORT ( c NUCLEAR subject, NRC organization for staff and international agree-POWER PLANTS.Cnteria For Ps rtectae Action Recommenda-ments, contractor, international organization, and licensed facili-tions For Severe Accidents. Daft Report For...

CL.3EL,F.;

ty.

KANTOR F.: MCKENNA.T.: et al. Office of Nuclear Reactor NUREG-0325 R20: U.S. NUCLEAR REGULATORY COMMISSION egulation (Post 941001). #JIy 1996. 19pp. 9608230202.

FEMA-REP-1. 89452:321.

ORGANIZATION CHARTS AND FUNCTIONAL STATEMENTS. July 1,1996.

• Ofc of Personnel (Post 870413).

The Nuclear Regulatory Commission (NRC) and the Federal July 1996. 68pp. 9608050055. 89244:273.

Emergency Management Agency (FEMA) have added 9upple-Functional statements and organization charts for the U.S.

ment 3 to NUREG-0654/ FEMA-REP-1, Revision 1, whig pro-Nuclear Regulatory Commission offices, divisions, and branches vides guidance for development of protective action recommen-are presented.

dations for the public for severe reactor accidents involving actual or projected core damage with the potential for loss of NUREG-0325 R21: U.S. NUCLEAR REGULATORY COMMISSION containment. Studies of severe reactor accidents and their con-ORGANIZATION CHARTS AND FUNCTIONAL sequences since the issuance of NUREG-0354/ FEMA-REP 1, STATEMENTS. August 19, 1996.

• Ofc of Personnel (Post Revision 1, have led the NRC staff to conclude that the pre-870413). August 1996. 68pp. 9609100243. 89609:235.

ferred initial protective action for a severe (core damage) acci-See NUREG-0325,R20 abstract.

dent is to evacuate promptly rather than to thelter the popula-NUREG-0525 V02 R04: SAFEGUARDS

SUMMARY

EVENT LIST tion near the plant, barring any constraints to evacuation. The (SSEL). January 1,

1990 Through December 31, 1995.

guidance in this document is intended to update and simplify FADDEN,M.A.: YARDUMIAN,J. Operations Branch. July 1996.

the decisionmaking process for protective actions for severe re-109pp. 9608060289. 89262:238.

actor accidents given in Appendix 1 to NUREG 0654/ FEMA-The Safeguards Summary Event List provides brief summa-REP-1, Revision 1.

ries of hundreds of safeguards related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory NUREG-0725 R11: PUBLIC INFORMATION CIRCULAR FOR Commission. Events are desenbed under the categories: Bomb-SHIPMENTS OF IRRADIATED REACTOR FUEL

• Office of related, intrusion, Missing / Allegedly Stolen, Transportation-relat-Nuclear Material Safety & Safeguards. July 1996. 32pp.

ed, Tampering / Vandalism, Arson, Firearms-related, Radiological 9608210216. 89420:305.

Sabotage, Non-radiological Sabotage, and Miscellaneous. Be-This circular has been prepared to provide information on the cause of the public interest, the Miscellaneous category also in-shipment of irradiated reactor fuel (spent fuel) subject to regula-cludes events reported involving source material, byproduct ma-tion by the Nuclear Regulatory Commission (NRC), and to meet I

terial, and natural uranium, which are exempt from safeguards the requirements of Public Law 96-295. The report provides a requirements. Information in the event descriptions was ob.

bnef desenption of NRC authonty for certain aspects of trans-tained from official NRC sources.

porting spent fuel. It provides descriptive statistics on spent fuel NUREG-0540 V18 N05: TITLE LIST OF DOCUMENTS MADE shipments regulated by the NRC from 1979 to 1995. It also lists PUBLICLY AVAILABLE. May 1-31, 1996.

• Division of Freedom detailed highway and railway segments used within each state of Information & Publications Services (Post 940714). July 1996.

from January 1,1993, through December 31,1995.

367pp. 9608050217. 89245:233.

1

2 Main Citations and Abstracts t

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NUREG-0750 V43 NOS: NUCLEAR REGULATORY COMMISSION information in this publication will be widely disseminated to ISSUAN,CES FOR MAY 1996.

• Division of Freedom of informa-managers and employees engaged in activities licensed by the terv 4 rublications Services (Post 940714). July 1996. 30pp.

NRC, so that actions can be taken to improve safety by avoid-06kO60271. 89258:145.

ing future violations similar to those described in this publica-Legal issuances of the Commission, the Atomic Safety and Li-tion.

censing Board Panel, the Administrative Law Judges, and NRC Program Offices are presented.

NUREG-0940 V15 N1 P3: ENFORCEMENT ACTIONS: SIGNIFI-CANT ACTIONS RESOLVED MATERIAL NUREG-0750 V43 N06: NUCLEAR REGULATORY COMMISSION LICENSEES. Semiannual Progress Report. January-June 1996.

• ISSUANCES FOR JUNE 1996.

• Dwision of Freedom of Infor*

Ofc of Enforcement (Post 870413). August 1996. 350pp.

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

9609100230. 89602:001.

120pp. 9609200257. 89729:124.

This compilation summarizes rignificant enforcement actions See NUREG-0750,V43,N05 abstract.

that have been resolved during the period (January. June NUREG-0837 V16 N02: NRC TLD DIRECT RADIATION MONI.

1996) and includes copies of letters, Notices, and Orders sent 2

TORING NETWORK. Progress Report.

(April-June,1996).

by the Nuclear Regulatory Commission to material licensees STRUCKMEYER,R. Regicn 1 (Post 820201). August 1996, with respect to these enforcement actions. It is anticipated that 248pp. 9609200268. 89727:134.

the information in this publication will be widely disseminated to This report provides the status ano results of the NRC Ther.

managers and employees engaged in activities licensed by the moluminescent Dosimeter (TLD) Direct Radiation Monitonng NRC, so that actions can be taken to improve safety by avoid-Network. It presents the radiation levels measured in the vicinity ing future violations similar to those described in this publica-of NRC licensed facilities throughout the country for the second tion.

4"8"*' U' 199 NUREG-1272 V09 N01: OFFICE FOR ANALYSIS AND EVALUA-NUREG-0933 S20: A PRIORITIZATION OF GENERIC SAFETY TION OF OPERATIONAL DATA.1994-FY 95 Annual Report -

ISSUES. EMRIT,R. Division of Engineering Technology (Post Reactors.

• Office for Analysis & Evaluation of Operational 941217). July 1996. 232pp. 9608050226. 89245:001, Data, Director. July 1996. 306pp. 9609100257. 89600:001.

1he report presents the safety prionty ranking for <;eneric This annual report of the U.S. Nuclear Regulatory Commis-safaty issues related to nuclear power plants. The prpose of sion's Office for Analysis and Evaluation of Operational Data I

these rankings is to assist in the timely and efficYnt allocation (AEOD) describes activities conducted during CY 1954 and FY of NRC resources for the resolution of those safety issues that 1995. The report is published in three parts. NUREG-1272, Vol.

have a significant potential for reducing risk. The safety priority 9, No.1, covers power reactors and presents an overview of rankings are HIGH, MEDIUM, LOW, and DROP, and have been the operating experience of the nuclear power industry from the assigned on the basis of risk significance estimates, the ratio of NRC perspective, including comments about the trends of some risk to costs and other impacts estimated to result if resolution key performance measures. The report also includes the princi-of the safety issues were implemented, and the consideration of pal findings and issues identified in AEOD studies over the past uncertainties and other quantitative or qualitative factors. To the year and summanzes information from such sources as licensee extent practical, estirnates are quantitatwe.

event reports, diagnostic evaluations, and reports to the NRC's NUREG 0936 V15 N01:

NRC REGULATORY Operations Center. NUREG-1272, Vol. 9, No. 2, covers nuclear AGENDA. Semiannual Report. January-June 1996.

• Division of materials and presents a review of the events and concerns

)

Freedom of Information & Publications Services (Post 940714),

during 1993 associated with the use of licensed material in non-

{

AugJst 1996 509p. 9609100233. 89601:267.

reactor applications, such as personnel overexposures and

)

The NRC Reg'ulatory Agenda is a compilation of all rules on medical misadministrations. Both reports also contain a discus-which the NRC has recently completed action, or has proposed sion of the incident Investigation Team program and summarize l

action, or is considering action, and all petitions for rulemaking both the incident investigation Team and Augmented inspection 1

which have been received by the Commission and are pending Team reports. Each volume contains a list of the AEOD reports disposition by the Commission. The Regulatory Agenda is up, issued from 1980 through 1993. NUREG 1272, Vol. 9 No. 3, dated and issued semiannually.

covers technical training and presents the activities of the Tech-nical Training Center in support of the NRC s mission.

NUREG-0940 V15 N1 P1: ENFORCEMENT ACTIONS: SIGNIFI-1 CANT ACTIONS RESOLVED INDIVIDUAL NUREG 1307 R06:

REPORT ON WASTE BURIAL ACTIONS. Semiannual Progress Report, January-June 1996.

• CHARGES. Escalation Of Decommissioning Waste Disposal i

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

Costs At Low-Level Waste Burial Facilities.

• Dwision of Regula-9609100232. 89603:001.

tory Applications (Post 941217). September 1996. 66pp.

This compilation summanzes significant enforcement actions 9609200324. 89726:236.

that have been resolved during the period (January - June One of the requirements placed upon nuclear power reactor 1996) and includes copies of Orders and Notices of Violation licensees by the U.S. Nuclear Regulatory Commission (NRC) is sent by the Nuclear Regulatory Commission to individuals with for the licensees to periodically adjust the estimate of the cost respect to these enforcement actions. It is anticipated that the of decommissioning tneir plants, in dollars of the current year, information in this publication will be widely disseminated to as part of the process to provide reasonable assurance that managers and employees engaged in activities licensed by the adequate funds for decommissioning will be available when NRC. The Commission believes this information may be useful needed. This report, which is scheduled to be revised periodi-to licensees in making employment decisions.

cally, contains the development of a formula for escalating de-commissioning cost estimates that is acceptable to the NRC, NUREG-0940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFl*

and contains values for the escalation of radioactive waste CANT ACTIONS RESOLVED REACTOR burial costs, by site and by year. The licensees may use the for-LICENSEES. Semiannual Progress Report. January-June 1996.

• mula, the coefficients, and the burial escalation from this report j

Ofc of Enforcement (Post 870413). August 1996. 266pp.

in their escalation analyses, or they may use an escalation rate 9609100251. 89601:001-at least equal to the escalation approach presented herein.

This compilation summanzes significant enforcement actions that have been resolved during the period (January June NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION IN-1996) and includes copies of letters, Notices, and Orders sent FORMATION DIGEST.1996 Edition. GARVER,M. Division of by the Nuclear Regulatory Commission to reactor licensees with Budget & Analysis (Post 890205). July 1996. 138pp.

respect to these enforcement actions. It is anticipated that the 9609030260. 89545:001.

4 Main Citations and Abstracts 3

The Nuclear Regulatory Commission Information Digest NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT (digest) provides a summary of information about the U.S. Nu.

DECOMMISSIONING OF THE SHIELDALLOY METALLURGI-clear Regulatory Commission (NRC), NRC's regulatory responsi-CAL CORPORATION. CAMBRIDGE, OHIO, FACILITY. Docket No.

bilities, NRC licensed activities, and general inforrnation on do-40-8948, License No. SMB 1507. WADE M.C.; BLASING,T.J.;

mestic and wuridwide nuclear energy. The digest, published an-CURTIS,A H.; et al. Oak Ridge National Laboratory. July 1996.

nually, is a compilation of nuclear and NRC-related data and is 249pp. 9608060185. 89260:063.

designed to provide a quick reference to major facts about the Shieldalloy Metallurgical Corporation holds a license from the tgency and the industry it regulates. In general, the data cover U.S. Nuclear Regulatory Commission (NRC) for the possession 1975 through 1995, with exceptions noted. Information on gen-of source material at its Cambndge, Ohio, facility. The source erating capacity and average capacity factor for operating U.S.

material is in the form of slag and is located in two piles that contain a total of 546,000 metric tons (606,000 tons) of materi-commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the al. The piles also contain chemical contaminants that may re-licensee. This information is reviewed by the NRC for consisten-quire remediation. Shieldalloy proposed to stabilize, cap, and cy only and no independent validation and/or verification is per-grade the slag piles as part of decommissioning the site and a

formed.

terminating the NRC heense. The DEIS evaluates radiological and nonradiological impacts associated with the proposed NUREG-1423 V06: A COMPILATION OF REPORTS OF THE AD-adon and M ahemaWe achons, including no action. Impacts VISORY COMMITTEE ON NUCLEAR WASTE. July 1995 - June am assessM for tam use, soceomes and Wal m 1996.

• Advisory Committee on Nuclear Waste. August 1996.

sources, geology, air quality, water quality and wetlands, human 54pp. 9609030264. 89547:283.

health, and biological resources. The staff concludes that the environmental impacts of the on-site and the off-site disposal al-This compilation contains 8 reorts issued by the Advisory ternatives are not significant if mitigation as described is carried Committee on Nuclear Waste (ALMV) dunng the eighth year of out and that there is no obviously superior attemative. A cost its operation. The reports were submitted to the Chairman and benefit analysis shows that the proposed action is less costly Commissioners of the U.S. Nuclear Regulatory Commission. All than all other attematives except no action. The no-action alter-reports prepared by the Committee have been made available native has no economic benefits. The on-site disposal altema-to the public through the NRC Public Document Room, the U.S.

tives have identical economic benefits, and the off-site disposal Library of Congress, and the internet at http://www.nrc. gov /

alternative has the greatest associated economic benefits to ACRSACNW.

local residents.

NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLE-ALPHA MODE CONTAINMENT FAILURE AND A REVIEW OF MENTING ALTERNATIVE TEMPERATURE-TIME CURVE FOR THE CURRENT UNDERSTANDING OF BROADER FUEL-TESTING THE FIRE RESISTANCE OF BARRIERS FOR NU-COOLANT INTERACTION ISSUES. Report Of The Second CLEAR POWER PLANT APPLICATIONS. COOPER,LY.;

Steam Explosion Review Group Workshop. BASU S. Division of STECKLER K.D. National Institute of Standards & Technology Systems Technology (Post 941217). GINSBERG,T. Brookhaven (formerly National Bureau of Standa.

• Office of Nuclear Reac.

tor Regulation (Post 941001). August 1996. 125pp.

National Laboratory. August 1996. 200pp. 9608230217.

9609200310. 89729:001.

89450 R Advances in fire science over the past 40 years have offered This report summarizes the review and evaluation by experts the potential for developing technically sound afternative tem-of the current understanding of the molten fuel-coolant interac' perature-time curves for use in evaluating fire barriers for areas tion (FCl) issues covenng the complete spectrum of interac-where fire exposures can be expected to be significantly differ-tions, i.e., from mild quenching to very energetic interactions in-ent than the ASTM E-119, standard temperature-time exposure.

ciuding those that could lead to the alpha-mode containment This report summarizes the development of the ASTM E-119, failure. The experts' review and evaluation took place in the standard temperature-time curve, and the efforts by the federal form of a Second Steam Explosion Review Group (SERG-2) government and the petrochemical industry to develop alterna-i Workshop, held in Annapolis, Maryland, on June 15 and 16, tive fire endurance curves for specific applications. The report 1995. The first such workshop (SERG-1) took place in 1985.

also provides a framework for the development of alternative Extensive discussions took place at the SERG-2 workshop on curves for application at nuclear power plants. The staff has the alpha-mode failure issue, based on the expe ts' responses concluded that in view of the effort necessary for the develop-to the questions raised, and consensus opinions on the status ment of nuclear power plant specific temperature-time curves, of resolution of the issue emerged from the discussions. Of the such curves are not a viable approach for resolving the issues cleven experts polled, all but two concluded that the alpha.

conceming Thermo-Lag fire barriers. However, the approach mode failure issue was resolved from a risk perspective, mean.

may be useful to licensees in the development of performance-ing that this mode of failure is of very low probability, that it is of based fire protection methods in the future.

little or no significance to the overall risk from a nuclear power NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLE-plant, and that any further reduction m residual uncertainties is AR POWER PLANTS. BAJWA,C.S.; WEST,K.S. Office of Nucle-1 not likely to change the probability in an appreciable manner. To ar Reactor Regulation (Post 941001). July 1996. 55pp.

a lesser degree, discussions also took place on the broador FCI 9608230207. 89455:045.

Issues such as mild quenching of core melt during non-explo-Nuclear power plants are divided into separate fire areas by sive FCl, and shock loading of lower head and ex-vessel sup-fire-rated structural barriers. Fire-rated penetration seals are in-port structures arising from explosive localized FCis. These stalled to seat certain openings in these barriers. The seals latter issues are relevant with regard to determining the efficacy maintain the fire-resistive integnty of the barriers cnd provide of certain accident management strategies for operating reac-reasonable assurance that a fire will be confined to the area in tors as well as for advanced light water reactors. The experts which it started. The U.S. Nuclear Regulatory Commission con-reviewed the status of understanding of the FCI phenomena in ducted a comprehensive technical assessment of penetration the context of these broader

• e identified residual uncer.

seals to address reports of potential problems, to determine if d

tainties in the understanding, recommended further re.

there were any problems of safety significance, and to deter-search (both experimental and anwytical) to reduce the uncer.

mine if NRC requirements, review guidance, and inspection pro-tainties.

cedures are adequate. Tt.e staff did not find plant-specific prob-lems of safety significance or concerns with generic implica-

4 Main Citations and Abstracts tions. The staff concluded that the general condition of penetra.

NUREG/CR-4219 V12 N1: HEAVY-SECTION STEEL TECHNOL-tion seal programs in industry is satisfactory, The staff also con-OGY PROGRAM. Semiannual Progress Report For October cluded that actions it had taken in 1988 and 1994 to address 1994 - March 1995. PENNELL,W.E. Oak Ridge National Labora-potential penetration seal problems increased industry aware-tory. July 1996, 146pp. 9608070004. ORNL/TM-9593.

ness of such problems and resulted in more thorough surveib 89285:040.

lances, maintenance, and corrective actions. These previous The Heavy Section Steel Technology (HSST) Program is con-staff actions, together with continued licensee upkeep of exist-ducted for the U.S. Nuclear Regulatory Commission (NRC) by ing penetration seal programs and continued NRC inspections, Oak Ridge National Laboratory (ORNL). The program focus is are adequate to maintain public health and safety.

on the development and validation of technology for the as-sessment of fracture-prevention margins in commercial nuclear NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' reactor pressure vessels. The HFST Program is organized in MEETING ON CRACKING IN LWR RPV HEAD seven tasks: (1) program management, (2) constraint effects PENETRATIONS. Held At ASTM Headquarters, Philadelphia.

analytical development and validation. (3) evaluation of cladding Pennsylvania, May 2 3, 1995. PUGH.C.E.; RANNEY,S.J. Oak effects (4) ductile to cleavage fracture mode conversion, (5)

Ridge National Laboratory. July 1996. 304pp. 9608210221.

fracture analysis methods development and applications, (6)

ORNL/TM-13187. 89420:001.

material property data and test methods, and (7) integration of This report contains 17 papers that were presented in four results into a state-of-the-art methodology. The program tasks sessior.s at the IAEA Specialists' Meeting on Cracking in LWR have been structured to place emphasis on the resolution frac-RPV Head Penetrations held at ASTM Headquarters in Philadel-ture issues with near term licensing significance. Resources to phia on May 2-3, 1995. The papers are compiled here in the execute the research tasks are drawn from ORNL with subcon-order they were presented in the sessions, and they relate to tract support from universities and other research laboratories.

operational observations, inspection techniques, analytical mod-Close contact is maintained with the sister Heavy-Section Steel eling, and regulatory control The goal of the meeting was to Irradiation Program at ORNL with related research programs allow intemational experts to review experience in the field of both ir. the United States and abroad. This report provides an ensunng adequate performance of reactor pressure vessel overview of principal developments in each of the seven pro-(RPV) heads and penetrations. The emphasis was aimed at gram tasks from October 1994 - March 1995, better understanding of behavior of reactor component maten-als, to provide guidance and recommendations assuring reliabil.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACK-ity, adequate performance, and directions for further investiga-ING IN LIGHT WATER REACTORS. Semiannual Report. April tions. The international nature of the meeting is illustrated by 1995 - December 1995. CHOPRA.O.K.; CHUNG.H.M.;

the fact that papers were presented by researchers from 10 GRUBER,E.E.; et al. Argonne National Laboratory. July 1996.

countries. There were technical experts pre 2ent from other 87pp. 9608210264. ANL-96/1. 89422:253.

countnes who participated in discussions of the results present-This report summarizes work performed by Argonne National ed. The IAEA issued a Working Material version of the meeting Laboratory on fatigue and environmentally assisted cracking papers (IAEA IWG-LMNPP 95/1), and this present document in.

(EAC) in light water reactors (LWRs) from April 1995 to Decem-corporates the final version of the papers as received from the ber 1995. Topics that have been investigated include (a) fatigue authors.

of carbon and low-alloy steel used in reactor piping and pres-sure vessels (b) EAC of Alloys 600 and 690, and (c) irradiation-NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/

assisted stress corrosion cracking (IASCC) of Type 304 SS. Fa-ASME SYMPOSIUM ON VALVE AND PUMP TESTING. Held At tigue tests were conducted on femtic steels in water that con-The Hyatt Regency Hotel, Washington,DC, July 15-18, 1996.

• tained various concentrations of dissolved orygen (DO) to de-Office of Nuclear Reactor Regulation (Post 941001).

• American termine whether a slow strain rate applied during different por-Society of Mechanical Engineers. July 1996. 700pp.

tions of a tensile-loading cycle are equally effective in de :reas-9608140271.89352:001.

ing fatigue life. Crack growth-rate tests were conducted ori com-The 1996 Symposium on Valve and Pump Testing, jointly pact-tension specimens from several heats of Alloys NO and sponsored by the Board on Nuclear Codes and Standards of 690 in simulated LWR environments. Effects of fluoride-ion con-the American Society of Mechanical Engineers and by the Nu-tamination on susceptibility to intergranular cracking of high-j clear Regulatory Commission, provides a forum for the discus-and commercial-purity Type 304 SS specimens from control-sion of current programs and methods for inservice testing and blade absorber tubes irradiated in boiling water reactors were motor-operated valve testing at nuclear power plants. The sym-determined in sluw-strain-rate-tensile tests at 288 degrees C.

posium also provides an opportunity to discuss the need to im-Microchemical changes in the specimens were studied by Auger prove that testing in order to help ensure the reliable perf arm-electron spectroscopy and scanning electron microscopy to de-ance of pumps and valves. The participation of industry repre-termine whether trace impurity elements may contribute to sentatives, regulators, and consultants results in the discussion IASCC of these materials.

j of a broad spectrum of ideas and perspectives regarding the im-1 provement of inservice testing of pumps and valves at nuclear NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION j

power plants.

INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress 1

Report On Field Experiments At A Humid Region j

NUREG/CR-2800 805: GUIDELINES FOR NUCLEAR POWER Site,Beltsville. Maryland. SCHULZ,R.K. Califomia, Univ. of, Los i

PLANT SAFETY ISSUE PRIORITIZATION INFORMATION DE-Angeles, CA. RIDKY,R.W. Maryland, Univ. of, College Park, MD.

VELOPMENT DALING,P.M.; LAVENDER,J.C. Battelle Memorial O'DONNELL.E. Division of Regulatory Applications (Post Institute, Pacific Northwest Laboratory. July 1996. 237pp.

941217). August 1996. 30pp. 9609030360. 89546:303.

9608050237. PNL-4297. 89243:001.

The project objective is to assess means for controlling waste This is the s&th in a series of reports to document the use of infilt.stion through waste disposal unit covers in humid regions.

a methodology developed by Pacific Northwest Laboratories to Experimental work is being performed in large scale lysimeters calculate, for prioritization purposes, the risk, dose, and cost im-(70'x45'xlO') at Beltsville, MD,and results of the assessment are pacts of implementing resolutions to reactor safety issues applicable to disposal of LLW, uranium mill tailings, hazardous (NUREG/CR-2800, Andrews, et al.,1983). This report contains waste, and sanitary landfills. Three concepts are under investi-the resutts of issue-specific analyses for 34 generic issues. The gation: (1) resistive layer barrier, (2) conductive layer barrier, results are referenced, as one consideration in setting priorities and (3) bioengineering water management. The resistive layer for reactor safety issues, in NUREG-0933, A Pnoritization of Ge-barrier consists of compacied earth (clay). The conductive layer neric Safety Issues.

barrier is a special case of the capillary barrier and it requires a

Main Citations and Abstracts 5

flow layer (e g. fine sandy loam) over a capillary break. As long As part of the U.S. Nuclear Regulatory Commission (NRC) as unsaturated conditions are maintained water is conducted by Standard Review Plan Update and Development Program (SRP-the flow layer to below the waste. This barrier is most efficient UDP), Pacific Northwest National Laboratory droeloped a listing at low flow rates and is thus best placed below a resistive layer of industry consensus codes and standards and other govem-barrier, Such a combination of the resistive layer over the con-ment and industry guidance referred to in regulatory documents.

ductive layer barrier promises to be highly effective provided The SRP-UDP has been completed and tht. SRP-Maintenance there is no appreciable subsidence. Bioengineenng water man Program (SRP-MP) is now maintaining this listing. Besides up-agement is a surface cover that is designed to accommodate dating previous information, Revision 3 adds approximately 80 subsidence. It consists of impermeable panels which ennance run-off and limit infiltration. Vegetation is planted in narrow citations. This listing identifies the version of the code or stand-openings between panels to transpire water from below the ard cited in the regulatory document, the regulatory document, panels. This system has successfully dewatered two lysimeters and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This thus demonstrating that, this procedure could be usod for reme-al action drying out existing water logged disposal sites at listing was developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, Information No-taces, Circulars, Enforcement Manual, Generic Letters, inspec-NUREG/CR-5595 R01: FORECAST: REGULATORY EFFECTS tion Manual. Policy Statements, Regulatory Guides, Standard COST ANALYSIS SOFTWARE MANUAL. Version 4.1.

Technical Specifications cod the Standard Review Plan LOPEZ,B.; SCIACCA.F.W. Science & Engineenng Associates-(NUREG-0800).

Inc.

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

r 9608050060. SEA 95-2755010A1. 89250:001.

NUREG/CR-6163: COMPUTER PROGRAMS FOR THE ACQUISI-The FORECAST program was developed to facilitate the TION AND ANALYSIS OF EDDY CURRENT ARRAY PROBE preparation of the value-impact portion of NRC regulatory analy-DATA. PATE J.R.; DODD.C.V. Oak Ridge National Laboratory.

ses. This PC program integrates the major cost and benefit con-July 1996.186pp. 9608210243. ORNL/TM-13212. 89424:001.

siderations that may result from a proposed regulatory change.

The objective of the improved Eddy Current ISI for Steam FORECAST automates much of the calculations typically needM in a regulatory analysis and thus reduces the time and Generators Tubing program is to upgrade and validate eddy-cur-labor required to perform these analyses. More importantly, its rent inspections, including probes, instrumentation, and data g

g integrated and consistent treatment of the different value impact considerations should help assure comprehensiveness, uniform-and repaired steam generator tubes; to improve defect detec-sty, and accuracy in the preparation of NRC regulatory analyses.

TM current FORECAST version 4.1 has been upgraded from ared thickness variations, denting, probe wobble, tube sheet, the previous version and now includes an uncertainty package tube supports, copper and sludge deposits, even when defect tnd an automatic cost escalation package in addition, it now types and other variables occur in combination; to transfer this explicitly addresses public health impacts, occupational health advanced technology to NRC's mobile NDE laboratory and impacts, onsite property damage, and government costs.

staff. This report documents computer programs that were de-NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE N'JCLEAR veloped for acquisition of eddy-current data from specially-de-POWER INDUSTRY. Annual Summary Of Program Performance signed 16-coil array probes. Complete code as well as instruc-Reports CY 1995.

SILBERNAGEL,M.;

BRICHOUX,J.;

tions for use are provided.

DURBIN.N. Battelle Seattle Research Center. July 1996.96pp.

NUREG/CR-6174 V01: REVISED ANALYSES OF DECOMMIS-9608060285. PNL-11202. 89258:230.

SiONING FOR THE REFERENCE BOILING WATER REACTOR This report summarizes the data from the semiannual reports of fitness-for duty program submitted to the NRC by utilities for POWER STATION.E*fects Of Current Reguir. tory And Other two reporting periods: January 1 through June 30,1995, and Considerations On The Financial Assurance Requirements Of The Decommissioning Rule And...

SMITH.R.I.;

July 1 through December 31, 1995. During 1995, licensees re-ported that they conducted 150,121 tests for the presence of BIERSCHBACH,M.C; KONZEK.G.J.; et al. Battelle Memorial in-illegal drugs and alcohol. Of these tests, 1,476 (.98%) were stitute, Pacific Northwest Laboratory. July 1996. 120pp.

confirmed posihve. Positive test results varied by category of 9608210240. PNL 9975. 89428:00t.

test and category of worker. The majonty of positive test results With the issuance of the Decommissioning Rule in 1988, nu-(1,122) were obtained through pre-access testing. Of tests con-clear power plant licensees are required tn submit to the U.S.

ducted on workers having access to the protected area,180 Nuclear Regulatnry Commission (NRC) decommissioning cost were positive from random testing and 139 were positive from estimates for review. This reevaluation study provides some of for-cause testing. Follow-up testing of workers who had previ-the needed bases documentation to the NRC staff that will ously tested positive resulted in 35 positive tests. For-cause assist them in assessing the adequacy of the licensee submit-testing resulted in the highest percentage of positive tests; tals. This report presents the results of a review and reevalua-about 18% of for cause tests were positive. In comparison, tion of the PNL 1980 decommissioning study of the WNP-2 nu-1.41% of pre-access tests and.27% of random iests were posi-clear p ent for the DECON, SAFSTOR, and ENTOMB decom-tive. Positive test rates also variad by category of worker. When missioning alternatives. These alternati.es now include an initial all types of tests are combined (pre-access, random, for-cause 5-7 year period dunng which the spent fuel is stored in the and follow-up testing), short-term contractor personnel had the spent fuel pool, prior to beginning major disassembly or ex-highest positive test rate at 1.44%. Licensee employees and tended safe storage of the plant. This report also includes NRC long-term contractors had lower combined positive test rates consideration that decommissioning activities leading to termi-(.34% and.40%, respectively). Of the substances tested, mari-nation of the nuclear license be completed within 60 years of juana was responsible for the highest percentage of positive final reactor shutdown, considera6on cf packaging and disposal test results (53.08%), followed by cocaine (24.24%) and alcohol requirements for Greator-Than-Class C low-level waste, and re flects all costs in 1993 dollars. Sensitivity of the total license NUREG/CR-5973 P93: CODES AND STANDARDS AND OTHER termination cost to the disposal at different lowlevel radioactive GUIDANCE CITED IN REGULATORY DOCUMENTS.

waste disposal sites, and to different depths of contaminated NICKOLAUS,J.R.; BOHLANDER K.L Battelle Memorial Institute, concrete surface removed, is also examined.

Pacific Northwest Laboratory. August 1996.

555pp.

9609030269. PNL-8462. 89548:001.

6 Main Citations and Abstracts NUREG/CR-6174 V02: REVISED ANALYSES Or DECOMMIS.

shallow notch SE(B) specimens, with and without side grooves, SiONING FOR THE REFERENCE BOILING WAhr. REACTOR Crack front conditions are characterized in terms of J-Q trajec-POWER STATION Effects Of Current Regulatory And Other tories and the constraint scalira model for cleavage fracture Considerations On The Financial Assurance Requirements Of toughness proposed previously by Dodds and Anderson. The 3-The Decommissioning Rule And....

SMITH,R.I.;

D computational results imply that a significantly less strict size /

BIERSCHBACH,M.C; KONZEK,G.J.; et al. Battelle Memonal in-deformation limits indicated by previous plane-strain computa-statute, Pacific Northwest Laboratory. July 1996 252pp.

tions, relative to the limits indicated by previous plane strain 9608210245. PNL-9975. 89422:001.

computations, is needed to maintain small-scale yielding condi-With the issuanca of the Decommissioning Rule in 1988, nu-tions at fracture by a stress-controlled cleavage mechanism in clear power plant licensees are requved to submit to the U.S.

deep notch SE(B) and C(T) specimens. Additional new results Nuclear Regulatory Commission (NRC) decommissioning cost made available from the 3-D analyses also include revised r/-

estimates for review. This reevaluation study provides some of plastic factors for use in experimental studies to convert meas-the needed bases documentation to the NRC staff that will ured work quantities to thickness average and maximum (local) assist them in assessing the adequacy of the licensee submit-J-values over the crack front.

tals. This report presents the results of a review and reevalua-tion of the PNL 1980 decommissioning study of the WNP 2 nu-NUREG/CR-6357: EVALUATION AND FIELD VALIDATION OF clear plant for the DECON, SAFSTOR, and ENTOMB decom-EDDY-CURRENT ARRAY PROBES FOR STEAM GENERATOR missioning attematives. These attematives now include an initial TUBE INSPECTION. DODD,C.V.; PATE,J.R. Oak Ridge National 5-7 year penod dunng which the spent fuel is stored in the Laboratory. July 1996. 86pp. 9608210247. ORNL/TM-13213.

spent fuel pool, prior to beginning major disassembly or ex-89424:189.

tended safe storage of the plant. This report also includes NRC The objective of the Improved Eddy-Current ISI for Steam consideration that decommissioning activities leading to termi-Generator Tubing program is to upgrade ard validate eddy-cur-nation of the nuclear license be completed within 60 years of rent inspections, including probes, instrumentation, and data final reactor shutdown, consideration of packaging and disposal processing techniques for inservice inspection of new, used, requirements for Greater Than-Class C low-level waste, and re-and repaired steam generator tubes; to improve defect detec-flects all costs in 1993 dollars. Sensitivity of the total heense tion, classification and characterization as affected by diameter termination cost to the disposal at different low-level radioactive and thickness variations, denting, probe wobble, tube sheet, waste disposal sites, and to different depths of contaminated tube supports, copper and sludge deposits, even when defect concrete surface removed, is also examined.

types and other variables occur in combination; to transfer this NUREG/CR-6189: A SIMPLIFIED MODEL OF AEROSOL RE-advanced technology to NRC's mobile NDE laboratory and MOVAL BY NATURAL PROCESSES IN REACTOR CONTA!N-staff. This report desenbes the design of spccialized high-speed MENTS. POWERS.D.A.: WASHINGTON,K.E. Sandia National Woil eddy-current array probes. Both pancake and rejection Laboratones. BURSON.S.B.; et al. Division of Systems Technol-coils are considered. Test results from inspections using the ogy (Post 941217). July 1996. 263pp. 9608060182. SAND 94-probes in working steam generators are given. Computer pro-0407. 89278:001.

grams developed for probe calculations are also supplied.

Simplified formulae are developed for estimating the aerosol NUREG/CR-6374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR decontamination that can be achieved by natural proces,ses in RADIOLABELED ANTIBODIES AND RELATED ISSUES.

the containments of pressurized water reactors and in the KAURIN,D.G.; CARSTEN,A.L; et a!. Brookhaven National Labo-drywells of boiling water reactors under severe accident conds-tions. These simplified formulae were derived by correlation of ratory. BARBER,D.E. Minnesota, Univ. oi Minneapolis, MN' results of Monte Carlo uncertainty analyses of detailed models Au9ust 1996. 176PP' 96091n02/7. BNL-NUREG-52476-i 8

of aerosol behavior under accident conditions. Monte Carlo un-adi abeled antibodies (RABs) are bei"9 developed and certainty analyses of decontamination by natural aerosol proc-esses are reported for 1000, 2000, 3000, and 4000 MW(th) used in medical in. aging and therapy in rapidly increasing num-pressunzed water reactors and for 1500, 2500, and 3500 bers. There are concerns about the radiation exposure of care.

MW(th) boiling water reactors. Uncertainty distributions for the givers and the general public from treated patents. The magni-tude of this hazard is closely re!ated to the RABs' whole-body decontamination factors and decontamination coefficients as functions of time were developed in the Monte Carlo analyses effective half-life (T(e)). Data on whole-body effective half-lives were calculated from external dose rates obtained from attend-by considering uncertainties in aerosol processes, material properties, reactor geometry, and severe accident progression.

ing physicians and radiation safety officers at participating insts-tutions. Calculations of T(e)s were made using exponential re-Phenomenological uncertainties examined in this work included uncertainties in aerosol coagulation by gravitational collision, gression analyses of data from patents receiving single and Brownian diffucion, turbulent diffusion, and turbulent inertia. Un-multiple administrations. These data were analyzed on the basis certainties in aerosol deposition by gravitational settling, thermo.

of age, sex, isotope tabel, radiation energy, antibody type, dis-ease treated, method of administration, and number of adminis-phoresis, diffusiophoresis, and turbulent diffusion were exam-trations. The effective half.hfe in the blood did not correlate with ined. Electrostatic charging of aerosol particles in severe acci-the T(e). The values of T(e) varied by a factor of two for pa-dents is discussed. Median (50 percentile),90, and 10 percent-ile values of the uncortainty distributions for effective decon-tients taking the same RAB. A single exponential clearance famination coefficients were correlated with time and reactor rate, compared with a bi-exponential clearance rate, provides an thermal power. These correlations constitute a simphfied model adequate fit for 95% of the data sets tested.

that can be used to estimate the decontamination by natural NUREG/CR-6375: STRAIN RATE AND INERTIAL EFFECTS ON aerosol processes at three levels of conservatism. Example ap-IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECl-plications of the simpbfied model are desenbed.

MENTS. VARGAS,P.M.; DODDS.R.H. Illinois, Univ. of, Urbana, NUREG/CR-6317: NUMERICAL INVESTIGATION OF 3-D CON.

IL. June 1996. 27pp. 9608060180. 89258:203.

STRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND When the seventy of impact loads is sufficient to produce C(T'. SPECIMENS. NEVALAINEN.M. Technical Research Centre large inelastic deformations, the assessment of crack-tip condi-of Finland (VTT). DODDS.R.H. lilinois, Univ. of, Urbana, IL July tions must include the effects of plasticity, strain rate and iner-1996. 56pp. 9608230213. 89455:100.

tia. This work examines the interaction of impact loading, inelas-This investigation employs 3-D nonhnear finite element analy-tic material deformation and rate sensitivity with the goal of im-ses to conduct an extensive parametric evaluation of crack front proving the interpretation of ductile fracture toughness values stress tnaxiality for deep notch SE(B) and C(T) specimens and measured under dynamic loading. Three-dimensional, nonlinear

Main Citations and Abstracts 7

dynamic analyses are performed for SE(B) fracture specimens at five sites and an application of the data management system (a/W = 0.5,0.15,0.0725) subjected to impact loading. Loading for data not associated with detector systems.

rates obtained in conventional drop tower tests (impact load-hne velocities of = 6 m/sec)are applied in the analyses. Strains at NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR key locations on the specimens and the support reactions (ap.

TUBING SAMPLES. DODD,C.V. Oak Ridge National Laboratory.

plied load) are extracted from the analyses to assess the accu-July 1996,64pp. 9608210230. ORNL/TM-13206. 89423:282.

racy of static formulas commonly used to estimate applied J The objective of the improved Eddy Current ISI for Steam values. Inertial offects on the applied J are quantified by exam-Generators program is to upgrade and validate eddy-current in-ining the acceleration component of J evaluated through a spections, including probes, instrumentation, and data process.

domain integral procedure.

ing techniques for inservice inspection of new, used, and re-NUREG/CR-6388: SEISMIC RESPONSE OF ROCK JOINTS AND paired steam generator tubes; to improve defect detection, clas-JOINTED ROCK MASS.

GHOSH,A.;

HSIUNG.S.M.;

sification and characterization as affected by diameter and CHOWDHURY,A.H. Center for Nuclear Waste Regulatory Analy-thickness variations, denting, probe wobble, tube sheet, tube ses. June 1996. 120pp. 9608060191. CNWRA 95-013.

supports, copper and sludge deposits, even when defect types 89266:191.

and other variables occur in combination; to transfer this ad-Two key technical uncertainties (KTU) that can potentially vanced technology to NRC's mobile NDE laboratory and staff.

pose a high risk of nonentnpliance with the performance objec-This report provides a description of the application of ad-tives of 10 CFR Part 60 are the prediction of (i) thermal-me-vanced eddy-current neural network analysis methods for the chanical effects or' stability of emplacement dnfts and the engi.

detection and evaluation of common steam generator tubing neered barrier system (EBS), and (ii) thermal. mechanical-hydro-flaws including axial and circumferential outer-diameter stress-logical effects on the host rock surrounding the EBS. This final rorrosion cracking and intergranular attack. The report de-report summarizes the research activities concerned with the re-scribes the training of the neural networks on tubing samples petitive seismic load aspect of both these KTUs. This research with known defects and the subsequent evaluation results for project has the dual focus of (i) understanding the key param-unknown samples. Evaluations were done in the presence of ar-eters affecting repository performance under repeated seismic tifacts. Computer programs are given in the appendix.

loading. & 'l (ii) evaluating current capabilities for calculating such effects. Laboratory expenments on Apache Leap tuff joints NUREG/CR-6463: REVIEW GUIDELINES ON SOFTWARE LAN-using cyclic pseudostate and dynamic loads indicate that the GUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY shear strength in the reverse direction of shearing is less than SYSTEMS. Final Report. HECHT,H.; HECHT,H.; GRAFF,S.; et al.

that in the forward direction. But the reverse shear strength pre-SoHaR, Inc. June 1996. 400pp. 9608060265. 89259:001.

dicted by UDEC (versions 1.82 and 1.83) is found to be incon sistent with these findings. Thus, a new joint model is desirable.

Guidelines for the programming and auditing of software writ-Field experiments at Lucky Friday Mine, scale-model experi-ten in high level languages for safety systems are presented.

ments conducted at CNWRA, and information in the literature The guidelines are derived from a framework of issues signifi-show that for excavations subjected to repetitive seismic mo-cant to s3ftware safety which was gathered from relevant tions, accumulation of shear displacement along the joints is the standards and research literature. Language-specific adapta-pnmary mode of deformation for the rock mass. However, the tions of these guidelines are provided for the followi"9 high currently available seismic design procedure for underground level languages: Ada, C/C+ +, Programmable Logic Controller excavations is based on the probable peak particle motion con-(PLC) Ladder Logic, International Electrotechnical Commission cept and does not explicitly take into account of either the time (IEC) Standard 1131-3 Sequential Function Charts, Pascal, and history of individual events or the effects of repetitive seismic PL/M. Appendices to the report include a tabular summary of events. An adequate seismic design methodology is desirable, the guidelines and additional in.ormation on selected languages.

The results of this research project will be used to: conduct pre-licensing reviews, provide guidance to DOE, develop CDMs, NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVAL-support IPA, and provide basis for developing seismic design UATION STUDIES.lmpacts Of Artificial Time History input On methodology.

In-Structure Demand Spectra. SEWELL R.T.; WU.S.C. Risk En-gineering, Inc. July 1996. 315pp. 9608210251, 89421:001.

NUREG/CR4450: CHARACTERIZATION OF CONTAMINATION THROUGH THE USE OF POSITION SENSITIVE DETECTORS This report documents research pertaining to conservatism and variability in seismic risk estimates. Specifcally, it examines AND DIGITAL IMAGE PROCESSING.

SHONKA,J.J.;

whether or not artificial motions produce unrealistic evaluation DEBORD,0.M.; BENNETT,T.E.; et al. Shonka Research Associ" ates, Inc. June 1336. 46pp. 9609200298. 89726:188.

demands, i.e., demands significantly inconsistent with those ex-This report describes development of a segruficant new pected from real earthquakes motions. To study these issues, method for morutonng radioactive surface contamination. A floor two types of artificial motions are considered; (a) motions with monitor prototype has been designed which uses position sensi-smooth response spectra, and (b) motions with realistic vari-tive proportional counter based radiation detectors. The system ations in spectral amplitude across vibration frequency. For both includes a novel operator interface consisting of an enhanced ty es of artifcial motion, time historios are 9enerated to match reality display providing the operator with 3 dimensional con-target spectral shapes. For comparison, empirical motions rep-tours of contamination and background subtracted stereo resentative of those that might result from strong earthquakes

" clicks". The process software saves electronic files of survey in the Eastom U.S. are also considered. The study findings sug-data at very high rates along with time stamped video recording gest that artificial motions resulting from typical simulation ap-and provides ccmpletely documented surveys in a visuahzation proaches (aimed at matching a given target spectrum) are gen-oriented data management system. The data management erally adequate and appropriate in representing the peak-re-system allows simple re-assembly of strips of data that are sponse demands that may be induced in knear structures and taken wrth a knear PSPC and allows visuahzation and treatment equipment responding to real earthquake motions. Also, given of the data using algonthms deveioped for processing images similar input Fourier energies at high-frequencies, levels of input from earth resource satelhtes. This report includes a bnef histo-Fourier energy at low frequencies observed for artdicial motions ry of the development path fc' the floor morutor, a discussion of are substantially similar to those levels noted in real earthquake pcsition senshve proportiorul counter technology, and details motions. In addition, the study reveals specific problems result-concoming the process software, post processor and hardware.

ing from the apphcation of Western U.S. type motions for seis-The last chapter discusses the field tests that were conducted mic evaluation of Eastem U.S. nuclear power plards.

8 Main Citations and Abstracts NUREG/CR-6467: IMPACT OF GROUND MOTION CHARACTER-based on UHS appear to be very close to the more-exact re.

12ATION ON CONSERVATISM AND VARIABILITY IN SEISMIC suits directly computed from scenario earthquakes. The conclu-RISK ESTIMATES. SEWELL,R.T.: TORO,G.R.; MCGUIRE,R.K.

sion does not depend on site configurations and structural char.

Risk Engineering, Inc. July 1996. 151pp. 9608210260.

acteristics. In addition, UH-ISS has composite shapes and may 89423:001.

not correspond to the characteristics possessed in a single This study evaluates the impact of alternative methods in earthquake. The shape is largely affected by the structural prop.

E lead to less biased and more precise estimates of risk. This treatment and charactertzation of earthquake ground motions erty in most cases and can be derived approximately from the on estimates of seismic nsk and its uncertainty. The objectise is corresponding UHS. Motions with smooth spectra, however, will to formulate specific procedures and characterizations that may not have the same damage potential as those of more realistic motions with lagged spectral shapes. As a result UHS-based report focuses on sources of conservatism and uncertainty in analysis may underestiraate the real demands in non-linear risk that may be introduced by simplifications that are made at structural analyses.

the interface of seismic hazard and fragility assessments, par-ticula ly the use of a fixed spectral shape for all magnitudes and NUREG/CR-6491: RECOMMENDATIONS FOR PROTECTING the anchoring of this shape to PGA. Results indicate significant AGAINST FAILURE BY BRITTLE FRACTURE. Category ll And conservatism in the use of standard review spectra at eastern ill Ferritic Steel Shipping Containers With Wall Thickness Great-U.S. Nuclear plant sites and a strong dependence of seismic er Than Four inches. SCHWARTZ,M.W.; FISCHER.L.E. Law-fragility on earthquake magnitude when PGA is used as the rence Livermore National Laboratory. August 1996. 26pp.

ground-motion charactenzation. This study concludes that a 9609030358. UCRL-ID-124583. 89546:334.

single, composite-magnitude spectrum of the appropriate shape This report provides entena for selecting ferritic steels that can generally be used to characterize ground motion for fragility would prevent brittle fracture in Category ll and ill shipping con-assessment without introducing significant bias or uncertainty in tainers with wall thickness greater than four inches. These seismic risk estimates. Results also show that the inelastic or methods are extensions of those previously used for Category 11 elastic spectral acceleration are superior to PGA as spectral an.

and lil containers with wall thickness less than four inches and chors, but they bring only a modest benefit in uncertainty reduc.

Category I containers with wall thickness greater inan four tion because uncertainty in the risk is dominated by the large inches.

uncertainty in the hazard.

NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN NUREG/CR-6468: GROUND MOTION INPUT IN SEISMIC EVAL.

THERMALLY STRIPED PIPE FLOWS.

LEMURE N.;

UATION STUDIES. impacts On Risk Assessment Of Uniform OLVERA.J.R.; RUGGLES A.E. Tennesseo, Univ. of, Knoxville, Hazard Spectra. WU.S.C.; SEWELL.R.T. Risk Engineering. Inc.

TN. December 1995.130pp. 9608050231. 89250:144.

July 1996.130pp. 9608210262. 89423:152.

The bulk temperature measurement of pipe flows with thermal This report documenta research on the subject of conserv.

striping is explored. An experiment is conducted to examine the atism and variability in seismic risk estimates. Particularly, it ex.

feasibility of using temperature measurements on the external amines the effects of the uniform hazard spectrum (UHS) for surface of the pipe to estimate the bulk temperature of the flow.

deriving probabilistic estimates of risk and in-structure demand Simple mixing models are used to characterize the development levels, as compared to the more-exact use of realistic time his-of the temperature profile in the flow. Simple averaging tech-tory inputs (of grven probability) that depend explicitly on magni-niques and Backward Propagating Neural Net are used to pre.

tude and distance. The approach differs significantly from the dict bulk temperature from the extemal temperature measure-conventional procedure in its exhaustive treatment of the ments. Accurate bulk temperatures can be predicted. However, ground-motion threat, and in its more detailed assessment of some temperature distnbutions in the flow effectively mask the component responses to that threat. It is found that the approxi-bulk temperature from the wall and cause significant error in the mate uniform hazard in-structure spectrum (UH-ISS) obtained bulk temperature predicted using this technique.

I l

C-

Secondary Report Number index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER ANL 96/1 NUREG/CR 4667 V21 ORNL/TM-9593 NUREG/CR 4219 V12 N1 BNL NUREG 52476 NUREG/CR-6374 PNL 11202 BSRC-700/96/012 NUREG/CR-5758 V06 NUREG/CR-5758 V06 PNL-4297 CNWRA 95-013 NUREG/CR4388 NUREG/CR-2800 SO5 FEMA-REP-1 PNL-8462 NUREG/CR-5973 R03 NUREGM54 ROI S03 PNL 9975 ORNL/TM-13187 NUREG/CP-0151 NUREG/CR4174 V01 PNL-9975 ORNL/TM-13206 NUREG/CR-6455 NUREG/CR4174 V02 SAND 944407 NUREG/CR4189 ORNL/TM-13212 NUREG/CR4163 ORNL/TM-13213 NUREG/CR4357 SEA 95-2755010A1 NUREG/CR 5595 RO1 UCRL40-124583 NUREG/CR 6491 9

i

l

Personal Author index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.

r SAJWA.C.S.

CHUNG,H.M.

NUREG-1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN POWER PLANTS.

UGHT WATER REACTORS. Semsannual Report. April 1995 December 1995.

BARBER.D.E.

NUREG/CR4374: WHOLE BODY EFFECTIVE HALF-LIVES FOR RA-CONGEL,F.

DIOLABELED ANTIBODIES AND RELATED ISSUES.

NUREG-0654 R01 S03: CRITERIA FOR PREPARATION AND EVALUA.

TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND BASU,5.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN PLANTS.Cnteria For Protective Action Fim..ne.J4mns For Severe ALPHA MODE CONTAINMENT FAILURE AND A REVIEW OF THE Accidents. Draft Report For..

CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT INTERACTION ISSUES. Fleport Of The Second Steam Explosion COO *ER,LY, Review Group Workshop.

NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING BAUM.J.W.

THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-UVES FOR RA-PLANT APPLtCATIONS.

DIOLABELED ANTIBODIES AND RELATED ISSUES.

CURTIS,A.H.

BENNETT T.E.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

NUREG/CR4450; CHARACTERl2ATION OF CONTAMINATION COMMISSIONING OF THE SHIELDALLOY METALLURGICAL THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND CORPORATION, CAMBRIDGE, OHIO, FACluTY. Docket No. 40-8948,Li-DIGITAL IMAGE PROCESSING.

conse No. SMB-1507.

SIERSCHSACH,M.C DAUNG,P.M.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT FOR T :E REFERENCE BO; LING WATER REACTOR POWER SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

STATION. Effects Of Current "legulatory And Other Consderations On The Financal Assurance Requirements Of The Decommissioning Rule DEBORD,D.M.

And....

NUREG/CR4450: CHARACTERl2ATION OF CONTAMINATION NUREG/CR 6174 V02: REVISED ANALYSES OF DECOMMISSIONING THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND FOR THE REFERENCE BOILING WATER REACTOR POWER DIGITAL IMAGE PROCESSING.

STATION. Effects Of Current Regulatory And Other Considerations On The Financial Assurance Hequirement? Cf The Decommissioning Rule DODO,C.V.

And.

NUREG/CR4183: COMPUTER PROGRAMS FOR THE ACQUISITION AND ANALYSIS OF EDDY-CURRENT ARRAY PROBE DATA.

BLASING,TJ.

NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-COMMISSIONING OF THE SHIELDALLOY METALLURGICAL SPECTION.

CORPORATION. CAMBRIDGE, OHIO, FACIUTY. Docket No. 40-8948.Li.

NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR conse No. SMB-1507.

TUBING SAMPLES.

80HLANDER.K.L DODDS.R.H.

NUREG/CR-5973 R03: COC,ES AND STANDARDS AND OTHER GUID.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT ANCE CITED IN REGULATORY OOCUMENTS.

EFFECTS ON BRITTLE FRACTURE IN SE(8) AND C(T) SPECIMENS.

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT BRICHOUX,J.

LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY. Annual Summary Of Prog am Performance Reports CY DURBIN,N.

1995.

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY. Annual Summary Of Program Performance Reports CY 80RSON,$.B.

1995.

NUREG/CR4189: A SIMPUFIED MODEL OF AEROSOL FIEMOVAL BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

EASTERLY,C E.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

CARSTEN,A.L COMMISSIONING OF THE SHIELOALLOY METALLURGICAL NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-UVES FOR RA-CORPORATION. CAMBRIDGE OHIO, FACILITY. Docket No. 404948,U-DIOLABELED ANTIBODIES AND RELATED ISSUES.

conne No. SMB-1507.

CHOPRA,0.K.

EDOELMON,0.K.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG-1543: DRAFT ENVIRONMENTAL (MPACT STATEMENT DE.

LtGHT WATER REACTORS. Semannual Report. April 1995. December COMMISSIONING OF THE SHIELDALLOY METALLURGICAL 1995.

CORPORATION CAMBRIDGE. OHIO, FACILITY. Docket No. 404948,U-conse No. SMB-1507.

CHOWDHURY,A.H.

NUREG/CR-6388: SEISMIC FIESPONSE OF ROCK JOINTS AND JOINT.

EMRIT,R ED ROCK MA*.S.

NUREG-0933 S20: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

11

I 12 Personal Author Index FADDEN,M.A.

KENNEDY,J.E NUREG4525 V02 R04: SAFEGUARDS

SUMMARY

EVENT UST NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-(SSEL). January 1,1990 Through December 31,1995.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION. CAMBRIDGE. OHIO, FACILITY. Docket No. 40-8948.U.

E 6491: RECOMMENDATIONS FOR PROTEC11NG AGAINST conse No. SMB-1507.

FAILURE BY BRITTLE FRACTURE. Category 11 And ill Ferntic Steel KDCH,8 Shipping Containers With Wall ThK:kness Greater Than Four inches.

NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES GARVER.M.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION INFORMA.

Report.

TlON DIGEST.1996 Edition.

KONZEK,G.J.

GHOSHA NUREG/CR-6174 V01: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4388. SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-FOR THE REFERENCE BOluNG WATER REACTOR POWER ED ROCK MASS-STATION Effects Of Current Regulatory And Other ConsideratKms On GINGSE%T.

The Fmancial Assurance Requirements Of The Decommsssonm0 Rule NUREG.1524: A REASSESSMENT OF THE POTENTIAL FOR AN And-ALPHA. MODE CONTAINMENT FAILURE AND A REVIEW OF THE NUREG/CR.6174 V02: REVISED ANALYSEE OF DECOMMISSIONING CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT FOR THE REFERENCE BOLLING WATER REACTOR POWER INTERACTION ISSUES Report Of The Second Steam Explosen STATION Effects Of Current Regulatory And Other Considerations On Review Group Workshop.

The Fmancial Assurance Requirements Of The Decommissonmg Rule And..

GRAFF,8.

NUREG/CR4463. REVIEW GUIDEUNES ON SOFTWARE LANGUAGES LAVENDER,J.C.

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS Final NUREG/CR.2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT Report.

SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

GREEN,W-LEMURE,N.

NUREG/CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER-FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS Final MALLY STRIPED PIPE FLOWS.

Report GRUSER,E.E.

UN,0.

NUREG/CR-4667 V21: ENVIRONMENTAt.LY AS$1STED CRACKING IN NUREG/CR.6463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES UGHT WATER REACTORS. Semiannual Report,' pril 1995 - December FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final A

1995.

Report HAGAN CJV.

LOPEZ,5.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-NUREG/CR-5595 RO1: FORECAST: REGULATORY EFFECTS COST COMM!SSIONING OF THE SHIELDALLOY METALLURGICAL ANALYSIS SOFTWARE MANUAL Vers on 4.1.

CORPORATION. CAMBRIDGE OHIO, FACILITY. Docket No. 40-8948.U-cense No SMB.1507.

MCCOLD,LN.

NUREG 1543. DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-NURE /CR4463: REVIEW GUIDEUNES ON SOFTWARE LANGUAGES COMMISSIONING OF T' ;E SHIELDALLOY METALLURGICAL FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS.Fnal CORPORATION. CAMBRIDGE. OHIO, FACIUTY. Docket No. 40 8948,U.

Report.

conse No. SMB-1507.

~

e HEPLER.M.

MCDUFFIE,P.N.

NUREG 0654 RO1 SO3: CRITERIA FOR PREPARATION AND EVALUA.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND FOR THE REFERENCE BOluNG WATER REACTOR POWER PREPAREDNESS IN SUPPORT OF NUCLEAR POWER STATION. Effects Of Current Regulatory And Other Consideratens On PLANTS.cnteria For Protective Acton Recommendations For Severe The Financial Assurance Requirements Of The Decommissoning Rule Accidents. Draft Report For..

And..

NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING HINS,A.G.

FOR THE REFERENCE BOluNG WATER REACTOR POWER NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN STATION. Effects Of Current Regulatory And Other Consuseratens On UGHT WATER REACTORS. Semiannual Report, April 1995 December The Fm' ancial Assurance Requirements Of The Decomtnissioning Rule 1995.

And....

HSIUNG,S.M.

NUREG CR 88 SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-MCOUIRE,R.K.

NUREG/CR-6467: IMPACT OF GROUND MOTION CHARACTERIZA-TION ON CONSERVATISM AND VARIABluTY iN SEISMIC RISK ES-HUGHES T.H.

TlW TES.

NUREG/CR4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN UGHT WATER REACTORS. Semiannual Report, April 1R95 December MCKENNA,T.

1995.

NUREG.0654 ROI S03: CRITERIA FOR PPEPARATION AND EVALUA.

TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND KANTOR.F.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG4654 R01 S03: CRITERIA FOR PREPARATION AND EVALUA*

PLANTS. Criteria For Protective Action Recommendatons For Severe TlON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND Accidents. Draft Report For..

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS.Criterla For Protectrve Action Nwi..ii -44 ions For Severe MOHSENI,A.

Accidents. Draft Report For--

NUREG-0654 RO1 S03: CRITERIA FOR PREPARATION AND EVALUA-

@SSNER,TA TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN PREPAREDNESS IN SUPPORT OF NUCLEAR POWER UGHT WATER REACTOF.S. Semiannual Report, April 1995 - December PLANTS.Cnteria For Protective Action Recommendations For Severe 1995.

Accidents. Draft Report For.

KAURIN.D.G.

NEVALAINEN M.

NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-UVES FOR RA.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT DIOl.ABELED ANTIBODIES AND RELATED ISSUES.

EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

l Personal Author Index 13 NICKOLAUS,JA SEWELL,R.T.

NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID-NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATION ANCE CITED IN REGULATORY DOCUMENTS.

STUDIES.trnpacts Of Artificial Time History input On in-Structure Demand Spectra.

O'DONNELL,E.

NUREG/CR-6467: IMPACT OF GROUND MOTION CHARACTERl2A-NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO TION ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES-NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-TIMATES.

penments At A Hurmd Region Site,Beltsville, Maryland.

NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION STUDIES. impacts On Risk Assessment Of Uniform Hazard Spectra.

NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER-SHACK,W J.

MALLY STRIPED PIPE FLOWS.

NUREG/CR 4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN PATE,JA gg NUREG/CR4163: COMPUTER PROGRAMS FOR THE ACQUISITION AND ANALYSIS OF EDDY. CURRENT ARRAY PROBE DATA.

SHONKA,J.J.

NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY

• NUREG/CR4450: CHARACTERIZATION OF CONTAMINATION CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND SPECTION.

DIGITAL IMAGE PROCESSING.

PENNELL,W.E.

SILBERNAGEL,M.

NUREG/CR-4219 V12 N1: HEAVY SECTION STEEL TECHNOLOGY NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER PROGRAM. Semiannual Progress Report For October 1994 March INDUSTRY. Annual Summary Of Program Performance Reports CY 1995.

1995.

POWERS.D.A.

SMWHM NUREG/CR4189: A SIMPUFIED MODEL OF AEROSOL REMOVAL BY NUREG/CR-6174 V01: REVISED ANALYSES OF DECOMMISSONING NATURAL PROCESSES IN REACTOR CONTAINMENTS.

FOR THE REFERENCE BOILING WATER REACTOR POWER PUGH,C.E.

STATION. Effects Of Current Regulatory And Other Considerations On NUREG/CP 0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

The Financial Assurance Requirements Of The Decommissioning Rule ING ON CRACKING IN LWR RPV HEAD PENLTRATIONS. Held At And_

ASTM Headquarte s. Pnaladelphia, Pennsyivania, May 2-3,1995.

NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING FOR THE REFERENCE BOluNG WATER REACTOR POWER RANNEY,8.J.

STATION. Effects Of Current Regulatory And Other Considerations On NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

The Financial Assurance Requirements Of The Decomtrussioning Rule ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At And..

ASTM Headquarters. Philadelphia, Pennsylvania, May 2-3.1995.

RIOKYAW, NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CA-4918 V09: CONTROL OF WATER INFILTRATION INTO LIGHT WATER REACTORS. Semiannual Report April 1995 December NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-

1995, penments At A H'imed Region Sete.Beltsville. Maryland SPRUNG,J.L RIZY,C.G.

NUREG/CR4189: A SIMP lFIED MODEL OF AEROSOL REMOVAL BY NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-NATURAL PROCESSES IN REACTOR CONTAINMENTS.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION, CAMBRIDGE OHIO, FACIUTY. Docket No. 40-8948.LL CTECKLER,K D.

cense No. SMB-1507.

NUREG 1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING CUGGLES,A.E.

THE FIRE RESISTANCE OF BARRlERS FOR NUCLEAR POWER NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER-PLANT APPUCATIONS.

MALLY STRIPED PIFE FLOWS.

STRUCKMEYER,R.

b U EG

-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN N

ORK.P t

iLJ 9

f UGHT WATER REACTORS. Semiannual Report, April 1995 December 1995.

TAl,A.

NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final l

N REG

-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN Re g UGHT WATER REACTORS. Semiannual Report, April 1995 - December 1995.

THAGGARD,M.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE.

SCHEXNAYDER,S.M COMMISSIONING OF THE SHIELDALLOY METALLURGICAL l

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-f COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATON CAMBRIDGE, OHIO, FACILITY. Docket No. 40 8948,LL cense No. SMB-1507.

CORPORATON, CAMBRIDGE. OHIO, FACIUTY. Docket No. 40-8948.LL i

conse No. SMB-1507.

TORQGA j

SCHULZ,R.K.

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-1 NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATON INTO TION ON CONSERVATISM AND VARIABlUTY IN SEISMIC RISK ES-NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex.

TIMATES.

i penments At A Humid Region Site Beltsville, Maryland.

p SCHWARTZ,M.W.

NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON lMPACT NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

FAILURE BY BRITTLE FRACTURE. Category 11 And ill Ferrrtic Steel Shipping Containers With Wall Thickness Greater Then Four inches.

WADE,M.C.

NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-SCIACCA.F.W.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL NUREG/CR-5595 RO1: FORECAST: REGULATCGY EFFECTS COST CORPORATON, CAMBRIDGE. OHIO, FACIUTY. Docket No. 40-8948,LL ANALYSIS SOFTWARE MANUAL Version 4.1.

cense No. SMB-1507.

14 Personal Author index WASHINGTON.K.E.

PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

PLANTS.Cntena For Protective Action Recommendations For Severe Accsdents. Draft Report For..

WEISMANN.J.J.

WU.S C.

NUREG/CR4450: CHARACTERl2ATION OF CONTAMINATION

^

NUREG/CR-6466: GROUND MOTION INPUT IN SEISMIC EVALUAflON D G T L IMAGE PR E SI G STUDIEL. impacts Of Artifical Time History input On in-Structure Demand Spect,a.

WENDELBOE,D.

NUREG/CR-6463 REVIEW GUIDELINES ON SOFTWARE LANGUAGES NUREG/CR-6468: GROUND MOTION INPUT IN SEISMIC EF UATION FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final STUDIES impacts On Risk Assessment Of Uniform Hazard Spectra.

Report.

YAROUMIAN,J.

NUREG-0525 V02 R04. SAFEGUARDS

SUMMARY

EVENT LIST NUR 1552: FIRE DARRIER PENETRATION SEALS IN NUCLEAR

@SEU. January 1,1990 Through December 31,1995.

POWER PLANTS.

ZALUZEC,N.J.

WINGERT V.L NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG 0654 ROI S03. CRITERIA FOR PREPARATION AND EVALUA-LIGHT WATER REACTORS. Semaannual RepyLApril 1995 - December TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND 1995.

Subject index This index was developed frorn keywords and word strings in titles and abstracts. During this development period, there will be some todundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcome.

3-D Finite Element Analysis Brittle Fracture NUREG/CR4317: NUPERICAL INVESTIGATION OF 3-D CONSTRAINT NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS-EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST NUREG 1272 V09 Not: OFFICE FOR ANALYSIS AND EVALUATION OF BME NNEtam H And in Nnne Steel OPERATIONAL DATA.1994 FY 95 Annual Report - Reactors.

ppng ntainers With Wan Mness %ater hn % inches.

Aerosol Bulk Temperature NUREG/CR-6189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG/GR 0015. BULK TEMPERATURE MEASUREMENT IN THER.

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

MALLY STRIPED PIPE FLOWS.

Alcohol Testing Data Chemical Augmentation NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG 1524: A REASSESSMENT OF THE POTENTIAL FOR AN INDUSTRY. Annual Summary Of Prograrr Performance Reports CY ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE 1995.

CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT Alpha-Mode Containment Failure INTERACTION ISSUES. Report Of The Second Steam Explosion Review Group Workshop.

NUREG-1524. A REASSESSMENT GF THE POTENTIAL FOR AN ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE Codes And Standards CURRENT UNDERSTANDING OF BROADER FUEL COOLANT NUREG/CR-5973 R03. CODES AND STANDARDS AND OTHER GUID-INTERACTION ISSUES. Report Of The Second Steam Explosion ANCE CITED IN REGULATORY DOCUMENTS.

Renew Group Workshop.

Conservatism UA R4163: COMPUTER PROGRAMS FOR THE ACOUISITION AND ANALYSIS OF EDDY-CURRENT ARRAY PROBE DATA.

NUREG/CR-6357: EVALUATION AND FIELD VALIDATION OF EDDY-TlMATES.

UR T ARRAY PROBES FOR STEAM GENERATOR TUBE IN-Corrosion Fatigue NUREG/CR 4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN Artificiel Time History LIGHT WATER REACTORS. Semiannual Report Apnl 1995 December NUREG/CR-6466: GROUND MOTION INPUT IN SEISMIC EVALUATION 1995.

STUDIESimpacts Of Artificial Time History input On in-Structure Demand Spectra.

Cost Estimate NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION NUREG 1307 R06: REPORT ON WASTE BURIAL CHARGES. Escalation STUDIES Impacts On Risk Assessment Of Uniform Hazard Spectra.

Of Decommissiorung Waste Disposal Costs At Low-Level Waste Bunal Facilities.

Aelsory Committee On Nuclear Waste NUREG-1423 V06: A COMPILATION OF REPORTS OF THE ADVISORY Crack Growth COMMITTEE ON NUCLEAR WASTE. July 1995 June 1996.

NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN BWR A

S. Senuannual %poAApnl 1995 - Decm NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMIS$10NING FOR THE REFERENCE BOILING WATER REACTOR POWER Cracking STATION. Effects Of Current Regulatory And Other Consderations On NUREG/CP4151: PROCEEDINGS OF THE lAEA SPECIALISTS' MEET.

The Financial Assurance Requrements Of The Decommiassorung Rule ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At NUR /CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING STM Headquarters. Philadelphia, PennsyNania. May2 3, 1995.

FOR THE REFERENCE BOILING WATER REACTOR POWER STATION Effects Of Current Regulatory And Other Consad irations On Data Analysis NURFG/CR-6455: DATA ANALYSIS FOR STEAM GENERATOR h Financial Assurance Requrements Of The Decommissiorung Rule TUdlNG SAMPLES.

gegogg,g gy, Decommissioning NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF LIVES FOR RA-NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-DIOLABELED ANTIBODIES AND RELATED ISSUES.

COMMISSIONING OF THE SHIELDALLOY METALLURGICAL CORPORATION, CAMBRIDGE. OHIO, FACILITY. Docket No. 40-8948,U-Boiling Water Reactor cense No. SMB-1507.

NUREG/CR4174 V0t: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING FOR THE REFERENCE BOLLING WATER REACTOR POWER FOR THE REFERENCE BOILING WATER REACTOR TWER STATION Effects Of Current Regulatory And Other Consderations On STATION Effects Of Current Regulatory And Other Considerations On The Financial Assurance Roqurements Of The Decommission #ng Rule The Finanew Assurance Requrements Of The Decommissiorung Rule And_.

And....

NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING FOR THE REFERENCE BOLLING WATER REACTOR POWER FOR THE REFERENCE BOILING WATER REACTOR POWER STATION. Effects Of Current Regulatory And Other Consderations On STATION Effects Of Current Regulatory And Other Consderations On The Financial Assurance Requrements Of The Decommissioning Rule The Financial Assurance Requrements Of The Decommisseorung Rule And..

And....

15

1 16 Subject Index Decontamination Fire Resistence NUREG/CR4189: A SIMPLIFIED MODEL OF ARROSOL REMOVAL BY NUREG 1547: METHODOLOGY FOR DFVELOPING AND IMPLEMENT.

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

ING ALTERNATIVE TEMPERATURF TIME CURVE FOR TESTING Draft Environmental Impact Statement PLAN PPL T NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-COMMISSIONING OF THE SHIELDALLOY METALLURGICAL Fitnese For Duty CORPORATON. CAMBRIDGE.OH'O FACILITY. Docket No. 40-8948.L).

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER conse No. SMB-1507.

INDUSTRY. Annual Summary Of Program Performance Reports CY 1995.

Drug Testing Data NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER II IN STRY. Annual Summary Of Program Performance Reports CY

'g"y'*

g gy g

ING ON CRACKING IN LWR RPV HEAD PENETRATONS. Held At Early Site Permit ASTM Headquarters. PhiladelpNa, Pennsylvania. May 2-3.1995.

NUREG-0654 ROI S03: CRITERIA FOR PREF @ATION AND EVALUA-TON OF RADIOLOGICAL EMERGENCY RcSPONSE PLANS AND Fracture Toughnese PREPAHEDNESS IN SUPPORT OF NUCLEAR POWER NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' MEET.

PLANTS Critena For Protectiva Acton Recommendations For Seve,,,

ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At Accidents. Draft Report For..

ASTM Headquarters. PNiadelpha. Pennsylvania. May 2 3,1995.

NUREG/CR-6317: NUMERICAL INVESTIGATION OF 3 D CONSTRAINT Eddy-Current EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

NUREG/CR4163. COMPUTER PROGRAMS FOR THE ACOUISITION AND ANALYSIS OF EDDY CURRENT ARRAY PROBE DATA.

Fuel-Cooient interaction NUREG/CR-6357: EVALUATION AND FIELD VALIDATION OF EDDY-NUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE SPECTION.

CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT INTERACTION ISSUES. Report Of The Second Steam Explosion

• • ' "P

' 'h E' R

54 S03 CRITERIA FOR PREPARATON AND EVALUA.

TON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND Generic Safety leaves PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG 0933 S20: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

PLANTS.Cntena For Protective Action R%u......Wetions For Severe Accidents. Draft Report For..

Ground Motion NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATON Enforcement Action NUREG 0940 V15 N1 P1: ENFORCEMENT ACTIONS: SIGNIFICANT AC-STUDIESImpacts Of Artifcial Time History input On in-Structure TIONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress NU E CR446 IMPACT OF GROUNO MOTION CHARACTERIZA.

NUR 9

5 P2 NFORCEMENT ACTIONS: SIGNIFICANT AC-TON ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES.

TIONS RESOLVED A ACTOR LICENSEES. Semiannual Progress S'M MND MM WM W EM MWG A

R 0940 V75 N1 P3: ENFORCEMENT ACTIONS: SIGNIFICANT AC.STUDIES.lmpacts On Risk Assessment Of Uruform Hazard Spectra.

NUR TlONS RESOLVED MATERIAL LICENSEES. Semiannual Progress G/CR-2800 S05: GUIDELINES FOR NUCLEAR POWER PLXT Enhanced Reality Display SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

NUREG/CR-6450: CHARACTERIZATION OF CONTAMINATON NUREG/CR-6463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final DIGITAL IMAGE PROCESSING.

Report.

FORECAST Computer Code Head Penetration NUREG/CR-5595 R01: FORECAST: REGULATORY EFFECTS COST NUREG/CP-0151: PROCEEDINGS OF THE lAEA SPECIALISTS' MEET-ANALYSIS SOFTWARE MANUAL. Version 4.1-ING ON CRACKING IN LWR APV HEAD PENETRATIONS. Held At ASTM Headquarters, PNiadelpNa, Pennsylvania. May 2-3,1995.

Ferrttic Steel NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST Heavy-Section Steel Technology Program FAILURE BY BRITTLE FRACTURE, Category li And lil Femtic Sted NUREG/CR-4219 V12 N1: HEAVY SECTION STEEL TECHNOLOGY SNpping Containers With Wall TNckness Greater Than Four inches.

PROGRAM. Semiannual Progress Report For October 1994 March 1995.

Field Experiment NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATON INTO U G

-4 8 V09: CONTROL OF WATER INFILTRATION INTO nts A A umid R Il ryta 6 EAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-Financial Aneurance 3 wiments At A Humid Region Site.Beltsville. Maryland.

NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING FOR THE REFERENCE BOfLING WATER REACTOR POWER impact W STATON. Effects Of Current Regulatory And Other Considerations On NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON lMPACT The Financial Assurance Requirernents Of The Decommissioning Rule LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

And....

NUREG/CR4174 V02-REVISED ANALYSES OF DECOMMISSIONING In-Structure Response Spectra FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/CR4466: GROUND MOTION INPUT IN SEISMIC EVALUATON STUDIES. impacts Of Artif' ial Time History input On in-Structure STATON. Effects Of Current Regulatory And Other Considerations On c

The Financial Assurance Requirements Of The Decommissioning Rule Demand Spectra.

And_.

Individual Action Fire Barrier NUREG-0940 V15 N1 P1: ENFORCEMENT ACTONS: SIGNIFiCANT AC-NUREG 1547: METHODOLCGY FOR DEVELOPING AND IMPLEMENT.

TONS RESOLVED INDIVIDUAL ACTONS. Semiannual Progress ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING Report. January 4une 1996.

THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER PLANT APPLICATONS.

Inertia Effect NUREG-1552: FIRE BARRIEH PENETRATION SIALS IN NUCLEAR NUREG/CR4375. STRAIN RATE AND INERTIAL EFFECTS ON IMPACT POWER PLANTS.

LOADED SINGLE EDGE NOTCH BEND SPECIMENTS.

Subject index 17 Information Digest Position Sensitive Deteetor NUREG-1350 V08: NUCLEAR REGULATORY COMMISSION INFORMA-NUREG/CR4450: CHARACTERIZATivN OF CONTAMINATION TION DIGEST.1996 Edition.

THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESSING.

g NUREG-0725 All: PUBUC INFORMATION CIRCULAR FOR SHIP-Program Performance Report MENTS OF 1RRADIATED REACTOR FUEL.

NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR POWER LWR INDUSTRY. Annual Summary Of Program Performance Reports CY NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN 1995.

Li T WATER REACTORS. Senuannual Report. April 1995 - December NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM-Legal leeuances POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency NUREG-0750 V43 N05: NUCLEAR REGULATORY COMMISSION IS-Hotel, Washington,0C, July 15-18,1996.

SUANCES FOR MAY 1996.

NUREG 0750 V43 N06: NUCLEAR REGULATORY COMMISSION IS-Radiation Protection SUANCES FOR JUNE 1996.

NUREG/CR4374: WHOLE BODY EFFECTIVE HALF-LtVES FOR RA-DIOLABELED ANTIBODIES AND RELATED ISSUES.

Lighe O star Reactor NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN Radiolabeled Antibodies 41 T WATER REACTORS. Semiannual Report, April 1995 December NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR RA.

DIOLABELED ANTIBODIES AND RELATED ISSUES.

Low-Level Weste Disposet NUREG 1307 R06: REPORT ON WASTE BURIAL CHARGES. Escalation Reactx Containment Of Decommissiorung Waste Disposal Costs At Low Level Waste Bunat NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY Facitrhes.

NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-Reactor Licensees penments At A Humid Region Site,Beltsville. Maryland.

NUREG-0940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANT AC-TIONS RESOLVED REACTOR LICENSEES. Semiannual Progress maw Licensees Report, January June 1996.

NUREG-0940 V15 N1 P3: ENFORCEMENT ACTIONS: SIGNIFICANT AC-TIONS RESOLVED MATERIAL UCENSEES. Semiannual Progress Reactor Vessel Report, January 4une 1996.

NUREG/CR-2800 S05: GUIDELINES FOR NUCLEAR POWER PLANT SAFETY ISSUE PRIORITIZATION INFORVATION DEVELOPMENT.

Motor-Operated Valve NUREG/CP 0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM-POSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Regency gR -093 5 N01: NRC REGULATORY AGENDA. Semiannual Hotel, Washington,DC, July 15-18,1996.

Report. January 4une 1996.

NRC/ASME Symposium NUREG/CP4152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM.

Regulatory Analysis POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency NUREG/CR-5595 R01: FORECAST: REGULATORY EFFECTS COST Hotel, Washington,DC, July 15-18,1996.

ANALYSIS SOFTWARE MANUAL Version 4.1.

Notch Bond Regulatory And Technical Report NUREG/CR4375: STRAIN RATE AND INEATIAL EFFECTS ON IMPACT NUREG-0304 V21 NO2: REGULATORY AND TECHNICAL REPORTS LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

(ABSTRACT INDEX JOURNAL). Compilation For Second Quarter Occupational Rad 6ation Exposure NUREG/CR-6174 V01: REVISED ANALYSES OF DECOMMISSIONING Regulatory Document FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/CR 5973 R03: CODES AND STANDARDS AND OTHER GUID-STATION Effects Of Current Regulatory And Other Considerations On ANCE CITED IN REGULATORY DOCUMENTS.

The Financial Assurance Requirements Of The Decomrnissioning Rule And....

Response Spectre NUREG/CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA-FOR THE REFERENCE BOILING WATER REACTOR POWER TION ON CONSERVATISM AND VARIABluTY IN SEISMIC RISK ES-STATION Effects Of Current Regulatory And Other Considerations On TlMATES' The Financial Assurance Requirements Of The Decommissiorung Rule And-Rock Joint NUREG/CR 6388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-Offeite Emergency Preparednese ED ROCK MASS.

Organization Chart NUREG-0325 R20- U.S. NUCLEAR REGULATORY COMMISSION OR.

Rock Mese GANIZATION CHARTS AND FUNCTIONAL STATEMENTS. July 1,

NUREG/CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT.

1996.

ED ROCK MASS.

NUREG-0325 R21: U S. NUCLEAR REGULATORY COMMISSION OR-GANIZATION CHARTS AND FUNCTIONAL STATEMENTS. August 19, Rules 1996.

NUREG-0936 V15 NOI: NRC REGULATORY AGENDA.Somiannual Report. January 4une 1996.

NUREG 1552: FIRE BARRIER PENETRATION SEALS IN NUCLEAR SE(8) Specimen POWER PLANTS.

NUREG/CR.6317 NUMERICAL INVESTIGATION OF 3-D CONSTRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

Petitions For Rulemaking NUREG-0936 V15 NOI: NRC REGULATORY AGENDA. Semiannual Safeguards Summary Event List Report. January-June 1996' NUREG-0525 V02 A04: SAFEGUARDS

SUMMARY

EVENT LIST Pilgrim Nuclear Power Station (SSEL). January 1,1990 Through December 31,1995.

Pipe Safety issue Priorttirat6on NUREG/GR-0015: BULK TEMPERATURE MEASUREMENT IN THER.

NURES/CR-2800 S05: GUIDELINES FOR NUCLEAR POWER PLANT MALLY STRIPED PIPE FLOWS.

SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

18 Subject index Sciety System Stress Corrosion Cracking NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS Final LIGHT WATER REACTORS. Semiannual Report Apnl 1995 - December Report.

1995.

Setemic Response Surface Contamination NUREG/CR4388: SEISMIC RESPONSE OF ROCK JOINTS AND JOINT.

NUREG/CR4450: CHARACTER 12ATION OF CONTAMINATION ED ROCK MASS' THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND DIGITAL IMAGE PROCESSING.

Seismic R6sk g

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTER 12A-NUREG 0837 V16 NO2: NRC TLD DIRECT RADIATION MONITORING TION ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK ES-NETWORK. Progress Report. (AprW-June,1996).

TIMATES.

NUREG/CR4468 GROUND MOTION INPUT IN SEISMIC EVALUATION Temperaturo-Time Curve STUDIES. impacts On Risk Assessment Of Unsform Hazard Spectra.

NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

ING ALTERNATIVE TEMPERATURE-TIME CURVE FOR TESTING Selsmic Risk Analysis THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER NUREG/CR-6466: GROUND MOTION INPUT IN SEISMIC EVALUATION PLANT APPLICATIONS.

STUDIESimpacts Of Artificial Time History input On in Structure Demand Spectra.

Thermal Diffusion NUREG/GR 0015 BULK TEMPERATURE MEASUREMENT IN THER-Severe Accident MALLY STRIPED PIPE FLOWS.

NUREG-0654 ROI S03: CRITERIA FOR PREPARATION AND EVALUA.

TION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND Thermoluminescent Dosimeter PREPAREDNESS IN SUPPORT OF NUCLEAR POWER NUREG-0837 V16 NO2: NRC TLD DIRECT RADIATION MONITORING PLANTSCntena For Protective Action Recommendations For Severe NETWORK. Progress Report. (Aprd-June,1996).

Accidents. Draft Report For -

Thermophoresis NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL BY NUREG/ 41 9 A S MPLIFIED MODEL OF AEROSOL REMOVAL BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

Title List NUREG-0540 V18 N05: TITLE LIST OF DOCUMENTS MADE PUBUCLY Shlpping Container AVAILABLE. May 1-31 1996.

NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING AGAINST NUREG-0540 V18 N06 YlTLE LIST OF DOCUMENTS MADE PUBLICLY FAILURE BY ORITTLE FRACTURE. Category II And lil Femtsc Steel AVAILA3LE. June 1-30,1996.

Shippeng Contaeners With Wall Thickness Greater Than Four inches.

Silicone Foam NUREG/CR-6163: COMPUTER PROGRAMS FOR TW ACQUISITION NU 1552 FIRE BARRIER PENETRATION SEALS IN NUCLEAR NUREG 7 V LUAT ON D I VA DA N OF EDDY-

~

CURRENT ARRAY PROBES FOR STEAM GENERA 10R TUBE IN-NUR G/ R REVIEW GUIDELINES ON SOFTWARE LANGUAGES T B NG S MP ES~

FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS Final Report-Uniform Hazard Spectrum NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUATION RE 1 PUBLIC INFORMATION CIRCULAR FOR SHIP-MENTS OF IRRADIATED REACTOR FUEL Value-impact Analysis NUREG/CR-5595 RO1: FORECAST: REGULATORY EFFECTS COST Standard Review Plan ANALYSIS SOFTWARE MANUAL Version 4.1.

NUREG/CR 5973 R03: CODES AND STANDARDS AND OTHER GUID-ANCE CITED IN REGULATORY DOCUMENTS.

Valve Testing NUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRC/ASME SYM-Steam Explos'on POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency NUREG 1524: A REASSESSMENT OF THE POTENTIAL FOR AN Hotel, Washington,DC, July 15-18,1996.

ALPHA MODE CONTAINMENT FAILURE AND A REVIEW OF THE N

CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT NU E O 20 NO2: UCENSEE CONTRACTOR AND VENDOR IN.

ACT I

Report Of The Second Steam Explosen S

lON STATUS REPORT. Quarterty Report, April-June 1996.(White Steam Generator Wall Thickness NUREG/CR-2800 SO5: GUIDELINES FOR NUCLEAR POWER PLANT NUREG/CR-6491: RECOMMENDATIONS FOR PROTECTING AGAINST SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

NUREG/CR4163. COMPUTER PROGRAMS FOR THE ACQUISITION FAILURE BY BRITTLE FRACTURE. Category 11 And 111 Ferntic Steel Shipping Containers With Wall Thickness Greater Than Four Inches.

AND ANALYSIS OF EDDY-CURRENT ARRAY PROBE DATA.

NUREG/CR4357: EVALUATION AND FIELD VAllDATION OF EDDY-Waste Burial CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-NUREG 1307 A06-REPORT ON WASTE BURIAL CHARGES Escalation NU G CR4455: DATA ANALYSIS FOR STEAM GENERATOR ac te TUBING SAMPLES.

Water infiltration Strain Rate NUREG/CR 4918 V09: CONTROL OF WATER INFILTRAT ON INTO NUREG/CR4375: STRAIN RATE AND INERTIAL EFFECTS ON IMPACT NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Os < Field Ex-LOADED SINGLE EDGE NOTCH BEND SPECIMENTS.

penmerits At A Humed Region Sste Beltsville, Maryland.

i.

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 foHowed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS ADVISORY COMMITTEE (S)

OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS ADVISORY COMMITTEE ON NUCLEAR WASTE NUREG-1423 V06: A COMPILATION OF REPORTS OF THE ADVISO-NUREG-0725 R11: PUBLIC INFORMATION CIRCULAR FOR SHIP.

RY COMMITTEE ON NUCLEAR WASTE. July 1995 June 1996.

MENTS OF IRRADIATED REACTOR FUEL.

OPERATIONS BRANCH OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)

NUREG-0525 V02 R04: SAFEGUARDS

SUMMARY

EVENT UST (SSEL). January 1,1990 Through December 31,1995.

REGION 1 (POST 820201)

NUREG-0837 V16 NO2: NRC TLD DIRECT RADIATION MONITORING DIVISION OF WASTE MANAGEMENT (NMSS 940403)

NETWORK. Progress Report. (Apni-June.1996)-

NUREG 1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-COMMISSIONING OF THE SHIELDALLOV MEI AU.URGICAL NU E OV5N P1 ENFORC ENT ACTIONS: SIGNFICANT CORPORATION, CAMBRIDGE. OHIO, FACILITY. Docket do.

40-ACTIONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress 8948.ljcense No. SMB 1507.

Report. January-June 1996.

NUREG4940 V15 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANTEDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST C%o5)

ACTIONS RESOLVED REACTOR LICENSEES. Semiannual Progress DIVISION OF ENGINEERING TECHNOLOGY (POST 941217)

NUREG-0933 S20: A PRIORtTIZATION OF GENERIC SAFETY NUR 0

N P3 ENFORCEMENT ACTIONS: SIGNIFICANT E

N RESOLVED MATERIAL LICENSEES.Sem6 annual Progress pp NUREG 1307 R06:

REPORT ON WASTE BURIAL OFC OF PERSONNEL (POST 870413)

CHARGES. Escalation Of Decommissioning Waste Disposal Costs At NUREG-0325 R20: U.S. NUCLEAR REGULATORY COMMISSION OR-Low-Level Waste Bunal Facilities.

GAN12ATION CHARTS AND FUNCTIONAL STATEMENTS.Jufy 1 NUREG/CR-4918 V09 CONTROL OF WATER INFILTRATION INTO NEAR SURFACE LLW DISPOSAL UNITS.Progiess Report On F# eld 1996.

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

Expenments At A Humid Region Site.Beltsville. Maryland.

GANIZATION CHARTS AND FUNCTIONAL STATEMENTS.Aaust DIVISION OF SYSTEMS TECHNOLOGY (POST 941217) 19.1996 NUREG 1524: A REASEESSMENT OF THE POTENTIAL FOR AN ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE EDO - OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)

DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV-CURRENT UNDERSTANDING OF BROADER FUEL-COOLANT

^

NUREG O V21 NO2; REGULATORY AND TECt;NICAL REPORTS N

(ABSTRACT INDEX JOURNAL). Compilation For Second Quarter NUR CR 89 A S MPLIFIED MODEL OF AEROSOL REMOVAL BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NU G V 8 N05: TITLE LIST OF DOCUMENTS MADE PUBLIC-EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)

LY AVAILABLE. May 1 31, 1996.

NUREG 0540 V18 N06: TITLE LIST OF DOCUMENTS MADE PUBLIC-OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)

ENO & N MSEE NRAN M WM N NU EG O 50 3 5 UCLE R REGULATORY COMMISSION IS-SPECTION STATUS REPORT. Quarterly Report.Apni-June SUANCES FOR MAY 1996.

G4654 R 3: CRITERIA FOR PREPARATION AND EVAL-NUREGO V43 N NUCLEAR REGULATORY COMMISSION IS-N UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS NUREG-0936 V15 N01: NRC REGULATORY AGENDA.Semaannual AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER Report. January-June 1996.

PLANTS.Cntena For Protectrve Action Recommendations For Severs Accidents Draft Report For....

EDO OFFICE 07.GE CONTROLLER (PRE 820418 & POST 890205)

DIVISION OF BUDGET & ANALYSIS (POST 890205)

NUREG 1547: MET HODOLOGY FOR DEVELOPING AND IMPLE-NUREG 1350 V08: NUCLEAR REGULATORY COMMISSION INFOR-MENTING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR MATION DIGEST.1996 Edeton-EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NU EG 15 2 IR B RRIER PENETRATION SEALS IN NUCLEAR WER P NTS OFFICE ANALYSIS & EVALUATION OF OPERATIONAL DATA. DI-SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt NUREG-1272 V09 N01: OFFICE FOR ANALYSIS AND EVALUATION Regency Hotel. Washington.DC. July 15 18.1996 OF OPERATIONAL DATA.1994 FY 95 Annual Report Reactors.

19

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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., pr,ogram of-fices) and then by subsections of these (e.g., divisions, branches) where appropnate. 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.

3 lhere were no NuREG/lA reports published during this quarter i

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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 offi end then by subsections of these (e.g., divisions) where appropriate. The sponsor orga iza-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 OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS DIVISION OF REGULATORY APPLICATIONS (POST 941217)

PROGRAM MANAGEMENT. POLICY DEVELOPMENT & ANALYS S NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO STAl?F (POST 670413)

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field NUREG/CR4491: RECOMMENDATIONS FOR PROTECTING Expenments At A Humid Region Site.Beltsville. Maryland.

AGAINST FAILURE BY BRITTLE FRACTURE Category II And 111 Fer.

NUREG/CF 5 RO1: FORECAST: REGULATORY EFFECTS COST nt-liteel Shipping Containers With Wall Thickness Greater Than ANALYS TTWARE MANUAL Version d.1.

Four anches.

NUREG/Ch a74 V01: REVISED ANALYSES OF DECOMMISS:ONING FOR THE REFERENCE BOILING WATER REACTOR POWER EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

OlVISiON OF ENGINEERING TECHNOLOGY (POST 941217)

STATION Effects Of Current Regulatory And Other Considerations NUREG/CR-2800 SOS: GUIDELINES FOR NUCLEAR POWER PLANT On The Financial Assurance Requirements Of The Decommissioneng SAFETY ISSUE PRIORITIZATION INFORMATION DEVELOPMENT.

Rule And-..

NUREG1CR-4219 V12 N1: HEAVY-SECTION STEEL TECHNOLOGY NUREG/CR-6174 V02: REVISED ANALYSES OF DECOMMIS$lONING PROGRAM.Sem6 annual Progress Report For October 1994. March FOR THE REFEFIENCE BOILING WATER REACTOR POWER 1995.

STATION Effects Of Current Regulatory And Other Considerations NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING On The Financial Assurance Requirements Of The Decommissioning IN LIGHT WATER REACTOPS. Semiannual Rcport. April 1995 - De-Rule And..

cembei 1995.

NUREG/CR4374: WHOLE-BODY EFFECTIVE HALF-LIVES FOR RA-NUREG/CR-6163: COMPUTER PROGRAMS FOR THE ACQUISITION DIOLABELED ANTIBODIES AND RELATED ISSUES.

[ONTED NUREG/ 43 7 U iI IN E I ATI N F 3 CON-KM S STRAINT EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T)

NUREG/CR-6450: CHARACTERIZATION OF CONTAMINATION NUR / 4357: EVALUATION AND F! ELD VALIDATION OF EDDY.

THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND

^L AG UR T ARRAY PROBES FOR STEAM GENERATOR TUDE IN-DIV O Op YSTEMS ECH OLOGY (POST 941217)

NUREG/CR 6375: STRAIN RATE AND INERTIAL EFFECTS ON NUREG/CR4189: A SIMPLIFIED MODEL OF AEROSOL REMOVAL IMPACT LOADED SINGLE-EDGE NOTCH BEND SPECIMENTS.

BY NATURAL PROCESSES IN REACTOR CONTAINMENTS.

NUREG/G' 6455: DATA ANALYSIS FOR STEAM GENERATOR NUREG/CR4463: REVIEW GUIDELINES ON SOFTWARE LAN-d TUBING SAMPLES.

GUAGES FOR USE IN NUCLEAR POWER PLANT SAFETY NUREG/CR44S6: GROUND MOTION INPUT IN SEISMIC EVALUA-SYSTEMS Final Report.

TION STUDIESImpacts Of Artificial Time History input On in-Stn.c.

ture Derriand Spectra.

EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 400420)

NUREG/CR4467: IMPACT OF GROUND MOTION CHARACTERIZA.

OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)

TION ON CONSERVATISM AND VARIABILITY IN SEISMIC RISK NUREG/CR-5758 V06: FITNESS FOR DUTY IN THE NUCLEAR ESTIMA7ES.

POWER INDUSTRY. Annual Summary Of Program Performance Re-NUREG/CR4468: GROUND MOTION INPUT IN SEISMIC EVALUA-ports CY 1995.

TION STUDIES.Pripacts On Risk Assessment Of Uniform Hazted NUREG/CR 5973 R03: CODES AND STANDARDS AND OTHER Spectra.

GUIDANCE CITED IN REGULATORY DOCUMENTS.

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1 Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.

i AMERICAN SOCIETY OF MECHANICAL ENGINEERS MARYLAND UNIV. OF, COLLEGE PARK, MD WUREG/CP-0152: PROCEEDINGS OF THE FOURTH NRG/ASME SYM-NUREG/CR-4918 V09: CONTROL OF WATER INFILTRATION INTO POSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Regency NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex-Hotel, Washington,DC, July 15 18,1996.

penments At A Humid Regen Site.Beltsville,Mafyland.

ARGONNE NATIONAL LA80RATORY MINNESOTA UNIV. OF, MINNEAPOLIS. MN NUREG/CR-4667 V21: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/Ch4374: WHOLE BODY EFFECTIVE HALF UVES FOR FA.

UGHT WATER REACTORS. Semiannual Report. April 1995. December DIOLABELED ANTIBODIES AND RELATED ISSUES.

1995.

CATTELLE MEMORIAL INSTITUTE. PACIFIC NORTHWEST NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERLY l

Lt ORATORY NATIONAL SUREAU OF NW.G/CR-2800 SO5: GUIDELINES FOR NUCLEAR POWER PLANT NUREG-1547: METHODOLOGY FOR DEVELOPING AND IMPLEMENT.

SAFETY ISSUE PRIORITIZ/. TION INFORMATION DEVELOPMENT.

ING ALTERNATIVE TEMPERATURE TIME CURVE FOR TESTING MUREG/CR-5758 V06. FITNESS FOR DUTY IN THE NUCLEAR POWER THE FIRE RESISTANCE OF BARRIERS FOR NUCLEAR POWER INDUSTRY. Annual Summary Of Program Performance Reports CY PLANT APPLICATIONS.

1995.

NUREG/CR-5973 R03: CODES AND STANDARDS AND OTHER GUID-OAK RIDGE NATIONAL LABORATORY ANCE CITED IN REGULATORY DOCUMENTS NUREG-1543: DRAFT ENVIRONMENTAL IMPACT STATEMENT DE-NUREG/CR4174 V01: REVISED ANALYSES OF DECOMMISSIONING COMMISSIONING OF THE SHIELDALLOY METALLURGICAL FOR THE REFERENCE BOILING WATER REACTOR POWER CORPORATION. CAMBRIDGE. OHIO, FACluTY. Docket No. 404948,U-STATION. Effects Of Current Regulatory And Other Consideratons On cense No. SMB-1507 The Financial Assurance Requirements Of The Decommtssioning Rule NUREG/CP 0151: PROCEEDINGS OF THE lAEA SPECIAUSTS' MEET.

ING ON CRACKING IN LWR RPV HEAD PENETRATIONS. Held At NUR /CR4174 V02: REVISED ANALYSES OF DECOMMISSIONING ASTM Headquarters PNiadelphia, Pennsylvania, May 2-3,1995.

FOR THE REFERENCE BOILING WATER REACTOR POWER NUREG/CR-4219 V12 N1: HEAVY SECTION STEEL TECHNOLOGY STAT'ON Effects Of Current Regulatory And Other Consideratons On The Financial Assurance Requirements Of The Decommissoning Rule PROGRAM. Semiannual Progress Report For October 1994 - March j

1995.

i And'"

NUREG/CR-6163: COMPUTER PROGRAMS FOR THE ACQUISITION CATTELLE SEATTLE RESEARCH CENTER AND ANALYSIS OF EDL,Y CURRENT ARRAY PROBE DATA.

I NUREG/CR 5758 V06. FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR4357: EVALUATION AND FIELD VALIDATION OF EDDY.

l INDUSTRY. Annual Summary Of Program i Armance Reports CY CURRENT ARRAY PROBES FOR STEAM GENERATOR TUBE IN-l 1995.

SPECTION.

NUREG/CR4455: DATA ANALYSIS FOR STEAM GENERATOR BROOKHAVEN NATIONAL LABORATORY TUBING SAMPLES.

MUREG-1524: A REASSESSMENT OF THE POTENTIAL FOR AN ALPHA-MODE CONTAINMENT FAILURE AND A REVIEW OF THE RISK ENGINEERING,1NC.

CURRENT UNDERSTANDING OF BROADER FUEL COOLANT NUREG/CR4466: GROUND MOTION IfWUT IN SEISMIC EVALUATION INTERACTION ISSUES Report Of The Second Steam Explosen STUDIES. impacts Of Artificial Time History input On in-Structure Review Group Worksh4 Demar Spectra.

NUREG/CR 4374: WHOLE BODY EFFECTIVE HALF-UVES FOR RA-NUREG/CR4467; IMPACT OF GROUND MOTION CHARACTERIZA-

)

DIOLABELED ANTIBODIES AND RELATED ISSUES.

TION ON CONSERVATISM AND VARIABluTY IN SEISMIC RISK ES-TIMATES.

CALIFORNIA, UNIV OF LOS ANGELES,CA NUREG/CR4468; GROUND MOTION INPUT IN SEISMIC EVALUATION NUREG/CR-4918 V015: CONTRO5 OF WATER INFILTRATION INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Field Ex.

STUDIES. impacts On Risk Assessment Of Uniform Hazard Spectra.

penments At A Humid Region Site,Beltsville, Maryland.

S. COHEN & ASSOCIATES,INC.

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES NUREG/CR-5595 ROI: FORECAST: REGULATORY EFFECTS COST PlVREG/CR4388. SEISMIC RESPONSE OF ROCK JOINTS AND JOINT-ANALYSIS SOFTWARE MANUAL Verson 4.1.

ED HOCK MASS.

SANDIA NATIONAL LAPORATORIES FEDERAL EMERGENCY MANAGEMENT AGENCY NUREG/CR-6189: A SIMPUFIED MODEL OF AEROSOL REMOVAL BY IJUREG-0654 RO1 S0*.t. CRITERIA FOR PREPARATION AND EVALUA-NATURAL PROCESSES IN REACTOR CONTAINMENTS.

TION OF RADIOLOGICAL EMERGENCY RESFONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER SCIENCE & ENGINEERING ASSOCIATES,INC.

PLANTS.Cntena For Protective Acton Flecommendatons For Severe NUREG/CR 5595 R01: FORECAST: REGULATORY EFFECTS COST Accidents. Draft Report For.-

ANALYSIS SOFTWARE MANUAL Version 4.1.

ILUNOIS, UNfV, OF, URBANA, IL SHONKA RESEARCH ASSOCIATES,INC.

NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT NUREG/CR4450: CHARACTERl2ATION OF CONTAMINATION EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C'T) SPECIMENS THROUGH THE USE OF POSITION SENSITIVE DETECTORS AND 1

NUREG/CR4375: STRAIN RATE AND INERTlAL tEFFECTS ON IMPACT LOADED SINGLE EDGE NOTCH BEND SPECIMENTS.

DIGITAL IMAGE PROCESSING.

LAWRENCE UVERMORE NATIONAL LABORATORY SOHAR. INC.

NUREG/GR4491: RECOMMENDATIONS FOR PROTECTING AGAINST NUREG/CH4463: REVIEW GUIDELINES ON SOFTWARE LANGUAGES FAILURE BY BRITTLE FRACTUR81. Category II And 111 Femtic Steel FOR USE IN NUCLEAR POWER PLANT SAFETY SYSTEMS. Final Shipping Containers With Wall Thekness Greater Than Four Inches.

Report.

25

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26 Contractor Index TECHNICAL RESEARCH CENTRE OF FINLAND (VTT)

TENNESSEE UNIV. OF, KNOXVILLE, TN NUREG/CR4317: NUMERICAL INVESTIGATION OF 3-D CONSTRAINT NUREG/GR@15: BULK TEMPERATURE MEASUREMENT IN THER-EFFECTS ON BRITTLE FRACTURE IN SE(B) AND C(T) SPECIMENS.

MALLY STRIPED PIPE FLOWS.

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i International Organization Index This index lists, in a;phabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.

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NUREG-0304 Vol. 21, No. 3 a w u mDSUemLE 3 DATE REPORT PUBUSr1ED Regulatory and Technical Reports (Abstract Index Journal) l uONTs YEAR Compilation for Third Quarter 1996 February 1997 l

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6. Aa)! HOR (5) 6 TYPE OF REPORT Reference

7. PERIOD COVERED (inclumve Dates)

July - September 1996 e PERFORMsNG ORGANIZATON - NAME AND ADDRESS (it NRC, provide Dumon. Omco or Region, U S Nuclear Reguistory Commesson, and mahng madress. W contractor, pronde name and mahng address )

Publications Branch Office ofInformation Resources Management U.S. Nuclear Regulatory Commission W.Wington, DC 20555 - 0001 9 SPONSORING ORGANIZATION - NAME AND ADDRESS (It NRC. type *Same as above'; W contractor, puvde NRC Dvtmon, Ofhce or Region. U S Nuclear Regulatory Con 1

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10. SUPPLEMENT ARY NOTES M. A. Sheehan, Project Manager 11 CSSTRACT (200 words or less)

This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed-ings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

12. CEY1NO8Crs !ESCRIPTORS (List words or phrases that wlR assist researchers in locahng the report) 13 AVAILABILITY STATEMENT Unlimited 14 SECURITY CLASSIFICATION compilation c,,, p,,,

abstract mdex Unclass.fied i

(The Report) l Unclassified 16 NUMBER Of PAGES 16 PRICli NRC FORM 335 Q-89)

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