ML20207J357

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Second Quarter 1988,April-June

ML20207J357
Person / Time
Issue date:	08/31/1988
From:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
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References
NUREG-0304, NUREG-0304-V13-N02, NUREG-304, NUREG-304-V13-N2, NUDOCS 8809060137
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NUREG-0304 Vol.13, No. 2 Regulatory and Technical Reports

' Abstract Index Journal?

Compilation for Second Quarter 1988 April - June i

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e Available from Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, D.C. 20013-7082 A year's subscription consists of 4 issues for this publication.

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NUREG-0304 ,

Vol.13, No. 2 l Regulatory and Technical Reports (Abstract Index Journal) l Compilation for .,

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CONTENTS Preface...............................................................................v Index Tab i Main Citations and Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

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• Staff Reports #

• Conference Proceedings l

• Contractor Reports

• International Agreement Reports .

Secondary Report Number Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Pe rso nal Authe r In de x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' 3 S u bj ec t I n d e x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 i NRC Originating Organization index (Staff Reports) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 N RC Originating Organization Index (International Agreements) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 N RC Contract Sponsor index (Contractor Reports) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... 7 Cont ractor inde x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 International Organization inoe x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 U cen sed Fa cility Inde x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 l l l l

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

Division of Publications Services Policy and Publications Management Branch Publishing and Translations Section Woodmont 537 U.S. Nuclear Regulatory Commission Washington, D.C. 20665 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP XXXX, NUREG/CR XXXX, and NUREG/lA XXXX. These precede the following indbxes:

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

NRC Originatin Organization Index (International Agreements)

NRC Contract ponsor Index (Contractor Reports)

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

The bibliographic elements of the main citations are the following:

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

ANDERSON, C.J. Division of Safety Technology. August 1981, 90 pp. 8109140048. 09570:200.

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

, author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the microfiche address (for internal NRC use).

Conference Report ,

NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE COLE OF RISK ASSESSMENT AND RELIABILITY ENGINEERING IN NUCLEAR REGULATION. JA.IERP, J.S. Argonne National Laboratory. May 1981,141 pp. 8105280299. ANL 813. 0863 :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 Docu-ment Control System accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC Internal use).

yontractor Report NUREG/CR 1566: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.: BENNETT, P.R.

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

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 -

l Document Control System accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC intemal use). ,

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

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

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

ADD - addendum APP appendix DRFT - draft ERR - errata N - number R - revision S - supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO) or from the National Technical Information Service, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:

Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202)275-2060 or (202)275-2171. Non-U.S. customers must make payment in advance either by Intern 8tional Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.

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

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

All these report codes are controlled and assigned by the staff of the Publishing and Translations Section of the NRC Division of Publications Services.

vi

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

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-nat;onal agreement reaort. The bibliographic information (see Preface for details) is followed by a brief abstract of tais report.

NUREG 0020 V12 N03: LICENSED OPERATING REACTORS first involved a signifcant degradabon of plant safety at Oyster STATUS

SUMMARY

REPORT. Data As Of February Creek; and the second invoNed a steam generator tube rupture 29,1988.(Gray Book 1) SCHWARTZ,t. Division of Computer & at Nortn Anna Urvt 1. There were four abnormal occurrences at Telecommun.catons Services (Post 870413). Apnl 1988. 505pp. the other NRC icensees. The frst invoNed a therapeutic meda 8805020159. 45340 145..

cal misadministration; the second involved a failure to report di.

The OPERATING UNITS STATUS REPORT LICENSED OP- agnoste medical misadministratons; the tNrd invoNed the sus-ERATING REACTORS provides data on the operation of nucle- pension of a well logging company's license; and the fourth in-ar units as timely and accurately as possible. This information is volved the suspension of an industr'.al ra$ography company's li-collected by the Offee of Administration and Resources Man- cense. There were two abnormal occurrences reported by an agement from the Headquarters staff of NRC's Offee of En- Agreement State (New York). The first invoNed a hospital con-forcement (OE), from NRC's Regional Offces, and from utAbes. tamination incident and the second involved therapeutic medical The three sectons of the report are: monthty highlights and sta- misadministrations. The report also contains informaticfl updat-tisbes for commercial operabng untts, and errata from previously ing some previously reported abnormal occurrtencet.

reported data; a compilaton of detailed information on each unit, provided by NRC's Regonal Offees, OE Headquarters and NUREG-0090 V10 N04: REPORT TO CONGRESS ON ABNOR.

the utilibes; and an appendix for miscellaneous informaton such MAL OCCURRENCES. October. December 1987.

• Office for as spent fuel storage capabdity, reactor years of expenence and Analysis & Evaluaton of Operational Data, Drector. March non power reactors in the U.S. It is hoped the report is helpful 1988. 34pp. 8804280329. 45270:213.

to all agencies and individuals interested in maintaining an Secton 208 of the Energy Reorganizaton Act of 1974 identi-awareness of the U.S. energy situaton as a whole. fies an abnormal occurrence as an unscheduled incident or event which the Nuclear Regulatory Commission determines to NUREG-0020 V12 N04: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of March 31,1988.(Gray be sqnsficant from the standpoint of pubfc health and safety Book 1) SCHWARTLI. Divison of Computer & Tele:ommunica. and requres a quarterly report of such events to be made to tons Servces (Post 870413). Vay 1988. 513pp. 8805200063 Congress. TNs report covers the penod October 1 to December 45550.091.

31,1987. Dunng the report penod, there was one abnormal oc-Currence at the NRC hcenseet; the item involved the suspen-See NUREG-0020,V12,NO3 abstract.

sion of Icense of an oil and gas well tracer company for non.

NUREG-0020 V12 N05: LICENSED OPERATING RE/.dTORS compliance with NRC regulatory requirements. There were no l STATUS

SUMMARY

REPORT. Data As Of April 30,198t,.(Gray abnormal occurrences reported by the Agreement States. The Book 1) SCHWARTZ,1. Division of Computer & Telecommunca- report also contains informaton updating some prevousty re-tiors Servees (Post 870414). June 1988. 500pp. 8806230155. ported abnormal occurrences.

45899:010.

See NUREG-0020,V12,NO3 abstract. NUREG-0304 V13 N01: REGULATORY AND TECHNICAL RE.

PORTS (ABSTRACT INDEX JOURNAL). Compilaton For Frst NUREGOu40 V12 N01: LICENSEE CONTRACTOR AND Quarter 1988, January March,

• CMsion of Freedom of Informa-VENDOR INSPECTION STATUS REPORT. Quarterty Report. January-March 1988(WNte Book)

• Dnnsion of Reactor Ins & Sfe rds (Post 8704!:). May 1988.136pp. [8071050 85 07 TNs journal includes att formal reports in the NUREG senes prepared by the NRC staff and contractors; proceedings of con-TNs perc6ce' overs the results of inspectons performed by femnces a1 wMshops; as weH as mmatonal agmement re-the NRC's Vend 'nspection Branch that have been distnbuted pods. N es n Ws compa2n am eded W access W to the inspecteo ,,rganizatons during the period from January title and abstract, secondary report number, personal author, ];

1988 through March 1988. Also included in tNs issue are the results of certain inspectons performed pnor to January 198f subject, NRC organization for staff an2 intemabonal agree- 1 l ments, contrac% intematoM orgaNaton, and hcensed fach that were not included in previous issues of NUREG-0040, j ty. i l NUREG-0090 V10 N03: REPORT TO CONGRESS ON ABNOR- i MAL OCCURRENCES Juty September 1987.

• Offee fo Anay NUREG-0540 V10 N02: TITLE LIST OF DOCUMENTS MADE  !

ses & Evabaton of Operabonal Data, Drector. March 1988. PUBLICLY AVAILABLE. February 1 29,1988.

• Divisen of Publi-45pp. 8804280308. 45270.244. cation Servces (870413 880514). Apnl 1988. 346pp. I Secton 208 of the Energy Reorganizaton Act of 1974 idents 8804280623. 45273:038.

fies an abnormal occurrence as an unscheduled incident or TNs document is a monthly pubhcaton containing desenp-event wtuch the Nuclear Regulatory Commisson determines to tons of informabon recetved and generated by the U.S. Nuclear be significant from the standpoint of pubhc health and safety Regulatory Commisson (NRC). TNs informabon includes (1) <

and requres a quarterty report of such events to be made to docketed matenal associated with civihan nucisar power plants l Congress. TNs report covers the penod July 1 to September and other uses of radcactrve matenals, and (2) nondocketed I 30,1987. Dunng the report penod, there were two abnormal oc- matenal rece4ved and generated by NRC perbnent to its ro:e as l currences at the tsuclear power plants heensed to operate. The a regulatory agency. The 'ollowmg indenes are included. Per- l 1

1 l

1 2 Main Citations and Abstracts sonal Author, Corporate Source, Report Number, and Cross er Regulatory Corrmsson (NRC), and to meet the requirements Reference to Princtpal Documents. of Pubhc Law 96-295. The NRC staff must approve such routes NUREG 0540 V10 N03: TITLE LIST OF DOCUMENTS MADE prior to their use in accordance with the, regulatory provisions of PUBLICLY AVAILABLE. March 1 31,1988.

• Division of Pubhca- Secton 73M d M M Pad 4 h @mam bcW m flects NRC staff knowledge as of September 30,1987, Spent ton Services (870413 880514). May 1988. 400pp. 8806020034.

fuel sNpment routes, pnmanly for road transportation, but also 45706:303 See NUREG-0540,V10,N02 abstract. incWmg three rad routes, are WaM on pdmons d %

partment of Transportaten road maps. Also included are the NUREG-0540 V10 N04: TITLE LIST OF DOCUMENTS MADE amounts of matenal shipped dunng the appropriate eight year PUBLICLY AVAILABLE. Apnl 1 30,1988.

• Drvision of Freedom period that safeguards regulations for spent fuel sNpments of Informaton & Publicaton Senoces (Post 880515). June 1988. have been efectrve. In addition, the Commission has chosen to 354pp. 8807070426. 46012:018. prodde informabon in tNs document regarding the NRC's safety See NUREG-0540,V10,N02 abstract. and safeguards regulatons for spent fuel shipments as well as safeguards incidents regarding spent fuel sNpments (of which NUREG-0683 S03 DRFT: PROGRAMMATIC ENVIR")NMENTAL none have been reported to date). TNs additonal informaton is IMPACT STATEMENT RELATED TO DECONTAMINATION furnished by the Commission in order to convey to the pubhc a AND DISPOSAL OF RADIOACTIVE WASTES RESULTING nm comWe peture of MC $atuy practices concWng FROM MARCH 28,1979 ACCIDENT,THREE MILE ISLAND NU.

CLEAR the shipment of spent fuel than Could be obtained by the publi-CTATION UNIT 2 Docket No. 50-320.(GPU caton of the sNpment routes and quantities alone.

Nuclear, incorporated)

• Office of Nuclear Reactor Regulation, Drector (Post 870411). Apnl 1988. 204pp. 8804280348. NUREG 0750 V26101: INDEXES TO NUCLEAR REGULATORY 45U0:009. COMMISSION ISSUANCES. July. September 198's.

• Onnsion of in accordance with the National Environmental Policy Act, the Pubhcaten Services (870413-880514). March 1988. 50pp.

Programmate Environmental impact Statement Related to De* 8804290204.45324:282.

contamnation and Disposal of Radcactive Waste from March Digests and indexes for issuances of the Commission, the 28,1979 Accident Three Mile Island Nuclear Staten, Urut 2 Atoms Safety and Licensing Appeal Panel, the Atomic Safety (PElS) has been supplemented. Ths draft supplement address- and Ucensing Board Panel, the Admirustrative Law Judge, the es potential environmental impacts associated with the licens. Directors' Decisions, and the Denials of Pebtons for Rulemak.

ee's (GPU Nuclear's) proposal to place the TMl 2 facility in a ing are presented.

post-defueling monitored storage mode followed by the comple-tion of cleanup. The NRC staff has concluded, based on this NUREG-0750 Y26102: INDEXES TO NUCLEAR REGULATORY evaluaton, that the hcensee's proposed plan and the NRC staff. COMMISSION ISSUANCES. July-December 1987.

• Division of idenbfied afternabves for completon of cleanup are within apoli. Publicaton Services (870413-880514). April 1988. 65pp.

cable regulate'y lists and could be implemented without signifi. 8805200092. 45550226.

cant envronmental impact. No afternative was ound r to be See NUREG-0750,V26,101 abstract.

clearty preferable from an envronmental impact perspective.

The staff concluded that the benefits of cleanup acton out- NUREG 0750 V27101: INDEXES TO NUCLEAR REGULATORY COMMISSION ISSUANCES. January March 1988.

• Dvision of weigh the small associated impacts ~

Freedom of information & Pubicaton Services (Post 880515).

NUREG-0713 V07: OCCUPATIONAL RADIATICM EXPOSURE AT June 1988. 46pp. 8807080350. 46077:107.

COMMERCIAL NUCLEAR POWER REACTORS AND OTHER See NUREG 0750,V26,101 abstract.

FACILITIES 1985 Eighteenth Annual Report. BROOKS.B. DM-son of Regulatory Applicatons (Post 870413). April 1988. NUREG-0750 V27 N02: NUCLEAR REGULATORY COMulSSION 168pp. 8804280390. 45271:136 ISSUANCES FOR FEBRUARY 1988. Pages 41255.

• Division This report summarizes the occupatonal ra$aton exposure of Pubhcation Services (870413-880514). April 1988. 223pp.

ure I for R ys e ( RS yn ear power L s es of CommssM tne Atomic Safety and G faciht>es and certain other categones of NRC heensees dunng censing Appeaf Panet, the Atomic Safety and Ucensing Board the years 1969 through 1985. The bulk of the data presented in Panel, the Administrabve Law Judge, and NRC program offices the report was obtained from annual radaten exposure reports are presented.

submitted in accordance with the require nents of 10 CFR NUREG 0750 V27 N03: NUCLEAR REGULATORY COMMISSION 20.407. Data on workers terminating their employment at certain ISSUANCES FOR MARCH 1988. Pages 257 334.

• Division of NRC heensed faciltties were obtained from reports submtted Pubhcaton Services (870413-880514). May 1988. 169pp.

pursuant to 10 CFR 20.408. The 1985 annual reports submitted 8806070066. 45726.299.

l by about 500 Icensees indicated that approximately 216,000 in. See NUREG 0750,V27,N02 abstract.

dM. duals were monitored, 94,000 of whom were monitored by I

nudear power facilities. They incurred an average individual NUREG-0437 V07 N04: NRC TLD DIRECT RADIATION MONI-dose of 0.22 rem (cSv) and an average measureable dose of TORING NETWORK. Progress Report, October-December 1987.

0.43 rem (cSv). Terminabon radabon exposure reports were STRUCKMEYER R.; MCNAMARA,N.; COHEN.L Regen 1. Ofc anayred to reveal that about 77,300 in$viduals completed ther of the Director. Apnl 1988. 323pp. 8804290185. 45283:099.

employment with one or more of the 500 covered licensees This report provides the status and results of the NRC Ther-dunng 1984. Some 73,200 of these endnnduals ;ermmated from molurrunescent Dosimeter (TLD) Drect Ra$aton Morutoring power reactor facihtars, and about 7,400 of them were consid. Network. It presents tne radiabon levels measured in the viciruty ered to be transient workerg who recetved an average dose of of NRC licensed facihty sies throughout the country for the 1f4 rem (cSv). fourth quarter of 1987.

NUREG-0725 R06: PUBLIC INFORMATION CIRCULAR FOR NUREG 0837 V08 N01: NRC TLD DIRECT RADIATION MONi-SHIPMENTS OF IRRADIATED REACTOR FUEL

• Drvison o' TORING NETWORK. Progress Report, January March 1988.

Safeguards & Transportation (Post 870413) Apnl 1988. 95pp. STRUCKMEYER.R.; MCNAMARA.N. Regen 1. Ofc of the Drec-8805200083. 45560 346. tor. June 1988. 224pp. 6807110535. 46078 214.

Th s circular has been prepared in response to numerous re- This report provides the status and results of the NRC Ther-quests for informaton regar$ng routes used for the shipment of moluminescent Dosimeter (TLD) Drect Radiaton Monitonng irradated reactor (spent) fuel subject to regulaton by the Nucle- Network. It presents the ra$at on lewwls measured in the vicinity 1

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1 Main Citati:ns and Abstracts 3 of NRC 1+ censed facil#y s4tes throughout the country for the first NUREG 1032: EVALUATION OF STATION BLACKOUT ACCl- l Quarter of 1988. DENTS AT NUCLEAR POWER PLANTS Technical Findings Re-lated To Unresolved Safety issue A-44 Final Report i NUREG-Ot33 S07: A PRIORITIZATION OF GENERIC SAFETY BARANOWSKY,P.W. Off ce of Nuclear Regulatory Research, ISSUES. EMRIT,R.; RIGGS,R.: MILSTEAD.W.; et al. Omson of Director (Post 860720). BARANOWSKY,P.W. Office of Nuclear Regu' story Appicatons (Post 870413). Apnl 1988. 291pp. Reactor Regulaton, Director (Post 870411). June 1988.170pp.

8805060326. 45408:020. 8806100152. 45785:188.

The report presents the pnonty rankings for generic safety "Station Blackout" whch is the complete loss of afternat ng i issues related to nuclear power plants. The purpose of these current (AC) electrical power in a nuclear power plant, has been rankings is to assist in the timely and effeient allocaton of NRC designated as Unresolved Safety issue A-44. Because many resources for the resoluton of those safety issues that have a safety systems required for reactor core decay heat rimoval i

significant potental for reducing risk. The safety prionty rankings and containment heat removal depend ort /.C power, the conse- ,

are HIGH, MEDIUM, LOW, and DROP and have been assigned quencos of a staton blackout could be severe. This report doc-  !

on the basis of nsk sigr:Jicance estimates, the ratio of risk to urnents the findangs of technical studies performed as part of '

costs and other impacts estimated to result if resolutons of the the program to resolve this issue. The important factors ana-safety issues were implemented, and the consideration of un- lyzed include; the frequency of loss of offsete power; the proba-a certainties and other quantitative or qualitative factors. To the bility that emergency or onsite AC power supphes would be un-extent practcal, estimates are quantitative. availablo; the capability and rehabihty of decay beat removal systems independent of AC power; and the likelihood that off-NUREG-0940 V07 N01: ENFORCEMENT ACTIONS:SIGNIFICANT site power would be restored before systems that cannot oper.

ACTIONS RESOLVED.Ouarterty Progress Report. January. March ate for extended penoris without AC power fail, thus resulting in 1988.

• Ofc of Enforcement (Post 870413). June 1988. 25Cpp. core damage. This report also addresses effects of different de-l 8807070438. 46014:04& g,gns, locatons, and operatonal features on the estimated fre-This compilation summarizes signfcant enforcement actons quency of core damage resulting from staton blackout events.  ;

that have been resolved dunng one quarterly penod (January -

March 1988) and includes copies of letters, Notices, and Orders NUREG 1109: REGULATORY /BA06T ANALYSIS FOR THE sent by the Nuclear Regulatory Commission to licensees with RESOLUTION OF UNRESOLVED SAFETY ISSUE A 44,STA- l 1 respect to these enforcement actons. It is antcipated that the TION BLACKOUT. RUBIN,A.M. Office of Nuclear Regulatory ,

informaton in this pubhcation will be widely disseminated to Research, Director (Post 860720). RUBIN,A.M. Office of Nucle-managers and employees engaged in actraties bcensed by the at Reactor Regulaton, Director (Post 870411). June 1988.

NRC, so that actons can be taken to improve safety by avoid- 98pp. 8806100170. 45785:118.

ing future violatons similar to those desenbed in this pubhca- Station blackout is the complete loss of alternating current tort (ac) electnc power to the essential and nonessential buses in a nuclear power plant; it resutts when both offsite power and the NUREG-0975 V06: COMPILATION OF CONTRACT RESEARCH onsite emergency ac power systems are untvailable. Because FOR THE MATERIALS ENGINEERING BRANCH DIVISION OF many safety systems required for reactor core decay heat re-ENGINEERING. Annual Report For FY 1987.

• Matenals Engi- moval and containment heat removal depend on ac power, the neenng Branch. June 1988. 425pp. 8807110528. 46083.319- consequences of a staten blackout could be severe. Because This report presents summaries of the research work per. of the concern about the frequency of loss of offsite power, the formed dunn0 fiscal year 1987 by laboratones and organizations number of failures of emergency diesel generators, and the po-

, under contracts administered by the NRC's Materials Engineer

• tentally severe consequences of a loss of all ac power, "Sta-ing Branch, Office of Nuclear Regulatory Research. Each con- tion Blackout" was designated as Unresolved Safety issue (USI) t tractor has wntten a more complete and detailed annual rcport A-44. This report presents ihe regulatory /backfit analysis for

• of their work which can be obtained by wnting to NRC; howev- USI A-44, it includes (1) a summary of the issue, (2) the recom.

er, we beheve it is useful to hsve a summary of each contrac* mended technical resoluton, (3) alternative resolutons consid-tor's ef1 orts for the year comt>ned into one volume. ered by the Nuclear Regulatory Commission (NRC) staff, (4) an NUMEG 1002 S06: SARiY EVALUATION REPORT RELATED assessment of me befits aM coMs of m reconne e TO THE OPERATION OF BRAIDWOOD STATION, UNITS 1 olum (5) m Mn ratona% @ m maw @ Wm USl A-44 and other NRC programs and requirements, and (7) a AND 2 Docket Nos. 50-456 And 50-457.(Commonwealth Edison backfit anatysis demonstrat.ng that the resoluton of USl A-44 [

Company)

• Dreson of Reactor Projects IllIV,V & Special comphes with the backfit rule (10 CFR 50.109).  ?

Projects (Post 870411). June 1988. 29pp. 8807060087.

46002:338. NUREG 1125 V09: A COMPILATION OF REPORTS OF THE AD- l In November 1983, the staff of the Nuclear Regulatory Com. VISORY COMMITTEE ON REACTOR SAFEGUARDS.1987 messon issued its Safety Evaluaton Report (NUREG 1002) re- Annual.

• ACRS Advisory Committee on Reactor Safeguards.

garding the application filed by the Commonwealth Edison Com- April 1988.137pp. 8805030096. 45342:247.

pany, as applicant and owner, for a beense to operate Braid- This compilation contains 47 ACRS reports submitted to the wood Staton, Units 1 and 2 (Docket Nos. 50 456 and 50-457). Commission or to the Executrve Director for Operatons dunng The first supplement to NUREG 1002 was issued in September calendar year 1987, it also includes a report to the Congress on 1986; the second supplement was issued in October 1986; the the NRC Safety Research Program for FY 1988. All repor's i third supplement was issued in May 1987; the fourth supple- have been made available to the pubhc through the NRC Pubhc ment was issued in July 1987 in support of the fuii-power 16* Document Room and the U.S. Library of Congress The reports 4

cense for Unit 1; the fifth supplement was issued in Decembe' are c'rvided into two groups: Part 1: ACRS Reports on Protect 1987 in supp;rt of the low power heense for Unit 2. This sixth p,y,ews, and Part 2: ACRS Reports on Genenc Subects. i Part i supplement to NUREG 1002 is in support of the full. power k. 1 contains ACRS reports alphabetired by project name and i

cense for Unit 2 and provides the status of items that remained within protect name by chronological order. Part 2 categonzes .

unresolved at the time Supplement 5 was pubhshed The facilit) the reports by the most appropnate genonc subject area and I is located in Reed Township, Will County, Ilhno+ within subject area by chronological order  ;

i l

l,

I i 4 M;in Citati:ns and Abstracts  :

NUREG-1214 R03: HISTORICAL DAT A

SUMMARY

OF THE SYS- NUMEG 1226: DEVELOPMENT AND UTILIZAT!ON OF THE NRC TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE. POLICY STATEMENT CN THE IJGULATION OF ADVANCED i PERSINKO.D. Orvision of Licensee Performance & Ovahty Eval. NUCLEAR POWER PLANTS. WILLIAMS.P.M.; KING,T.L. Offee i uaten (Post 870411). May 1988, 78pp. 8805260374. of Nucim Regulatory Research. Director (Post 860720). June l 45632 048. 1988. ' epp. #?% 3 /. 46013-217. .

l The Histoncal Data Summary of the Systematic Assessenent On March 26,1965, the U.S. Nuclear Regulatory Commission of Licensee Performance (SALP) is produced penod+cally by the issued for pubhc comment a "Proposed Policy for Regulaten of U.S. Nuclear Regulatory Commission. This summary provides Advanced Nuclear Prwer Plants" (50 FR 11884). This report l' the results of the assessmer't for each facihty by NRC Region presents and discusses the Commission's final version of that and is further dmded into the following three seCtons: Section 1 policy as titled and published on Juiy 8,1936 "Regulaton of presents the most recent SALP report ratings for facdities ,,inder Advanced Nuclear Power Plants, Statement of Polcy" (51 FR

construction and in operaton. Secten 2 presents a chronologi- 24643). It provides an overview of

omments recerved from the  !

cal lerng of all SALP report ratings for each operabng facility- public, of the sigrwficant changes from the proposed Polcy l 3] Sec. .,n 3 presents a chronologcal hsbng of all SALP report rat. Statement to the find Policy Statement, and of the Commis.  !

l ings for each facihty under constractiort For historical purposes, tion's response to six questions contained in the proposed l past constructen SALP ratings for facihties that recently have Polcy Statement. The report also dscusses the definition for j been hcensed also are listed in Secten 3. advanced reactests, the establishrnent of an Advanced Reactors veUREG 1217 DRFT FC: EVALUATION OF SAFETY r,4 PLICA- Group, the staff review approach and information needs, and N umaton of tM pow Staternent m miate to othw NRC t TIONS OF CONTROL SYSTEMS IN LWR NUCLEAriPOWER Fograms, M*g N pohcies W safeh goa4, sem a@

PLANTS. Technical Findings Related To Unresolved Safety l$ sue A 47. Draft Report For Comment. SZUKIEWIC2 A.J. C;vi- dents and standardizaton. In addition, guidance for advanced  ;

sion of Engineenng (Post 870413). April 1988. 73pp. mac ors s opwatmg enem, tWe M.  ;

' opment, foreign infcematon and data, and prototype testing is .

8805260301. 4563(085 This report summanzes the work performed by the Nuclear provided. Finalty, a discussion on the use of less presenptrve Regulatory Commission staff and its contractors. Idaho Natonal and nonprescriptive design enteria for advanced reactors, which Engineenng Laboratones (INEL), Oak Ridge Natonal Laboratory the Pohey Statement encourages,is presented. ,

(ORNL), and Pacific Northwest Laboratory (PNL), leading to the proposed resolutbn of Unresolved Safety issue (USI) A-47, NUREG 1232 W2: SAFETY EVALUATION REPORT ON TEN-Saft:'/ Implicatons of Controi Systems. An in-depth evalua- NESSEE VALLEY AUTHORITY, Sequoyah Nuclear Perform- f hon was performed on non- safety grade control systems see ance Plan.

• Ofc of Special Projects. May 1988. 362pp. '

8805260367. 45659.001' o four ear steam em S ) p an a Genera ctr This Safety Evaluation (SER) on the information submitted by l

i Compary (GE) boshng water reactor (BWR), a 3-loop Westing- the Tennessee Valley Authonty (TVA) in its Sequoyah Nuclear ,

3 house (W) pressunzed-water reactor (PWR) design, a once- Performance Plan, through Revision 2, and suprorting docu- F through steam generator PWR designed by Babcock & Wilcox ments has been prepared by me U.S. Nuclear Regulatory Com-i Co. (B&W). and a Combustion Engineenng (CE) PWR design. m,&sion staff. The Plan addresses the plant specific concerns  :

This report describes the technical studies performed by the requiring resoluton before startup of either of the Sequoyah  !

I taboratones, the NRC staff assessment of the results, the ge- units. In partcular, the SER addresses reovired acbons for Unit '

nene apphcabihty of the evaluatons, and the technical findings 2 restart. In many cases, the programmate aspects for Unrt 1 resutting from these studies. are identied to those for Urut 2, the staff will conduct inspec-tons of implementaten for those programs. Where the Urvt 1 i NUREG 1218 f>RFT FC: REGULATORY ANALYSIS FOR PRO. program is different, the staff evaluation wdl be provided in a  !

POSED RESOLUTION OF USt A-47. Safety Imphcatons Of supplement to this SER. On the basis of its review, the s'.aN  !

Cor' trol Systems Draft Rept For Comment. SZUKIEWICZ,A.J. concludes that Sequoyah specife issues have been resolved to Division of Engineenng (Post 870413). Apnl 1988. 82pp. the extent that would support restart of Sequoyah Urvt 2. ,

8805260236. 45631:014. [

This report presents a summary of the regulatory anatysis NUREG 1233 DRFT FC: REGULATORY ANALYSIS FOR U$l A-  ;

4 conducted by the NRC staff to evaluate the value impact of al. 40, "SEISMIC DESIGN CRITERIA." Draft Report For Comment. -

i ternatives for the resoluton of Unresolved Safety issue (USI) A. SHAUKAT,S.K.; CHOKSHl,N C.; ANDERSON,N R. Dmson of '

j 47, "Safety Impications of Control Systems." The NRC statt Engineering (Post 870413). April 1998. 53pp. 8806060019. i proposed resoluton is based on these analyses and the techrg. 45726.031.

cat findings and conclusons presented in NUREG-1217 The This report consists of a regulatory analyses for Unresolved

] staff has concluded that certain actons should be talien to im. Safety Issue (USI) A 40, "Seisme Design Cntena

• The reguta-4 prove safety in hght water reactor (LWR) plants. The actions tory analysis discusses the impact of the proposed changes in

recommended that certain plants upgrade their control systems the Standard Rev;ew Plan (SRP) Sectons 2.5.2, 3.7.1, 3.7.2 and i

to preclude reactor vessel / steam generator overidt events and 3.7,3 (NUREG-0800).

to prevent steam generator dryout, modify their technical speci-ficaton to penodicalty venty operabikty of these systems, and NUREG 1266 V02: NRC SAFETY RESEARCH IN SUPPORT OF modify selected emergency procedures to ensure plant safe REGULATION 1987.

• Offee of Nuclear Regula en Research, j Shutdown following a small. break loss.cf. coolant accident. Director (Post 86n720). May 1988. 59pp. 405200095.

, 45549 327.

j NUREG 1221: SUYMARY, ANALYSIS AND RESPONSE TC This report, the third in a senes of annual reports, was pre-PUBLIC COMMENTS ON PROPOSED AMENDMENTS TO I's pared in response to congressonal inquines concerning how j CFR PARTS 30.40,50,51,70 AND 72: DECOMMISSIONING nuclear regulatory research is used. It summan2es the accom-T CRITERIA FOR NUCLEAR FACILITIES.

• Dmson of Engineer- phshments of the Of* ice of Nuclear Regulatory Research dunng ing (Post 870413). June '988. 600pp. 8807060104. 46000182. . 1987. The goal of this office rs to ensure that research provides l In February,1985, the NRC issued for pubic comment pro- the techncal bases for rulemaking and for related decisons in posed rules on decommissioning of nuclear facdities. Comment support of NRC heensing and enspecton actmties. This report I letters were received from 143 organizstions and indviduals. desenbes both the direct contnbutons to scient fc and technical j This report provdes a summary and anahsis and response to knowtedge with regard to nuclear safety and their regulatory ap.

4 the pubhc comments receiv3d phcatons.

1 i

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1 i Main Citations Cnd Abstracts 5 1

NUREG 1273: TECHNICAL FINDINGS AND REGULATORY (STP), Units 1 and 2 (Docket Nos. 50-498 and 50-499). located i ANALYSIS FOR GENERIC SAFETY ISSUE II.E.4.3, "CONTAIN. in Matagorda County, Texas. These aflegatons were provided MENT INTEGRITY CHECK." SERKlZ,A.W. Division of Reactor to the NRC by the Government Accountabikty Project (GAP) l & Plant Systems (870413-880716). Apnl 1985. 170pp. wNch received them from apptrmmately 35 current and former  !

l 8805030120.45343.024. employees of STP, and covered a wide range of concerns with TNs report contains the technical fadings and regulatory hardware and Quakty assurance and ctYtrol, and issues of man.

anafysis for Generic Safety issue 11 E.4.3, "Containment integnty agement, harassment and intnadat on and wrongdoing. Only Check An evaluaton of the contatnrrunt isolat>on history from those concerns considered by the SSAT to be technically ori- l 1965 to 1983 reveals that (except for a small number of events) ented were selected for review based on their possble safety '

containment ir;tegnty has been maintained and that the me)0nty signifcance. generic imphCations, specificity to a partcular plant l of reported events have been events related to exceedog component, system or structure, and to provide a muttadisciphne Technical Specifcaton kmits (or 0.6 times the allowable leak. overview of the implemantaten and effectiveness of the STP

age level). In ae.diton, more recent nsk tr,tlyses have shown Quahty Assurance Program. The SSAT review of GAP's allega.

that allowable leakage rates even if increasea by a f actor of 10 tons has identfied no substantive safety Msue that would war.

would not signifcantty increase nsk. Potential method of contin- rant delay in the NRC't consideraton of a full-power hcense for  ;

vous monitonng are identified and evaluated. Therefore, these STP Unit 1.

techncal findings and r:3k evaluatons support closure o' Gener.

ic issue ll E.4.3. NUREG 1300: RADIOACTIVE MATERIAL IN THE WEST LAKE LANDFILLSummary Report.

• Drvision of Industrial & Med4 cal NUREG.1283: SAFETY EVALUATION REPORT RELATED TO Nuclear Safety (Post 870729). Apnl 1988. 22pp. 8805090165.

THE RENEWAL OF THi! OPERATING LICENSE FOR THE RE* 45412:328.

SEARCH REACTOR AT PURDUE UNIVERSITY.

• Standardiza. The West Lake Landfill is located near the city of St. Louis in bon & Non-Po.ver Reactor Project Directorate. April 1988.69pp. Bndgeton, St Louis County, Missouri. The site has been used 8805090116. 45432:303. since 1962 for disposing of municipal refuse, industrial sohd and This Safety Evaluation Report for the apphcation filed by hqdd wastes, and construct >on demo 6 ton debns. TNs report

, Purdue Urvversity for a renewal of Operating Ucense R-87 to summanzes the circumstances of the radcactve material found .

i continue to operate a research reactor has been prepared by in the West Lake Landfill. Pnmary emphasis is on the radologi-the Office of Nuclear Reactor Regulaton of the U.S. Nuclea' cat environtr, ental aspects as they relate to potental dispositon j Regulatory Commission. The facihty is owned by Purdue Unrver.

of the material trty and is located os the campus in West Lafayette, Indiana. ,

On the basis of its technical review, the staff concludes that the NUREG 1311: FUNDING THE NRC TRAINWG PROGRAM FOR reactor facility can continue to be operated by the 'Jniversity STATES. LUBENAU J.O.; CORLEY,J.H.; KAMMERER.C. State, without endangering the health and safety of the pubhc or the local & Irdan Tnbe Programs. June 1988. 77pp. 8807070455.

envronment. 46011 176. ,

NUREG.1296: THERMAL OVERLOAD PROTECTION FOR ELEC. On February 3,1988, the Commission received a briefing on TRIC MOTORS ON SAFETY RELATED MOTOR-OPERATED the State, Local 2nd ino6an Tnbes Programs of the NRC Offee VALVES GENERIC ISSUE 11 E.6.1. ROTHBERG.O. Division of of Governmental and Pubhc Affairs. The bnefing included dis-

, Engineenng (Post 870413). June 1988. 51pp. 8807110511. cusson of the Agreement State program and, more particularty, 46083.122. the training provided to StSte personnel to help them maintain

, The NRC regulatory positions, as stated in Regulatory Guide programs wNch are adequate to protect pubhc health and i

1.106, Revision 1, have been identfeed by the Office for Anaty, safety and compatible with the Commission's program. The

ses and Evaluaton of Operatonal Data (AEOD) as potential con- Commission endorsed the NRC State training program but tnbutors to vatve motor burnout. AEOD is partcularty concerned questoned the long. standing practce of paying the travel and

, about the atlowed pohey of bpassing thermal overload devices per diem of State persorsel approved to attend the NRC spom l during nortnat conditons. Regulatory Guide 1.106 favors com. sored training The staff was requested by the Commission to 1 promising the function of thermal overioad devices in order to provide a report on tNs aspect. This report is the staff's re-i

^

avoid interfenng with the safety-related operabon of motor-oper. sponsa it includes an evaluaton of the practce of funding ated valves. This report desenbes thermal overioad devices and State travel and per diem costs for personnel attending NRC ther use It is concluded that the pohcies stated in Regulatory courses and other optons to make tNs program more cos' ef-Guioc 1.106 are technically correct and allow suffcent flexibehty fective including utikring wWever poss ble manifial cost Fwder-to attow the use of thermal overload protecton without interfer, al and commercal trairung facdities.

ing with safety related functions of motor-operated valves. How-ever,it appears that heensees are needlessly bypassing or oth. NUREG 1318: TECHNICAL POSITION ON ITEMS AND ACTIVI-erwisc compromising the use of thermal overload protecton. TIES IN THE HIGH LEVEL WASTE GEOLOGIC REPOSITORY Some ;icensees are using inadequate design practces to size PROGRAM SUBJECT TO QUALITY ASSURANCE REQUIRE.

thermal overlond devices. The problem of valve motor burnout MENTS. DUNCAN,A.B.; BILHORN.S G,; KENNEDY,Jt. Drvison is related to a lack of standards and uniform guidance for the of High Level Waste Mana9ement IPost 870413). Apnl 1988.

design, instaflaton, maintenance, and testing of motor overload 8% '

nt provide guidance on how to identify items protective devices. The NRC's Office of Nuclear Regulatory Re-

, search will contact several nuclear standards organizatens to and actrvibes subject to Quality Assurance in the Ngh-level nu-clear waste repository program for pre-closure and post-closure mot v be eve o phases of the reposery. In the pre-closure phase, structures, systems, and compoets essentat to the prevenbon or mitiga-NUREG 13% NRC SAFETY SIGNIFICANCE ASSEESMENT ton of an accident that could result in an off-site radiabon dose i TEAM REDORT ON ALLEGATIONS RELATED TO THE SOUTH of 0.5 rem or greater are termed "important to safety." In the TEXAS PROJECT, UNITS 1 & 2.

• Dreson of Reactor Projects - post closure phase, the bamers wNch are reled on 'o meet the til,lVV & Specal Projects (Post 870411). March 1988.151pp. containment and isolaton requwemerits are defined as "impor-8804280527.45274:151, tant to waste isolaten." These structures, systems, compo-

{ TNs report provides the results of a review by the Safety Sig- nents, and t>arrers, and the actrv1 ties related to their character.

nifcance Assessment Team (SSAT) of the Nuclear Regulatory iraton, design, constructon and operaton are required to meet Commisson (NRC) of aneged construebon irregulanties at quahty assurance (OA) enteria to provide confidence in the per.

Houston Lighting and Power Company's South Texas Project formance of the geologic repository. The list of structures, sys-1 1

4

i 6 Main Citations and Abstracts tems, and components important to safety and engineered bar- assay, correlaton of unnary uransum samples with at samphng nors important to waste isolaton is referred to as the "O List" resutto in industnal settrngs, delayed neutron count ng, laserM-i and Ises ethin the scope of the Q A program. nebc phosphometry, isotope diluton mass spectrometry, reso-l NUMEG 1320: NUCLEAR FUEL CYCLE FACILITY ACCIDENT nance Maton spectroscopy, hsse vack anaWs, lasere ANALYSIS HANDBOOK. AYER.J E.; CLARK A.T.: LOYSEN,P.; duced fluoresence, and costs of sampling and processing. The et al. Dreson of Industrial & Medcal Nuclear Safety (Post nsne presenta%ns of the second meebng, on December 4, 870729) May 1988. 300pp. 8806100179. 45788.258. 1985, dealt mth the nephrotoxicity of uramum. Among the The Nuclear Regulatory Commission (NRC) has sponsored a topecs were the physiology of the kdney, the effects of heavy research program to develop improved methods for realisteally metals on the kdney, animal stud >es in uramum nephrotoxicity, evaluabng the consequences of major accdents in nuclear fuel Comparisons of k dney Nstology in rune humans, renal effects in i

i cycle facilsbes. These methods, along with supportng informa, uramum mill workers, renal damage from d Herent uranium iso-ton and illustratrve examples are provided in tNs handbook topes, and Canadian studies on uranium toxicrty. Discuss 4ons Four types of faciht>es: fuel manufactunng, fuel reprocessing, f0D*o9 th* P'esentatens are italuded in the edted tran-waste storage and soldifcaton, and spent fuel storage; and six 8CfiPl8-accdent typea fos, explosions, spdis, tornadoes, nuclear ent" NUREG/CR 2000 V07 N3: LICENSEE EVENT REPORT (LER) calites, and equrpment fritures, are covered. Both computer COMPIL/iTION.For Month Of March 1988.

• Oak Rdge Naton-and hand calculations are presentM to esbmate the source al Laboratory. Apnl 1988.163pp. 8805090093. ORNL/NSIC-term from potential accdents. TNS source term informabon is 200. 45412.001, used as input to computer codes which calculate the trar@ ort TNs monthly report contains Licensee Ennt Report (LER) and release of mass, energy, and material throughout the facth- operatcnal informaton that was procesfed into the LER data ty and to the envronment.

file of the Nuclear Safety information Center (NSIC) dunng the NUREG 1325: DISPOSITION OF RECOMMENDATIONS OF THE ons month penod identAed on the Cover of the document. The N ATIONAL RESF. ARCH COUNCIL IN THE REPORT "REVITAL- LERs, from which this informabon is de1ved, are submitted to IZING NUCLEAR SAFETY RESEARCH." ' Offee of Nuclear the Nuclear Regulatory Commisson (NRC) by nuclear power Regulatory Research, Director (Post 860720). June 1988. 43pp. plant licensees in accordance with federal regulabons. Proce-8807060093.46002:293. dures for LER toorung for revisons to those events occurring On December 8,1986, the Cornmittee on Nuclear Safety Re. pnot to 1984 are desenbed in NRC Regulatory Guide 1,18 and search of the Natonal Research Courcl submitted its report, NUREG 1061, "Instructons for Preparabon of Data Entry "Revitakzing Nuclear Safety Research," to the U.S. Nuclear Sheets for Licensee Event Reports." For those events occurnng Regulatory Commisson (NRC). The Commesson and its staff on and after January 1,1984, LERs are being tut % in ac.

I have carefulty reviewed the Comrnettee's report and have exten- cordance with the revised rule cont:rined in Title 10 Part 50.73 i srvery examined the planmng, implementation, and management of the Code of Federal Regulatons (10 CFR 50.73 Licensee of NRC research programs in order to respond most effectively Event Report System) which was pubhshed in the Federal Reg-to tree Committee's recommendabons. This report presents the ister (Vol. 48, No.144) on Jufy 26,1983. NUREG 1022, "Lh Commesson's view cf the Committee's report and describes the consee Event Report System Desenpton of Systems and actons that are under way in response et its recommendatons. Guidelines for Reportng," provides supporting guidance and in-NUREG/CP-0075: PROCEEDINGS OF CSNt/NRC WORKSHOP formaton on the revised LER rule. The LER summanes in this ON DUCTILE PIPING FRACTURE MECHANICS.

report are arranged afphabetcCfy by facility name and then t KANNINEN.M.F. Southwest Research inst:tute. May 1988. chronologically by event date for each facility. Component, t 164pp. 8807110512. CSNI 97. 46082:3 t 8. system, ks; word, and component vendor indesca follow the This report contains the papers presented at a workshop summanes. Vendors are those identified by the utility W. the mechng that was conducted to compare the vanous different LER form is imbated, the keywords for the componer', system, elasic plaste fracture mechanics anatysis methods that can be and general keyword inderes are assigned by thr, computer j applied to assess the margin of safety in cracked nuclear plant using . srelaton tables from the Sequence Coding and Search pipes. A specific problem a cacumferentalty cracked Type 304 System.

stainless steel pipe in combined axial tension and bending was NUREGIC%2000 V07 N4: LICENSEE EVENT REPORT (LER) addressed. The appbed bending rnoments at crack growth inct" COMPILAMN For Month Of Apnl 1988.

• Oak Rdge Natonal aton and at fracture instabihty were sought Seven estimaton Laboratory. May 1988.132pp. 8806020043 ORNL/NSIC-200 type solut.ons eve per4ormed along with a benchmark elastc* 45706:089.

j plastic fato element ;olut nrt it was learned that precise spech See NUREG/CR 2000,V07,N03 abstract.

i ficaton of the muenal st. ass strain curve must be made to obtain meaningtu; resutts. But, when applied under controlled NUREG/CR 2000 V07 N6: LICENSEE EVENT REPORT (LER) condatons, the detterent estimaton method solubons do provide COMPILATION For Month Of May 1988. ' Oak Rdge Natonal reasonably consistent resutts. These resutts appear to be con- i.aboratory. June 1988.147pp. 6807110514. ORNL/NSIC 200.

servatrve in companson with an elastic-plasbc finite element so- 46083:169.

tuton that was performed to provde a compansan wrth these See NUREG/CR 2000,V07 NO3 abstract.

NUREG/CR 3609: POWER SPdCTRAL DENSITY FUNCTIONS i NUREG/CP 0093: PROCEEDINGS OF THE MEETING ON UL- COMPATIBLE Wi1H NRC REGULATORY GUIDE 1.60 RE.

] TRASENSITNE TECHNIQUES FOR MEASUREMENT OF URA- SPONSE SPECTRA. SHINOZUKA.M ; MOCH 3,T.:

NIUM IN BIOLOGICAL SAMPLES AND THE NEPH90 TOXI. SAMARAS.E F. Columbia Univ., New York, NY. June 1988 CITY OF URANIUM KATl;REN.R L; WEBER.J R. Battelle Me- 71pp. 8807080360. 46077:033 monal Institute, Pacific Northwest Laboratory. Apnl 1981 172pp. Among other possMtes, the Kanai-Topmi power spectral 8805260245 PNL 6511. 45632120. density enhanced at the h1.t frequency range is found to be Edited transenpts are provded of two pubhc meetings spon- useful for generatng ground acceleraton time histores that sat.

sored by the Occupatonal Radiaton Protecten Branch of the isty NRC RG 1.60 requirements. The values of the parameters

, Divison of Radiation Programs and Earth Sciences, Nuclear involved in the spectral densrty functon are recommended for l Regulatory Commisson. The fast meeting, held on December 3, this purpose. Also, a suggestion is made as to in what way the j 1985, included nine presentatens covenng uttrasensitive tech- power spectral density requwements can be placed in combina-3 rwques for measurement of uranum in biological specimens. ton with those of the current NRC RG 160 to ensure both the Topics irntude laser spectrometnc techniques for uranium be- response and power tpectrum requvements.

i

[  ;

I {

1

- - _- .=- - - - -- - -. ._ . -._~

l h

i Main Citations and Abstracts 7 i

I NUREG/CR 3499 S01: UTILITY FINANCIAL STABILITY AND mal shock technology. (11) Pressure Vesset Research Users'

, THE AVAILABILITY OF FUNDS FOR DECOMMISSIONING.An Facility, and (12) shippmg-cask matenal evaluatons.

j Analysas Of Intemal And External Funding SIEGELJ.J. Eng" Ec m Research, Inc. June 1988. 38pp NUREG/CR 4315 V09 RI: EVALUATION OF NUCLEAA FACILI.

l TY DECOMMISSIONING PROJECTS. Summary Status The NRC Is currently developing feal rules in the area of de- Report,Three M,le Nand Unit 2,Radcactive Waste And undry commissoneg nuclear facihtos. A part of that rutemaking ettort Shtpments. DOERGE,D.H.; HAFFNER,0 R. Westinghouse Han.

i is assunng that funds will be avaitable at the time of decommis- tord Co. June 1988. 48r,. 8807110504. 46085:120,  ;

j soning of power reactors. Prevous NRC reports, ocluding TNs document summanzes informaton concemeng redcac-NUREG/CR 3899, pubbshed September,1984, have examined trve waste and laundry shipments from the Three Mile Island [

] Nuclear Staton Unit 2 to radioactrve waste disposat sites and to i this issue by studyng vanous furung methods. This report pro-vides an update by considenng pubic comments received on rotective clotNng decontammaton facikbes (taundnes) since

, the loss of ccotant acodent expenenced on March 28,1979- i the NRC's proposed rule on decomrrassionsng (pubkshed Febru-Data were collected from radioactrve shepment records, summa-ary,1985) and by analyrng the retabve hvel of assurance of rized, and placed in a computenzod otormation retneval/ manip.

j internal and extemal reserves. In its analysis, the report makes use of specific case utikty financial situatons. The report con- ufaton system whch permits extraction of specife informaton ciudes that from a financial standpoent, *1th the exception of as requwed. Informaton contained in tNs report includes: waste PSNH, internal ref ress currently provide suffeent assurance dis osal arte locatons, dose rates Cune content, waste descrip-of funds for decomrmsoneg The report also concludes that tion, container type and number, volumes and weights.

i the NRC should recommend changes in bankruptcy laws, in- NUREG/CR 460k TRAIN'NG MANUAL ON STATISTICAL METH-ciuding decommissionmg obligatons m utikty prospectuses, and ODS FOR NLCLEAR MATERIAL MANAGEMENT. JAECH.JL s onduct perodic financtal reviews of nuclear utikties due to Batteile Memorial Institute, Pacific Northwest Laboratory. Apnl

. ungmg econome cordtions. 1988. 450pp. 880623020/, PNL 5855. 45896:128.

NUREG/CR 4042 V06: DEGRADED PIPING PROGRAM PHASE ms traming manual on stawicat mem W nuckar mau ILSixth Program Repo,t October 1986 - September 1987, a a s P ' '

WILKOWSKI,G Ma AHMAD,J.; BARNES,C.R.; et al. Battelle Me- al M thod f a atw a( ns me edited by W. Mchael Bowen and Carl A. L Stt. The training morial Institute, Columbus Laboratones. Aprd 1988. 333pp.

manual follows the reference book in its termaclogy, notaton .

l ed n is an An al eport of the U.S, NRC's De- aM memc@@ H is WW to be und mm me reWee i graded Piping .ogram . Phase il This is tf.e sixth program as a g@ h se%acM Mnm M as a #m  ;

I report on this program. Pnor reports were sem3 annual rsports.

manual formal mses a stames on hs suW H cm 2

Tt,e intent of this program es to experimentatty validate and en-se d a uber of example problems for each chapter, follow-hance avadable analybcal methods for evaluateg the mechani- 9 O*N8* I* ** **

• aal behavior of nuclear powet plant piping contaming cacumfer-aH Met N mawial is pennW e %sNeaf Wm em entially onented defects. Fifty-seven pipe expenments have each problem and soluten starting on a new page so that 6n 4 been conducted to date. These and approximately fifty additen- cpeon e us page 2 M mus N We W <

be handed the ciass participants fsst and the solutions later.

l al pipe expenments from other programs have been anatyred.

J In the ana'ytcat effort, a screening entenon has been devel- NUREG/CR 4439 V01: NUCLEArt COMPUTERIZED LIBRARY oped to show when the net secton collapse ana'ysis is vahd FOR ASSESSING REACTOR REllABILITY (NUCLARR). Volume This shows that even tough matenals such as stainless steel 1 Summary Desenption. GERTMAN.D.l.: G'LMORE.W Ea l i can fait at less than net secton-collapse loads rf the pipe diam- GALYEAN,WJ : et al. EG&G Idaho, Inc. (subs. of EG&G, Inc )  !

3 eter es sufficientt large. Numerous preds trve J estimaoon February 1988. 30pp. 8805090146. EGG 2458. 45413:043

, schemes Pave been evaluated and modifed. A f nite length sur- A data management system has been emplemented which j face cracked pipe estimaton scheme tss also been developed supports a vanety of nsk-related analyses and prowdes a repos.

and incorporated into a computer code called NR&PE. TNs story of hardware component failure and human error probat>lity 3

code prowdes a convenient way of anatyreg cracked pipe mth data to the riek analyst. The Nuclear Computenred Library for a number of evrently accepted anatytcal methods Supporting Assessing Reactor Reliability, NUCLARR, is an interactive,

] research efforts involve investigating geometry effects on J R graphically onented system whch resides on a personal com- [

q curves, as well as charactenzing the matena; proWes for puter (PC) or PC-compatible enwronment. An overview of the 1 '

each pepe tested The significance of att of the effvrts to date data management system, including a description of data col-relative to pipe fracture arWysee and flaw assessment entena lecten, specificaton, data structure, and taxonomies, is present-

! are discussed. ed in Volume i of this report Programming actmties, procedures ,

j NUREG/CR 4219 V04 N2: HEAVY SECTION STEEL TECHNOL. a [pr senQn V du I hV d

OGY PROGRAM Semiannual Progress Report For Aprd-Sep- -

tember 1987. CORWIN.W.R. Oak Ridge Natonal Laboratory. NUREG/CR 4445: CLOSEOUT OF IE BULLETIN 83 08 ELECTRI-Aprd 1988. 336pp 8806020048. ORNL/TM 9593. 45705:113. C AL CIRCUlT BREAKERS WITH AN UNDERVOLTAGE TRIP The Heavy Section Steel Technology (HSST) Program is an FE?.TURE IN USE IN SAFETY RELATED APPLICATIONS  :

I engineenng research actmty conducted by the Oak Ridge Na- OTHER THAN THE REACTOR TRIP SYSTEF.'. FOLEY,WJa l tonal Laboratory for the Nuclear Regulatory Comrmsson. The DEAN R.S.; HENNICK.A. Parameter, Inc. Aprd 1988, 4 tpp.

J Program compnses studies related to all areas of the technolo- 8805090133. PARAMETER IE182 454t3.001.  ;

) gy of matenals fabncated into thick section pnmary coolant con- The NRCnF sued Bunetin 83-08 December 28,1983 be-l tainment systems of light water-cooled nuclear power reactors causi of concern about cecut breaker defoencies reported per '

The investigston focuses on the behaver and structural integn- prevous bulletins 83 01 and 83-04 The object of IEB 83-08 r ty of steel pressure vessels continuing cracklike flaws. Current was to assure proper operation of creut breakers eth under- ,

work is organized into twelve tasks: (t) program management, vettase tnp attachments (UVTAs) in all safety-related apphca. ,

(2) fracture methodology and analysis (3) matenal charactenza. tons other than use as reactor tnp breakers (RTBs). The bulle-tion and properties (4) enwronmentally assisted crack-growth tin was issued for acten to alt licensees and holders of con-stud,es (5) crack arrest technology, (6) rrataton effects stud. structon permits of power reactors. Evsbaton of utility re-ies. (7) ciadding evaluatons, (B) intermediate vessel tests and sponses W NRC/ Region inspecton reports shown that the analysts, (9) thermal-shock technology, (10) pressunzed ther, bulletin can ne closed out per speatic entena for 123 (99%) of i

. . - . _- - - . - __ . _ _ - - _ . . . ~_

i i  !

s Main Citations and Abttracts I the 124 facilites to wtWCh it was issued. A followup item is pro. envronmentatty. assisted cracking of AISI 1020 steel at elevat-

! posed for use by the NRC to assure completon of reovired ac- ed temperatures (150 degree C). For the proposed satt site, the j tons at the remairung facihty. Crcuit breakers with UVTAs were importance of the d9taten of corrosson tasts and conditaons that used in safety related appheatons other than the reactor tnp may preclude prompt initiaton of long term testing are die-i system b sin (6) faceties. Malfunctons of the UTVAs were re. cussed. NBS work related to vitnficaten of HLW borossicate ported ordy for the facihty for which followup is proposed. glass at the West Valley Demonstraten Protect (WVDP) and at NUREG/CR 4474 V05: PRECURSORS TO POTENTIAL SEVERE the Defense Waste Processing Facshty (DWPF) is discussed.

CORE DAMAGE ACCIDENTS.1986,A STATUS REPORT, Achwties of the Matenats Charactertraton Center (MCC) are ,

MINARICK.J.W.; HARRIS,J D.; AUSTIN.P.N.; et al. Oak Ridge presented. To stress the necessity of independent data interpre. ,

, Natonal Laboratory. May 1988.183pp. 8805260278. ORNL/ tatens, an F straton is given of a concluson drawn from pub. '

NOAC 232. 45650 260. lished data that is different from the concluson reached by the (

I Thaty five operational events, reported in licensee event rc investigator, ,

! ports and occumng at commercial LWRs dunng 1986, are con- MENT SURVIVAL

-' JUREG/CR 4763: SAFETY RELATED

, sidered to be precursors to potenhal severe core damage. IN HYDROGEN BURNS IN LARGE Dt.. . WR CONTAINMENT t These are desenbed along with associated s>gnificaree est" BUILDINGS. KING,0.8.; NICOL 2TTECF; DANDINI,V.J.; et al. >

mates, categonzaton, and subsequent analysas. This stuO #s a Sandia Nabonal Laboratories. March 1988.299pp.8804280588.

conbnuaton of earlier work, which evaluated the 196M981 ao 1984 1985 events. The report discusses (1) the general raNn. SAND 864280. 45272:099 ale for this study, (2) the se'ecton and documentaton of events Anatyteal and expenmental investigatons of equipment sur-as precursors, (3) the estim. ton and use of con 6 tonal prob- vaal in hydrogen burns in large dry PWR conta:nment buddings

, have been conducted. Both atmosphenc and subatmospherc

abdities of subsequent severe core damage to rank precursor

! events, and (4) the initial conclusions from the assessment of containments were considered. Two sets of anatytical studies l 86 ents and from the collective assessment of 1984 1986 were camed out for atmosphenc large dry containments. One set anatyred the hydrogen burn that occurred as a resutt of the March 1979, accident at Three Mile island The other set cork NUMEG/CR 4474 V06: PRECURSORS TO POTENTIAL SEVERE sid3 red a hybnd power plant consatng of the Zon reactor CORE DAMAGE ACCIDENTS:1986.A STATUS REPORT- housed in the TMI-2 cor tainment building. An analytcal study of MINARICK.J W.; HARRIS.J D.; AUSTIN.P.N.; et al. Oak R4ge subatmospheric containments was also carred out using a Natonal Laboratory. May 1988. 315pp. 8805260286. ORNL/ model of the Surry nuclear power plant. To complement the NOAC 232. 45631:093. analyses, a series of expenments simulating hydrogen burns in See NUREG/CR 4674,V05 abstract. targe dry containments was also conducted using the Sandia ,

i NUREG/CR 4720: EOUlPMENT QUALIFICATION RESEARCH severe combined envronmeni test chambor (SCETCh). The ex.

TEST OF A HIGH RANGE RADIATION MONITOR. penments investgated the survivability of thermalty and radi-RICHARDS.E.H.; JACO6US M.J.; DROZDA.P.M.; et al Sand a aton aged nuclear qualSed Brand Rex power and cmtrol cable National Laboratonts. February 1988. 64pp. 8806230158. and a Barton 763 pressure transrutter in a simulated LOCA/hy.

, SAND 86-1938. 45898.305. drogen bum envronment. .

steam and vi m t must s t s NtJREG/CR 4f77: STEAM OXIDATION OF ZlRCALOY CLAD-of coolant accdent (LOCA) to assess possible synergiste ef. DING IN THE ORNL FISSION PRODUCT RELEASE TESTS.

fects that may be rnpo". ant to its performance in an acedent. YAMASHITA,T. Oak Ridge Nat onal Laboratory. March 1988.

The detector, manufactured by General Atomic, was simulta- 58pp. 8805200101. ORNL/TM 10272. 45560-051. -

neously subjected to a simulated accident environment includ, A simple model (ZlRCOX) has been developed to calculate ing 17' degree C (340 degree F) steen at 410 kPa gage (60 the extent of oxidation of Zacaloy cladding in the vertical fur.

psig) and 4 Mrad /hr gamma radiaton wtute its performance was nace tests conducted at ORNL The model is based on the fact ,

' that the oxidaten of ZrCaloy is governed by the parabol6c rate rnorutored Test results showed that the detector successtuffy ,

l operated at the begh dose rate and temperature, ethout evi- law. By introducing the equrvaient time t*, the model is able to ,

donce of synergisms. However, at reduced radiation levels in a handle nonisothermal oxidaten as well as isothermal. The

!' saturated steam envvonment, the detector signal at the readout degree of cladding omdaten and H(2) prduction were calculat-mndule detenorated in accuracy or ceased attogether. The ed using three sets of rate constants for the Zircaloy oxidaten, cause of these anomalies is attributed to leakage currents and/ and these resutts were compared mth those measured experi-l or possib6e gaNanc acton in the coaxial connectons and/or mentally. The calculated results showed excellent ag eement cables. with the expenments. The rate constant for Zacaloy oxidaton that gave the best agreement was one bated upon combined NUMEG/CR 4735 V03: EVALUATION AND COMPILATION OF Pawel et al. and Prater and Courtnght data. The temperature

DOE WASTE PACKAGE TEST DATA. Biannual difference between the cladding and the Erconta fumace tube

Report February-Ju!y 1987. INTERRANTE.C.; ESCALANTE,E.

liner was estimated by the HEATING 6 heat transfer program FRAKER,A.; et al. Commerr.c Dept of, Natonal Bureau of and was found to be about 50 K for the maximum ordaten Standards. May 1988.160pp. 84060700!9. 4572 '.023. rate. The heatsng atmosphere dunng test VI 1 was a!so evaluat-J 1hes report summanzes evaluations by the Natonri Bureau of ed in terms of the crygen potential.

s Standards (NBS) of Department of Energy activites on waste I

packages desgned for containment of Ngh-level n.Jear waste NUMEQ/CR 4770: PRELIMINARY STUDIES OF THE MORPHOL.  ;

l (HLW). The waste package is a propased engireered bamer OGY OF THERMAL GRADIENT TUBE DEPOSITS FROM FIS-4 that is part of a permanent repository for HLW. Vaal alloys are SION PRODUCT RELEASE EXPERIMENTS. WISBEY,S.J. Oak l 4

the pnncipal bamers within the engineered bamer system. The Rdge Natonal Laboratory. March 1988. 57pp. 8805090156. l i corroson of canddate container matenals, partcularty carbon ORNL/TM 10273. 45413 296. -

steels, stainless steels and cooper, is discussed, The level of Sectons of thermal gradient tubes and deposrts from filters i understanding of several proposed container matenats is ques- used as collectors in several fisson product release tests at  ;

toned for the canddste repository in toft. Three issues are ad- ORNL have been examined by scanning electron mcroscopy dressed (1) The possibility of stress. induced fadure of Zrcaloy, with elemental identificaton by energy dispersive X-ray anatysis.

1 (2) Wssible corroson of copper and copper alloys and (3) the Shape, size, and composaton of the deposits are reported, cor.

j lack of site.specife charactenraton data The Basatt Waste Iso- relatons with expenmental condtons such as gas compositen

laton P<olect (BWIP) et

ton dscusses localized corrosion and and temperature, as well as eth independent anatySes, have [

l

< t j r l

l t

L

M;in Citations and Abstracts 9 ,

i I

i been made where possible. A w4e vanety of shapes and struc. needed n arte charactenzaton at locatons similar to the Nitrate j l tures. spparently dependent on the deposaton temperature. Disposal Pit to provide the desired degree of predictNo Capab4-

, were pnoiographed and eiementai anatyses were recorded. Ai- 14s. 1 though some hsson products (Cs, Ba, Ag) were detected, f structursi and impunty elements (Sn, Si, S, W, Pt) were pre. NUREG/CR 4481: FICSION PRODUCT RELEASE CHARACTER. l dominant in most cases. Reccw.adatons for anaYbcal proce, ;3 TICS INTO CONTAINMENT UNDER DESIGN BASIS AND y 4

dures and ha%ng of samdar samples are made for the future. SEVERE ACCIDENT CONDITIONS. NOURBAKHSH.H P.;  ;

KHATIB.RAHBAR; DAVtS.R E. Brookhaven Natonal Laboratory. l NUREG/CR 4838: APPROACHES TO UNCERTAINTY ANALYSIS March 1988. 127pp. 6807070446. BNL NUREG.52059.

IN PROBA9ILtSTIC RISK ASSESSMENT, BOHN,M.P.; 46013-284.

, WHEELER.T.A.; PARRY,G.W. Sandia Natonal Laboratones. A detai,ed recew of the radclogical release estmates for  !

j January 19C8.108pp. 8805090083. SAND 87 0871. 45449 001. hght water reactor accident sequeraces is presented as a basis An etegral part of any probab hstc nsk assessment (PRA) is for development of a simpkf.ed approach for prodcton c8 char-the performance of an uncertanty anarysis to quantdy the un- actenstes of radiological releases mto containments under certainty in the point ethmates of the nsk measures cons 4ered. design basis and severe accident condtons for both Pressur.

WNie a vanety of classical methods of uncertainty analysis ized Water Reactors (PWRs) and Boiling Water Reactors ,

exist, apptcaton of these methods and developing new tech * (BWRs). Resultng source term estimates are also compared i naques consistent wtth existng PRA data bases and the need ,,tn parallel results using the Source Term Code Package l for expert (subjectve) input has been an area of considerable (STCP) methodology.

i interest since the peneenng Reactor Safety Study (WASH-1400) in 1975. TNs report presents the results of a entcal NUREG/CR 4832: CLOSEOUT OF IE BULLET:N 80-03 LOSS OF review of existing methods for periormmg uncertainty analyses CHARCOAL FROM STANDARD TYPE ft,TWO-INCH, TRAY AD-4 for PRAS, with spectal emphasis on ident#ying data base hrruta- SORBER CELLS. DEAN,R.S.; FOLEY,W.J ; HENNICK.A. Param-tons on the vanous methods. Both classical and Baysian ap- eter, Inc. April 1H8. 28pp. 6805200093. PARAMETER lE167, proaches have been examined. TNs work was funded by the 45560.318.

U S. Nuclear Regulatory Commisson in support of its ongoing Because of concern about defactrve charcoal tray adsorber fuS scope PRA of the LaSatie nuclear power staten. Thus, in cells found in certain ventilaton systems at the Sequoyah ih-additon to the review, thas report contains recommendabons for clear Plant, the NRC/tE issued IE Bunetin 80-03 on February 8, a suitable uncertainty ana'ysis methodology for the LaSalle 1980. Some charcoal cells are used in ventilaton systems asso-PRA. ciated with engineered safety features, wNeh are provided for NUREG/CR 4884 V01: THERMODYNAMIC TABLES FOR NU- protecten from abnormal events. Others are installed to control  :

CLEAR WASTE ISOLATION. Aqueous Solutens Database. radioactrve matenals dunng expected operatons. Licensees of L PHILLIPS.S L; HALE,F.V4 SILVESTER,LFJ et al. Lawrence operafng power reactors and holders of permats for those under  ;

Berkeley Laboratory. June 1988.195pp. 8807110498. LBL- constructen were required to take specific actons. Evaluabon ,

22860. 46082:118. of utlity responses and NRC/ Region inspecten reports shows v J that the bullebn can be closed out by means of specihe criteria  ;

Tem of consistent thermodynamic property values for nu.

] cles waste isolaton are given. The tables include critically as. W 43 (9W of me 124 fac+ ties with operating hcenses or  :

I sessed values for Gibbs energy of formaton, enthalpy of forma- construction permits. A folt,;wup item is proposed for the only 1 fac$ty with open bulletn status, for use by the NRC in ensonng

~

tion, entropy and heat capacity for genene minerals; sohds; ,

aqueous ions; ion pairs and complex ens of selected achnide sabsfactory completon of correctrve aeten. The cells wrth rivet-  ;

and hssen decay products at 25 degree C and zero ionic ed screens wh,ch were identifed at Sequoyah were not found  ;

strength. These intnnsic data are used to calculate equihbnum at any other facihty. Atthough cells with miscellaneous defects 4 constants and standard potentals whch are compared with typ- were found at nine facilit es other than Sequoyah, there were no

]; ical expenmental measurements and other work. Recommenda, charcoal problems.

bons for additonal research are given.

NUREG/CR 4833: CLOSEOUT OF IE BULLETIN 80-19. FAIL-NUMEG/CR 4479 V01: DEMONSTRATION OF PERFORMANCE URES OF MERCURY WETTED MATRIX RELAYS IN REAC- r MODELING OF A LOW LEVEL WASTE SHALLOW LAND TOR PROTECTIVE SYSTEMS OF OPERATING NUCLEAR l BURIAL SITE.A Companson Of Predctive Raeonuchde Trans. POWER PLANTS DESIGNED BY COMBUSTION ENGINEER- j port Modeling Versus Field Observations At The Nrtrate Dispos- ING. FOLEY,W.Ja DEAN.R.Sa HENNICK.A. Parameter, Inc. t i al Pit S4te, Chalk River Nuclear Labs. ROBERTSGN,0.Ea Aprd 1988. 26pp. 8805090125. PARAMETER lE168. 45412:301.

i BERCERON M P4 MYERS,0.A.; et al. Battelle Memorial Insti. The NRC AE issued IE Butlebn 80-19 irutialty on July 31,1980,

, tute, Pacife Northwest Laboratory. November 1987. 137pp. and issued Revision 1 of the bullebn on August 13,1980 The i 8805090112. PNL 6175 45412:164. Mieln was issued to att keensees and holders of constructon Before a heense can oe obtained to construct a facaty for the perrrwts of power reactors, because of numerous reports about shallow-land bunal of low. level waste, the U.S. Nur. tear Reguta- single and muttple failures of C.P. Clare Model HG2X 1011 tory Cornmisson must be assured that the facekbes will meet mercury wetted matnx relays in reactor protectrve systems. The i both performarce obpecbves and presenptrve requiremea.ts set concern based on those reports was the build-up of Co80Cident

] forth in 10CFR61, "Ocensing Requirements for Land Disposal "failed-closed" failures of certain sets of relays could result in i of Radcactive Waste." Subpart D, Secten 61.50(a)(2) of tnp failures for off-normal events. Evaluabon of utAtf responses 10CFR61 states that a "6sposal site shan be capable of beog and NRC/Regon inspecton reports shows that the butichn can

charactented, modeled, anatyred and morwtored." In order to be closed out per specific entena for 100% of the 123 power ,

l test the concept of site modelabdrty," a 30-year old low level facihbes with operating beenses or constructon perrrwts. In  !

raeoactive waste esposal site at Chalk River Nuclear Laborato- effect, all of the responses and especton eeports apply to Revi- .

nes (CANL), Canada, was used as a held locabon for evaluabng saon 1 of the bullebn. An except the three following facAttes the process of site charactenzaton and the subsequent model- l either do not have the sub}ect relays in the reactor protective og predictons of radonuchde transport from the site by ground- system, or have changed the relays to an acceptable type as a water. This evaluabon was performed by companng the actual resutt of the buliebn. An inspecton report closed the bullebn for measured raeonuchde rrugraton with predicted m,graton esb- Catvert Chtts 1 & 2 based on hcensee comnytmentr, to replace mated from hydrologo/radionuchde trensport frudets. This com- '

the mercury wetted relays with the dry-contact type. For St.

, panson Ms provided vstuable insights into the apphcabahty of Lucie 1, the hcensee elected to conbnue to use the subject ,

I transport rnodelog. and in determirwng what level of effort is relays and presented acceptable justhcaton. (

I 1

t 1

1 I

10 Main Citati:ns cnd Abstracts &

l NUREG/CH 4071: RESULTS OF SCMISCALE MOD 2C FEED. NUREG/CM 5015: IMPROVED- RELtABILITY OF RESIDUAL WATER AND STEAM LINE BREAK ($ FS) EXPERIMENT HEAT REMOVAL CAPABILITY IN PWRS AS RELATED TO i SERIES Mac Steam Une Break Accdont Expenments. RESOLUTION OF GENERIC ISSUE 99 CHU,T.L; BOUCHER T.J. EG&G Idaho. Inc. (subs. of EG&G, Inc ). March FITZPATRICK,R.; YOON,W.H.; et al. Brookhaven Nabonal Lab-1988.11209. 8804280505 EGG 2516. 45274:302. oratory. May 1988,159pp. 8006070054. BNL NUREG 52121.

) Ths report presents the resutts of two empenments conduct. 45727:184.

ed in the Sernscale Mod.2C facAty wNch s4 mutated main steam This report sumer.anzes a study performed by Brookhaven ,'

hne break accdents at hw;h pressure and temperature. Tests S. Natonal Laboratory for the Reactor and Plant Safety issues FS 1 and 3.FS4 simulaied double-ended offset shears of the Branch, RES of the U S. Nuclear Regulatory Commisson in pur-i man steam kne downstream and upstream, respectrvely, of the suit of the resolution of NRC Genenc issue 99. Genenc lasue flow restnctor Intel and boundary conctons were scaled from, 99 focuses on the nsk associated with loss of resdual heat re-and compounding failures and assumptons simulated, tho.J movat events at PWRs while whut down. Numerous loss of re.

sdual heat removal events have occurred at pressunzed water conotons ubhzed for Fmal Safety Analysis Report (FSAR) cal, reactors (PWRs) m the USA, which were terminated pnor to cutabons. Pnmary and secondary thermal hydraulic responses are charactenred, and the mfluence of the break size or loca- deman N MW m N % eWH N W W loss of residual heat removal events and ovestigates ways of ton on the responses is dscussed. The hmebng of pnmarwto-lowering (Ns nsk.

secondary heat transfer by conducton heat transfer is shown to l produce a trend of mereased pnmary cooling w:th decreased NUREG/CR 5016: COMPENDIUM AND COMPAR! SON OF [

l break size, pointing out the need for further analysis for smarier INTERNATIONAL PRACTICE FOR PLUGGING. REPAIR AND

break sizes. The degree of conservatism inherent in FSAR sep* INSPECTION OF STEAM GENERATOR TUBING. CLARK,RA;

' arator performance and break site and locaton assumptons is KURTZ,RJ Battelle Memonal Institute, Pacif c North *-est Labo-shown to be questionable, and the FSAR assumption of a loss ratory. Apnl 1988. 71pp. 8805090114. PNL 6341. 45432:233.

of offsite power rs shown to be renconservative. The effective- The Comrnttee on the Safety of Nuc' ear Installabons (CSNI) ;

ness of the recovery operatons in reganng and maintanng of the Orgamzaton for Econorme Cooperation and Development control of the system is addressed, and main steam kne break Nuclear Energy Agency (OECD-NEA) is an miematonal body issues are discussed. Finalty, conclusons are drawn and recom- of scientists and engineers with responsMties for nuclear mendatons are made for further utilizabon of the data safety research and nuclear icensng. The CSNt fosters interna. l 1

tonal cooperaten in nuclear safety amongst OECO member l

'j NUREG/CR 5000: METHODOLOGY FOR UNCERTAINTY ESTI- countries. In Jury 1986, the Comrnttee's Pnncipal Workeg MATION IN NUREG 1150 (DRAFT). Conclusions Of A Review Group p Pnma y Circuit integnty agtved rt would be useful to Panel. KOUTS.H.; CORNELLA.; FARMER.R.; et al. Brookhaven those setting entena and making decisions about pluggeg of r Natonal Laboratory. December 1987. 23pp. 8806230139. BNL- aegraded steam generator tubes to have a better appreciaton NUREG 52119. 45896.102. of tre entena presenty employed m other members countnes j A revew has been undertaken by a pane! of experts, of the and their technical bases. The Urvted States Nuclear Regulatory

] methodology for estimaton of uncertainty in severe accident Commisson (U.S. NRC) offered to arrange the preparaton of a ,

nsk resuttng from accidents to nuclear power plants as present- comparative summary for CSNI based on responses to a Ques-ed ir' the Draft NUREG 1150 report This report provdes de- bonnaire circulated by the OECD NEA among member coun. t j tailed discussons and conclusons resutting from this rece* tnes. The following report is based upcn the inforraaten ob-I P'OC'88 tained from nine countnes currently operating pressunzed water [

NUREG/CR 5013. FATIGUE LIFE CHARACTERIZATION OF NUREG/CR 5019: NEUTRON EXPOSURE PARAMETERS FO3  !

j SMOOTH AND NOTCHED PIPING STEEL SPEClVENS IN 288 1 DEGREE C AIR ENVIRONMENTS. TERRELLJ B. Matenals En- THE METALLURGICAL TEST SPECIMENS IN THE FIFTH i goeenng Associates. Inc. May 1988. 77pp. 8805200115. MEA. HEAVY SECTION STEEL TECHNOLOGY 1RRADIATION i MILLER.LF.; BALDWIN,C A ;  ;

2232.45561.256. SERIES CAPSULES.

) STALLMA7N,F.W.; et al. Oak Rdge Natonal Laboratory. March j Fatigue strain-Irfe tests were conducted on ASME SA 106 8 I piping steel at 24 degree C (76 degree F) and at PWR operat. 1988.127pp. 6dO4280633. ORNL/TM 10582. 4527t024.

ing temperature,289 degree C (550 degree F). under complete. The Heavy Secton Steel Techr' ology (HSST) Program, sup-ly reversed loa $ng Smooth specimens were tested at both ported by the U.S. Nuclear Regulatory Commesson has com-l, temperatures whereas specimens containing notches of vanous pleted the S3res 5 (HSSTS) erra$abon expenments. Twelve capsules which contain metallurgical test specimens have been acuities were tested at 288 degree C. Fatque limits at 10(7) cycles were esbmated in be 185 MPa (26 8 ksi) at 24 degree C irra$ated at the Oak RM Research Reactor located at the l Oak Rdge Nconal Laboratory. These capsules have been d;s.

and 232 MPa (33.7 ksi) at 288 degree C. The etterence in fa- assembled, intemal dosimeters have been ana'yted, and expo-j tague strength observed at the PWR temperature is postulated sure parameters are presented for each irra$aton test speci.

! to be due to dynamic stran aging processes However, there is men. This report desenbes the computatonal methodology for I a reducton in low cycle *atque strength at this temperature the least squares adjustment of the dosimetry data with neu-j which reselts e a decrease in the intended safety factcf of the trofvcs calculations, and it presents esposure parameters at n ASME Secton lit desan curve for carbon steels. Notch strain each test spectmen locaton for the fluence rate greater than f histones were estimated for the notched specimen tests using 1.0 MeV, fluence rate greater than 0.1 MeV. and dsplacements vanous interpretabons of Neuber s rule. It was concluded that per atom. The speerfic actrvity of each dosimeter at the end of the use of the fabgue notch concentraton factor (Kf) in the #U * " D*

Neuber relaton m conguncton with the uniarial cyche stress. ,

q stran curve provded the best correlaten of notched specimen NUREG/CR 5021 V01: USER'S GUIDE FOR PRISIM ARKANSAS fatigue data with resutts obtared from smooth specimen tests NUCLEAR ONE . UNIT 1 Volume 1. Program For inspectors.

The notched specimen strain hfe results derrved from the apptb CAMPBELLO.J ; GUTHRIEN.H.; KIRCHNER J R.; et al. Oak j caton of Neuber3 n.le alone roved to be conservatrve wher' Rdge Natonal Laboratory. March 1998.192pp. 8805090144.

g Compared to smt.0th spectinen test results to such an entent ORNL/TM 10604. 45434154.

that Neuber generated notch stress and strain amplitudes This user's gude is a two-volume document designed to I cannot be compared to the ASME Secton Ill fatque curves for teach NRC inspectors and NRC regulators how to access prob-

[ Carbon steels abihsbC risk assessment informaton from the two Plant Risk 1

1 i

i  !

l  !

i Malfa Citatioris and Abstracts 11  !

I i Siatus Informaton Management System (PRISIM) programs de- nsk from seismec inmated accidents is an important contnbutor j veloped for Adansas Nuclear One Unit One (ANO 1). Volume to overall nsk for the U S nuclear power plants studes. .

1 desenbes how ths PRA informaton available in Version 1.0 of

• j PRISIM is useful fr.J planning inspectons. Using PRISIM, in- NUMEGICR 5044: ESTIMATION TECHNIQUES FOH COMMON CAUSE FAfLURE EVENTS. KELLY,EJ: HEMPHILLG M. Los

! spectors can quickly access PRA informaton and use that info,,

Alamos Natonal Laboratory. March 1988. 53pp. 8806100174.

maton to update risk anatysis results.reflectmg a plan;'s status at any particular t.me. Volume 2 desenbos fm the PRA infor. LA 11179 MS. 45788 205.  ;

Common cause faduto probabihty estsnaton techruques, in- >

maton available in Verson 2.0 of PRIS!M is useful as an eval.

uaton tool for regulatcry setmbes. Usng PRISIM. regulators cleng B ' actor, basic paramete6 bmomal failure rate, multiple [

Greek, and C factor estimators, are evaluated and compared j can both access PRA informabon and moofy the mtormation to

] assess the impact these Changes may have on plant safety, using simulaton data that Captures the real word problem of Both volumes e.ro stand alone documents; each volume pro, sparse data from different piams, The effects on the esbmators' j sents several sample computer sessons des *gned to lead the performances from undertying factors such as ccmmcm cause shock rates, lethal shock rates probabehty of faihng given a user through a venety of PRISIM apphcations ustd to obtain

• shock, independent failure ratet, and system operatonal time PRA-related informaton for monitonng and controtir g plant nsk. are $scussed. Worst case results are reported, and it is seen NUREG/CR 5021 V0*: USER'S GUIDE FOR PRISIM ARKANSAS that for erttemely small common cause failure probabihties the NUCLEAR ONE . UNIT 1. Volume 2, Program Fw Rogvtators, binomial failure rate esbmators are best. Howev9r, these esth CAMPBELL,0.J.; GUTHRIE V.H; KIRCHNER.JA. et al. Oak mators can undereshmate the true probabihties when the fail-3 Ridge Natonal Laboratory. March 1988. 224pp. 8805090170. ures deviate from the bmomat failure rate model. The BJactor p 4 ORNL/TM 10604. 45433 290. technique is shown to be conservatrve, and m some cases to l TNs user's guide is a two volume document desgned to overeshmate the true probabsty by several orcers of magni-  !

teach NRC mspectors and NRC regulators how to access prob. tude. When there are observed failures for each failuro event,  !

abikstic nsk assessment informaton from the two Plant Risk the basic parameter techruque is best and is easily calculated. i Status Information Management System (PRISIM) programs de. TNs eshmator is investgsted in detait and is used to develop an j veloped for Arkansas Nuclear One . Unit One (ANO 1). Volume eshmator for the probatwhty of K or more units faihng due to a 1 descnbes how the PRA informabon available in Verson 1.0 of common cause. Uncertainty hmrts for this probability are also l PRISIM is useful for planning inspectons. Using PRIStM, in. developed.  ;

spectors can quickly access PRA informaton and use that infor.

NUREG/CR 5045: KANSAS-NEBRASKA SEISMICITY STUDIES i

{ maton to update nsk analysis resutts, reflecting a plant's status USING THE KANSAS-NEBRASKA MICROEARTHOUAKE at any particular bme. Volume 2 desenbes how the PRA infor. NETWORK. Final Repc't. STEEPLES.O.W.: HILDEBRAND.O M.;

maton available 6n Verson 2 0 of PRISIM is useful as an eval' BENNETT,B.C.; et al. Kansas, Univ. of, Lawrence, KS. March uaton tool for ragulatory actmtes. Using PRISIM, regulators 1988. 78pp. 8806020039 45706 22'  :

can both access PRA informaton and mod'ty the informabon to The Kansas Geological Survey HGS) operates a 15 station I sesmograph network w'th statens located n northeast Kansas l a h olume a ta alone docume t and southeast Nebraska. The network ta supported in part by NUREG/CR 5034: OPTIMlZATION OF THE CONTROL OF CON. fun 6ng from me UW Staks Wclear Ngdam Mmsson l TAMINATION AT NUCLEAR POWER PLANTS. KHAN,T.A.; (NRC) TNs repoi1 discusses operabon of the network and sum-  ;

BAUM.J W. Brookhaven Nabonal Laboratory. May 1988.146pp. mantes the results of research that atlows a better understand- t i 8806230171. BNL NUREG 52073. 45898.084. mg of the seismcity of the regon and the knk between the beis-A methodology is desenbed for the optim2aton of the actions medy and me McW seg of the mgoA NsWs W a taken to control contaminston. ft deals with many aspects of crustal sesmc @acton my aW a W W W W am contammaton, such as the monetary vuve assigned to a urut of escussed in Appe@ B 2 me MM g radabon d,se, the treatment of skm and entremity dose, ind NUREG/CR 5055: ATMOSPHERIC DIFFUSION FOR CONTROL i the inettiC6encies introduced from workmg in a Contammated en. ROOM HABITABILITY ASSESSMENTS. RAMSDELLJV. Bat.

j vronment The opbmitaton method is 6ttustrated with t*o case telle Memorial insttute, Pacific Northwest Laboratory, May

, studes based on cleanup protects at nuclear power plants 1388.120pp. 8805260384. PNL-6391. 45632.292 1 Guidelines for the use of protectrve apparel, and for monitormg Th s report presents the resuits of an evaluaton of the proce.

ra$aton and contaminabon at various levels of contammaton dure used by the NRC statt to assess nuclear reactor control

) are presented The report concludes that additonal research is room habitatxtity. The evaluaton is based on expenmental data i required to Quant;ty the effect of a contaminated envronrnent collected in seven sets of feeld expenments at nuclear power l on work efficiencies- plant sites The procedure is generalty unservatrve, but the models in the procedure show little skill in pred cting the effects l NUREG/CR 5042 S01: EVALUATION OF EXTERNAL HAZARDS of d;tferent atmosphenc con 6 bons on maomum effluent con-TO NUCLEAR POWER PLANTd IN THE UNITED centratons in buiteng wakes. Two attomatrve busleng-wake STATES Seismic Hazard. PRASSINOS,P.G. Lawrence Liver-

! models have been developed using the expenmental data The j more NatonaI Laboratory. Apnl 1988. 64po. 8805030107. UCID- first recdel dtfers sg%cantry from current models in the 21223.45343 194.

manner in wNeh wind speed enters the model. The second

As part of the research program Supporting the implementa- model is an extenson of the first model that has more desirable j ton of the NRC Pohey Statement on Severe Accidents, the asymptote behavor and includes consideraton of the mt> gating Lawrence Lrvermore Natonal Laboratory (LLNL) has performed effect of plume nse on concentratons m budding wakes. A set a study of the nsk of core damage to nuclear power plants m of non mathematical guidehnes is offered for use m evaluating the United States due to senmec htiated events The broad ob- potential control room air intake locatons.

i tectrve has been to gam an understan6ng of whether or not seismic events are among the major potenbal accident intators NUMEG/CR 50th EARLY AND CONTINUING EFFECTS OF that may pose a threat of severe reactor core damage or of COMBINED ALPHA AND BETA IRRADIATION OF THE large radcactive release to the envvonment from the reactor. LUNG Phase 11 Report SCOTT,B Ra HAHNf F.; SNIPES.M B ;

The analysis was based on two fgures-ot. ment, one based on et al. Lovelace Bemed & Enywonmental Research Insttute core Gamage treQuency and the other based on the frequency March 1988. 41pp 8804280444. (MF 119 45269 001.

of large ra$oactrve releases Using these two fqures.of. ment TNs report summan2es an mhalaton exposure expenment as evaluaton entena, it has been possible to ascertain that the that concems earty and contifung effects of combined a'pha I

i J

. -,-----.-r-, , - - - , , , . , ,-,w-. -- --_.~v -,. ,,w ,e = * - - ' - - - - -c - - - -,r- ,--

l 12 Main Citations and Abstracts i

snd beta rie6aton of the lung of rats. Both morbety at 18 programs. Such reviews will hkely result fdiowing the resoluton months and mortakty etNo it months after esposure were ex- of USI A 44 and GSl B 56. The desef generator rehatulity pro-ammed for rats orposed to the beta-wmtter (147)Pm, the alpha- gram is a managcmern system for acNevng and maintaming a i errwttF (2M)Pu, or both combined. The results were used to sWected (or target) level of rWiebihty. TNs can be acNeved by:

validate hatard furction models that were developed (1) for pul- (1) understeneng the f actors that control the EDG rehabikty and j monary fur'ctonal mort >6ty at 18 months and (2) for lethataty (2) then apptying rehabshty and maintenance techruques in 2

from reesten pneumennis and pulmonary fibrosis etNn is proper proporton to achieve selected performance goals. The months. Both models were found to adeovatWy predet the e - concepts and guidehnes escuswd in LNs report are concepts

penmental obswvatons after comtaned chronic alpha and tma and approachn that have been successful in appl 6 cations  !

rradators of ihe lung. A relatrve teologCal effectiveness of ap- where Ngh levels of rehabikty must be mantamed. Both the I promirriately 7 was obtained for (238)Pu alpha radaton Com- EDG to6 ability program process and a set of review items for i pared to (147)Pm beta ra6aton for both pulmonary functonal NRC use are provided. The review items represent a checkhst j i y nd lethahty from raeston pneumorwtis and pulmo-for reveweg EDG rehabihty programs. They do not, in them- i a sWves, constitute a rehabihty program. Rather, the review items  ;

NUREG/CR 5072

DECAY HEAT REMOVAL USING FEED-AND. are those estectrve features of a rehabikty program that must BLEED FOR U.S. PRESSURIZED WATER REACTORS. be present for the program to be acceptable. r LOOMIS.G.: COZZUOL.J.M. EG&G ldaho. Inc. (subs of EGAG, t

] inc ).

• Idaho Nator.at Engmeenno Laboratory. June 1988. NUREG/CR 6062: SIMULATION EXPERIMENTS ON TWO. -

48pp. 8607110521. EGG 2526. 46085.024. PHASE NATURAL CIRCULATION IN A FREON 113 FLOW VIS.

As p.vt of a Urvted States Nuclear Regulatory Comrnission UALIZATION LOOP. LEE,S.Y.; ISHit M. Argonne National Labo-(USNRC) evaluaton of current decay heat removal methods, ratory. January 1988. 58pp. 8805200070. ANL 881. 45549:096 l j the adequacy of feed and-bleed decay heat removal has been in order to study the two-phase natural crculaton afd flow  !

assessed for Uruted States pressorited water reactors terminat>on dunng a small break loss of coolant accident in (USPWRs). Use of feed and-bleed for decay heat remova' be- LWR, simulaton expenments have boon performed using a comes necessary irt a pressunted water reactor (PWR) system Freon 113 flow visualizaton loop. The mam focus of the present L if there is a loss of steam generator heat sink capabdaty. The opemet wu plaW on N No phase flow behavor in N '

feed and-bleed technique involves passing hot fluid out of the 4

hot-leg U-bend typical of B&W LWR systems The loop was va e P , wh e ta sly e the pr sys m b@ based on N Wphase now scalog enWa dweioped

, eth subcooled Ngh pressure injecton system (HPIS) flow, under tNs progra,w to fed M N Wect of M prope, j charging flow, or both. TNs doeurnent summarizes the results of phase changes and coupleg betwun hydrodyname and heat j avadable expenmental and analytcal work that has been per- transfer phenomena Signifcantry 6fferent flow cohaviors have  !

formed to investigate the thermal hydraule phenomena associ. been observed due to the non-equiltmum phase change phe-ated mth the feed-and-bleed technique. These resutts are then nomena such as the 11asNng and condensaton in the Freon ,

synthesired into a statement of adequacy of the feed and-bleed loop in comparison eth the prevous a$ababc expenment. The [

technique as a means of decay heat removal. It is concluded phenomena Created much more unstable hydrodynarrWC Conde-  !

that feed and-bleed can be a viable afternatrve form of decay tons wNch lead to cyche or oscillatory flow behavers. Also, the l heat removal for USPWRs. but that successful use of feed and- void estnbuton and pnmary loop flow rste were measured in  !

bleed is contingent upon the existence and use of procedures detail in additon to the important key parsmeters, such as the

for its implementaton, as well as upon the specifes of plant oower input. loop fneton and the liquid level inside the simulat- ,

design. ed steam generator.  !

]

i NUREG/CR 5076: AN APPROACH TO THE QUANTIFICATION  !

NUREG/CR 6085 V01: THERMOOYNAMIC NONEQUILIBRIUM IN

) OF SEISMIC MARGINS IN NUCLEAR POWER PLANTS The Importance Of BWR Plant Systems And Functions To Sersmic POST-CRITICAL HEAT FLUX BOILtNG IN A ROD I

Margins. AMICO.P.J. Lawrence Levermore Natonal Laboratory. .

BUNDLE Desenpton Of Experrnents And Sample Results. ,

l Apphed Rak Technology Corp May 1988 40pp.6806230148_ TUZLA,Ka UNAL,C.; BADR,04 et al. LeNgh Univ., BetNehem, ,

UCAL 15985. 45896 060 PA. June 1988,150pp. 6807110494. 46085:169, i

]

in NUREG/CR-4334 ("An Approach to the Ovantifcaton og TNs report desenbes the post CHF heat transfer expenments i

! Seisme Margins m Nuclear .%er Plants"), the Empert Panet on 6n a 3 x 3 rod bun $e The objectrve oss to obtain measure- f Quantifcation of Sessmic Margms presented a teclruque for monts of thermodynarrne nonequihbrium in the post-CHF regime studyng the issue of quant #png seismic margins As pa6 of and to charactenze :ts effects on two-phase beat transfer for that techn.que, the panel included methods for simphtyng the venfcaton of models used in thermal-hydraube codes. A two-margms assessment by screerung out components and systems phase loop was constructed. The rune rod test bunse incorpo-using both systems and fragilities screening out components rated a heated throud to s4mulate the operating charactenstes i

and systems using both systems and fragiktes screerwng guide- of a large rod bundte. An enginal

• hot patch" technique was de-  !

1 la es. At the tme of that report, the panel was able to develop veloped to achieve steady state post.CHF conditons 6 a rod  !

frag +bties screening guidehnes for all ptants, however the sys- bun @e. Steam temperature probes, developed earlier at LeNgh tems screening guidehnes aDphed only to PWRs (due to a for tests in single tubes, wert medfed for use in the rod I shortage of BWR seismac PRAs upon wtuch to base BWR sys- bunde Each test provided measurements of system pressure, tems screerung guidehnes) TNs report develops the BWR sys- coolant flow rate, wall beat flux, wall temperatures, two phase -

tems screerung guidehnes by utsking the results of a number of equihbnum qualities, and vapor superheat temperatures These ';

i BWR PRAs which have become available sece the pubhcaton pnmary data permitted deterrrunaton of well heat transfer coeff*

i of NUREG/CR 4334 cients, nonequikbnum vapor quahties, and Quench front p.opa-

! NUREG/CR-5078 V01: A REUABluTY PROGRAM FOR EMER. 9aton velocit>es. Emperenents were conducted m three 6tterent ,

i GENCY DIESEL GENERATORS AT NUCLEAR POWER modes- a) steady. state mth fined CHF tocaton, b) reflood eth j J PLANTS Program Structure. LOFGREN.E.V.; DEMOSS,0 M ; advancog CHF locatsons (propagatmg quench front), c) botl-ott [

FR AGOLA.J R4 et al Sand 1a Natonal Laboratones Apnl 1988. eth retreatmg CHF tocatoas Tests were expected over the fol.

• I' 155pp 8804?90386 SAND 87 7176 45271.304. lowing range of conctons Coolant nass flux, 0.1 to 26 kg/  !

The purpose of the report is to develop guidance for the NRC m(2)s, (Intet) quality, 40 degree C subcooled to 0 40, Pressure, f' j staff to evaluate emergency 6esel generator (EDG) rehab&ty 105 to 120 kPa. Heat flux,5 to 43 KW/m(25 i r i

i

! P

i Main Citations and Abstracts 13 NUMEG/CR 6095 V02: THERMODYNAMIC NONEQUILIBRIUM IN NURt0/CR 6113: FINDtNGS OF THE PEER REVIEW PANEL ON POST CRITICAL HEAT FLJX BOILING IN A ROD THE DRAFT REACTOR RtSK REFERENCE BUNDLE Data For Statahred Quench Front Tests. TUZLA.K.; DOCUMENT,NURFG 1150. KASTENBERG,W E.; ,

UNALC; BADR,0.; et al. LeNgh unw., BetNehem, PA. June APOSTOLAKis,G.: P"KEL.J H; et al. Lawrence Uvermore Na-d 1988. E05pp. 8807110524. 46080293. bonal Laboratorv '88. 238pp. 8806230152. UCtD 21346.

See NUREG/CR 5095.V01 abstr2ct. 459001 60.

TNs report s the fmd.ng of the *'NUREG 1150 Peer i NUREG/CR 6096 V03: THERMODYNAMIC NONEQUILIBRIUM IN Review Pant A the methodology and resutts presented in the ,

! POST CRITICAL HEAT FLUX BOILING IN A ROO Dratt Reactor Risk Reference Study (NUREG 1150) and sup- i BUNDLE. Data For Advancing Quench Front Tests. TUZLA K.; portmg documentaten. The report consists of two pnncipal [

tJNAL,C.; BADR,04 et al. LeNgh Urvv., Bethlehem, PA. June parts: the charman's report, wNch summantes the precepal 1988. 567pp. 8807110530. 46079 081.

issues of m rm*, and m di@al members mports, wNch See NUREG/CR 5095,V01 abstract. suppy m Nudval hndogs W techrwcal Mads of M W-O teen reviewers.

l NUREQ/CR4095 V04: THERMODYNAMIC NONEOUILIBRIUM IN NUMEG/CR 5123: STUDIES OF THE PATTERN AND AGES OF

, POST CRITICAL HEAT FLUX BotLlNG IN A ROD POST METAMORPHIC FAULTS IN THE PIEDMONT OF V!R-BUNDLE Data For Retreaung Quench Front Tests. TUZLA,rL; GINIA AND NOR1H CAROLINA GLOVER.L; COSTAIN,J K.;

j UNAL,C.; BADR.O.; et al. LeNgh Urw., BetNehem, PA June CORUH,C, Vrfnia Polytechtse institute & State Urw., Blacks- ,

J 1985. 201pp. 8807110476. 46085:322. burg, VA. Apnl 1988. 67pp. 6805060296. 45430.226.

o See NUREG/CR 5095,V01 abtract. A geolog,c comdor from the Blue Rdge to the eastem Pied- [

mont of Vrgmia is integrated into a tectorwe model and artrapo-4 NUREG/CR 5105: RESPONSE MARGINS INVESTIGATION OF tated downward 10 to 15 Itm by means of seistne reflecten and PlPING DYNAMIC ANALYSES USING THE INDEPENDENT gravity studies. The Blue Ridge appears to be a Nnge zone that SUPPORT MOTION METHOD AND PVRC DAMPING. faced a nft generated lapetus Ocean. An Eastern contment  ;

BEZLER P.; WANG,Y.K.; REICH.M. Brookhaven Nabonal Labo- wth an Eocambnan and Cambnan magmate are and se$ments ratory. March 1988. 393pp. 8805260282. BNL NUREG-57137. of the same age, coilded wth the North Amencan conbnental 45633 052. margin in the Mddle and Lato Ordovician. Subsequent Devono-An evaluaton of Independent Support Mobon (ISM) response Mississippaan and Mississippian Permian orogenests continued spectrum methods of anahsis coupled mth the Pressure Vessel to dove tNn thrust nappes onto North Amenca Earty Mesozoic '

Research Committee (PVRC) recommendaten for dampng, to nft basins record the beginning of the Atlante basin and, from

] compute the dynamic Component of the seismc response of Micidle Jurassic to Present the margin of North Amenca was t ppog systems, was completed. Response estimates for five covered by Coastal Plain sediments. Several constrained hypo-ppog/ structural systems were developed using fourteen var. centers of the central Vrgna se<smc tone, ediacent to a re-iants of the ISM response spectrum method, the Uniform Sup- flecton prone, show an apparent reisbon to structure. We ten-4 port Moton response spectrum method and the ISM time Nsto. tatrvely conclude that flat and ramp fautts formed dunng Paleo- [

4 ry anaysis method, all based on the PVRC recommendatens roic nappe emptacement are currently being reactrvated. The

, for dampng The ISM /PVRC calculatonal procedures were reactivaten may be targety aseistmc on the old thrust faults, but found to ethibit orderty charactenstes eth levels of conserv. seismoty appears to be related to Ngh angle transcurrent faults j atism comparable to those obtained wh the ISM / uniform where new rock breakage may be occumng.

damping procedures. Using the ISM /PVRC response spectrum

] , method wth absolute combinaton between group contnbutons NUREGICR 5129: EXPERIMENTAL ASSESS!JIENT OF THE IN-provded consistently conservatrve results whde using the ISM / FLUENCE OF DYNAMIC LOADING ON THE PERMEABILITY PVRC response spectrum method mth square *oot sum of OF WET AND OF DRIED CEMENT BOREHOLE SEALS.

J ADISCMA.G.; DAEMENJA Antona, Univ of Tucson, AZ. Apnl I j squares combinator bet *een group contnbutons provded esti-1988. 279pp. 6805090129. 45433 011.

mates of response whch were deemed to be acceptable.

An expenmental seahng performance assessment of cement NUREG/CR 5106: USER'S GUIDE FOR THE TACT 5 COMPUTER beehole pbgs mat have been subjected to dyname baeng is CODE. WEST.D B.; GILPIN.H E. Science Appicatons Intema- provided. This menudes a study of plugs that have oned, as well l

1 tmal Corp (formerty Science Appleatons, inc). June 1988. as of plugs that have remaced wet throughout the testeg i 205pp. 8807070447 SAIC 88/3023. 46013 011 pened An m%cWy how myew Watn mat deep um  !

l The TAC 15 computer code, e successor to TACT til and ear.

Nground sMWs e canpeted e am saw N sudace

structures, openings at shallow depth, and openings e fractured her versons of TACT (an actor *ym for Trar. sport of ACTivrtd, rocks, when subrected to earthquakes and subsurface blasts.

( simulates the movement of ra$oactivity hypoinetically released Cement plugs are instafled in 2 5 cm &ameter coarial holes in

trom a reactor core as it migrates through user defoed regens 15 cm dameter granite cyimders Water is m;ected under pres-

, (nodes) of the contamment, is anmobehred by fdters and sprays- sure on top of the plugs and ts collected below the plugs. Hy-l and is released to the outsde envronment. The code has been draube conductmtes are calcutated Once a long term steady-modfed to run on a personal computer (PC) A senes of inter- state flow trend has been estabhshed, the sample are subjected active BASIC pre-processor codes assists the user e comping to dynamic loa $ng on a shaking table. Shaking is performed st a nucide mput data fde and a plant model data fde The plant acceleratons up % 2 g and for up to 300 seconds Wet cement model data fde specifies a dynamic compartment model, which seals are less p,rmeable than intact Charcoal granite. Sealmg is repts>ented by systems of or$ nary 6tterential equatons wtn performance can degrade severery wtion cement seals are ab constant coefficients The einatons are soNed emplotty by lowed to dry. Dye injecton shows very hmited and urdorm pen-matnu transformaton methods A code run carres out the et*- etration into wet plugs, but strongiy preferential flow along the graton of these systems of equatons over a successon of time pluc/ rock mterface of cred plugs The permeabdity of wet and intervals tonowng reactor shutdo*ft, with the eterval bound

• of rewetted prevouth dred cement seats does not change seg-anes corresponong to transitons of system paramoter values nificantty after the opphcaton of dynamic loads. Sea'mg in an whch must be constant within each time eterval Ou+put gener, unsaturated envronment may a+fect the drymg (cunng. agog) ated ecludes the level of ra$oactyty e each node of the con- conetons of cementt.ous seats, as well as the structure of j l tanment and m the envvonment, and radaten doses to re'er- eartnen seats An unsaturated envronment will n+0d to be mte.

I ence m@vdua's at up to three etterent receptor poets grated reabsticath mte Seahng performance tests and ans'yses.

i 1

i 14 Main Citations and Abstracts

! I l

NUREGICR 5130: BENTONITE BOHEHOLE PLUG FLOW TEST. adiusted to account for labor productmty, rasaton fields, learn-j ING WITH FIVE WATER TYPES. G AUDETTE.M V.; og curve effects, and impacts on anestary systems or compo.

j DAEMEN.J J. Antona, UrW. of. Tucson, AZ. Amt 1966. 223pp, nents For compansons of ethmated vs actual labor costs, ap-i 6605090139.45432 010. proumatety four dozen actual cost data pomts (as reported by l The hydrauhc conductmty has been determoed of plugs con- t4 nuclear utAtes) were obtamed. Detaded background informa-a structed estN commercial precompressed bentervie pottets. Ben- ton was collected on each indmdual data poet to grve the best j torvte tas been hydrated and tested mth waters of frve efferent understandmg possible so that the labor productery factors, re- .

chemeal compostions, ecludeg one groundwater (Ogallala aq- moval factors, etc, could }ud cowsly be chosen, TNs study con- '

uifer, Tomas). The groundwater conta.ned a vgrvfcant amount ciudes that cost estwnates that are typcalty ethm 40% of the .

of sohds, nators prepared in the laboratory 6d not Prepared actual values can be generated by prudentfy useg the method- l

waters used for testeg included estitled water, a hgh (1000 olog.es and cost factors invest, gated herein. l ppm) and a low (45 ppm) calcium soluton, and a 39 ppm so$um water, Uncompacted pivgs were constructed by drop- NUREQ/CR 5142

DUCTILE TO BRITTLE TOUGHNESS TRANSL.  ;

ping bentrote tablets nto waterfded cyhnders, or by meAng TION CHARACTER!ZATION OF A5338 STEEL JOYCE.J.A.  ;

powdered bentorvte with preselected water volumes e order to David W. Taylor Naval Research & Development Center, June  !

obtain co6troned nbal water contents. The hydrauhc conductivi- 1988. 37pp, 6807110516. 46099 318. i i ty of all plugs tested mth all wsters would result in a classafca- Central to the understanding of nucleaf reactor contamment [

ton of pracbeepy impervous, by convenbonal sod mecharwes vessel fracture safe design is the development of techneques to '

standaTs. Vanatens of several orders of magn #ude of the hy- charactoiue and prodct the fracture of ductile metals in the "

draulc conductrvity are obsarved. Clay plugs constructed from upper regon of the ductile to bottle toughness transeten. TNs bentontte tablets hydrated eth unfdtered Ogaltata groundwater project has utazed the J integral parameter to develop tough-exNbited reduced swelimg and lower hydraule conductmty than ness transition mformaten for state and dynamic loseng rates smlar plugs constructed from tablets and d>sbned water. The througnout the toughness transtten for an A533 grade B clasa ,

diferences m observed conductrvebes may be govemed by fac- 1 containment vessel steel The J at cleavage (J(civ)) is evalu-  !

i tors such as seethng charactenstes and permeant colloidal ated when cleavage occurs, and the J(Ic) is evaluated when i i matter cloggeg plug pore spaces. Constant pressure intecton ductile crack extension is present. In many specimens, for botn  ;

and transent pulse tesbng methods have been tned to deter

• state and dynamc loadeg rates, both J(k) and J(Civ) are evalu-

,i trwne hydraube conductmty. Especially in constant pressure m- sted and plotted as a functon of test temperature and test rate.

j jector tests, outflow volumes may require adjustment to ac- A pnncipal concluson is that if dynamic loadng rates are used, j count for consolidaten drainage. Attempts made here at such very little size dependence seems to be present, though larger 5

correctons have not been successful Consohdatcn testeg re- specimens produce lower bound resofts Close agreement is i 1 Quires entremefy tong bme pereds to approach a constant lemtt. a!so shown between dynamic ntiaton Cleavage toughness [

lt appears probable that the flow tests have ret been pursued values and the arrest toughness K(la) values obtamed by NBS i for a suffcent tirne to assure complete determinston of wate' (Garthersburg) dynamic crack arrest tests conducted on large 6 cherrustry effects on hydrauhc conductmty. edge cracked plates of LNs same steel alloy.  ;

NUMEQ/CR 5137: BIODEGRADATION TESTING OF TMI2  !

EPICOR.it WASTE FORMS. ROGERS,R D; MCCONNELLJ W NUMEG/CR 51472 FUNDAMENTAL ATTRIBUTES OF A PRACTI-

] EG&G Idaho, Inc. (subs. of EG&G, loc ). June 1968. 40pp CAL CONFIGURATION MANAGEMENT PROGRAM FOR NU. j CLEAR PLANT DESIGN CONTROL KLEIN,S.M. IRC Intema-  ;

l 8807070421. EGG 2540. 46011:344.

i Waste form tesbng is bemo conducted by the Three Mile tonal, Inc. June 1968. 80pp. 6807060362. 46077J65. -

tstand Urvt 2 (TMI 2) EPICOR It Resm/ Leer investgaton; Low. TNs report summantes the resuNs of an evababem of fm6  ;

Level Waste Data Base Development Program or the U.S. Nu- ings identeed durmg a number of Safety-System Furabonal in-

• 1 clear Regulatory Comfrussen (NRC) m accordance with the spectons and Safety System Outage Mod.fcaton inspectons j NRC Branch Techrvest Posrton on Waste Form. Waste forms wNch are related to confquraten management A computen:M [

wtuch were tested contam 6cn exchange resins sob $f.ed with database of these findmgs was generated from a revew of tese a i ymyl ester styrene and Portland Type t il cement. TNs report desgn especton reports Based on the resurts of the evalue- j

- desertes the biodegradatcn testeg of those waste forms, pre- ton, attnbutes of a confguraton management program were ,

! sents the test results, and provdes recommendatons for arter- developed wtich are responsive to mntrkring these types of m-  ;

nate test enetrodoiogy. Specton findmgs. Incorporation of these key attnbutes es con- I sidered good practce m the development of a contguraton  !

4 NUREQ/CP 5130: VALIDATION OF GENERIC COST E STl- management program at operatog nuclear plants MATES FOR CONSTRUCTION RELATED ACTMTIES AT NU-  ;

CLEAR POWER PLANTS Feal Report SIMlON.G.; NUREG/CR 5150: STEAM GENERATOR OPERATING SCtACCA.F ; CLAtBORNE.E.; et at Scence & Engineereg As- EXPER:ENCE Update For 1964 1966. FRANK.L: STOKLEY,J. l sociates. Inc. May 1988. 53pp 8805200123. SEA 87 253 04A1. Science Apphcatons intematonal Corp. (formerty Scence Ap-45561.334. pheabons. Inc ). June 1988, 65pp. 8807110505 SAIC-87/3014.

• TNs report represents a validaten study of the cost method- 46099 233. ,

ologes and quantitatrve factors derrved n "Labor Productmty TNs report summanzes operatonal events and degradaton Adt ustment Factors" (NUREG/CR 4546) and "Genenc Method- mechanrsms affectng pressunted water reactor steam genera-

, ology for Eshmahng the Lats Cost Associated with the Remov- tot etegnty, provdes updated especton results reported m l

! al of Hardware. Matenats and Structures From Nuclear Power 1984,1985, and 1986, and hghhghts both prevatent problem i i Plants" (SEA Report 64 116-05-A 1) TNs cost methodo6ogy areas and advances e improved equipment test practices, pre-

was developed to support NRC analysts e determong genene venbve measures, repas techneques, and replacement proco- {

! estmates of removal, estatlaton, and total tabar costs for com dures it desenbes eQupment desqn features of the three major -

1 structon-related actvites at nuclear generatmg statows in ad- supphers and escusses 68 plants in detaet. Steam generator ,

I $ ton to the vakdaten dcsson, this report revews the gener- degradaten mecharusms melude entergranular stress corroson ,

j c cost anahsis methodology employed it s'so oscusses each crackmg. pnmary water stress corroson crackeg pittmg. mter-  :

of the 6nevdual cost factors used in estimahng the costs of granular attack, and versten wear that affects tube etegnty i j physical modficatons at nuclear power plants The genene ests and causes leakage Plug 7ng, skeeving. heat treatment, pee & l madng approach presented uses the "greenf.e6d* or new plant mg, chemical cleanmg, and steam generator replacements are i

!' constructen 6nstanaten costs compded m the Energy Economic deserted and regulatory instruments and inspecton guidehnes [

Osta Base (EEDB) as a basehne These basehne costs are then for non4)structrve evaluabons and girth weld crackmg are es- [

i i

J t

.c..__ _r_.._ , _ ,__ , , . . . _ . . _ . _ , _ . _ _ _ . _ , - _ ,

Main Citati:ns and Abstracts 15 cussed. The report concludes that s'though degradation mecha. reducers, and generabred turbulence sources are present up-rusms are generally understood, the elmnation of unschedded stream Cf the vaNo w, thin 10 pipe d.ameters Major fengs irk plant shutdowns and costry repairs resulting from leabng tubes clude the flow velocity requered to acNeve a full open, stable has not been achieved. HghbgNts of steam generator research disk positen, the magnitude of d sk mot on developed with and unresoNed saiety issues are d+ cussed these upstream disturbances with now velocities below full open cond.t.oas, as well as dtsk natural frecuency data wNch can be NUREO/CR 5151: PERFORMANCE BASED INSPECTIONS. used to predict wear and fatque damage. Reducers were found HAWKINSJ NRC No Deta ed a Atfihaton Grven. JOHNSON.J to cause litt'e or no performance degradaton. Elbow effects Weinch & Assoc,ates LINER R.TJ et al. Science Apphcations must be consdered when located witNn 5 d1ameters of the Internatonal Corp (formerly Sc+nce Applcatens, Inc ). June check va've, wNie severe turt>ulence sources have sgnrficant 1988 27pp 8806230162. SAIC 88/3014 45907 234 effect at d stances to 10 d1ameters C'aarnay swing check de- ,

TNs typort desenbes the concept of perfortMnce-based ark sgns were found to be partcularty sensitrve to manufactunng spectons that is being taught in NRC's traing course, "In. tolerances and instattaton vanables makog them hke?y candi-spect!ng for Performance " TNs co ept has bean endorsed dates for premature failure Reduceg the disk full opening angte and is being impfemented by the Nuclear Regulatory Commis* on these clearnay desgns results in sgnificant performance om.

Sion (NRC) NRC performance based inspectons concentrate provement.

on actmties that impact plant rehabety and safety. The inspec-tions beg n with performance based observatons, and then the NUREG/CR 5160: GUIDELINES FOR THE USE OF THE EEDB inspectors let d+ repancies or uncerta:nt es lead to inspecten g g g g ggg gg of otner areas, Swh as quatty ventcaton organgaton effec- Report. ROBINSON.T.; SIMlON.G ; SCIACCA.F.; et al. Science trveness, tra:ntng adequacy, and procedural controts. TNs in- e Engneenng Associates, Inc. May 1988. 72pp. 8806239166.

Specton approach depa'ts from past NRC pract>ces tnat em- SEA 87 25 A1 5898 32 phasized documentation and program review as a means t measure operatonal sa ety The first goal of performance-based constructon cost estimates for boM^9 water reactors (BWRs) inspectors is to improve the NRC inspector's abity to accu- and pressunzed water reactors (PWRs). The genenc cost esti-ratefy eraluate plant safety and rehabaty. This goal wdl be mat.ng methods developed for the NRC utare the EEDB cost acNeved by increas;ng the inspector s emphasis on actual ob- data as a basis for estimating the costs of physical modifica-servaten of ongoog facil ty work aumtres and reducing the em. tons to nuclear plants. Such mod ficatons may be mandated by phass on document aNd program reeews. The secondary goal new or revised NRC regutatory requirements. The costs pre-of periormance-based level inspectons is to encourage licens- sented in tne EEDB are of1en grven at a relativefy high level of ees to manage their f acAt--es in a performance-based manner, aggregatcri The defeton of matenal, labor, and equipment costs is seldom geven at the same level as that encountered in NUREQ/CR 5159: PREDICTION OF CHECK VALVE PERFORM- plant modificaton projects Additonal defoton is needed to ANCE AND DEGRADATION IN NUCLE AR POWER PLANT adequatety estimate the costs of many proposed changes TNs SYSTEMS KALSI.M S., HORST.C L; WANG.J K. Kaiss Engi. report presents matenal and equipment costs and labor man-neenng. Inc. May 1999 70pp 8806230210. KEl 1559 hours / costs at the component, subcomponent, and subsystem a5897 233 level that support and correspond to the more Nghty aggregat-Derradatcn and falure of swing check vanes and ressiting ed data presented in the EEDB 11 is intended to be a supple-damage to p; ant equipment has led to a need to develop a ment to the EEDB Specificatty, unat labor and mitenaf/ equip-method to predect performance and deg'adation of these v4Nes ment Costs are defined for the following types of n:Stenal and in nuclear power piant systems TNS Phase I investigaton de- eqwpment. Rotating machinery, pping related commodities veloped methods *Nch can be used to predict the stabil.ty of (piping, vanes, hangers, and insu'aton), instrumentaten and the check vane d sk when poing d sturbances such as elbows, control. ;+ghting and service pow >r, skid mounted equipment.

l l

l

- - = a -- - - . . - _-- -a--ne - - -a m--a--- -- - - ----.---_. mp m.L-sa.ms sau -..m, .- . -.- u - . -L- a.---a,- s I

i I

i l

l l

l 1

s I

i

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l

Secondary Report Number index ,

i 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-r:ferenced to the NUREG number for the report and to the 10 digit NRC Document Control System accession number. l I

(

MCONOARY REPORT NUwMR REPORTNUweem ONDARYAtPORTNUween m ogt7 NUwegm ANL48-1 NUREG/CR 5062 NU T M-10272 NURE -4777 BVI-2120 NUREG/CR4062 V06 NL/TM 10 NUR -4 77$

BNL-NUREG 52059 NURE G/CR-4681 gj U: 0604 hl# E 2 V01 BNL-NUREG42073 NUREG/CR 5034 NL/TM tm NUREGI 502) V02

/ T '4 V N2 BNL NUREG-52137 NUREG/CR 5105 PARAMETER i 162 NUREG/ 4665 CSNI97 NUREC./CP 0075 #ARAMETE R IE167 NUREG/ R-4932 EGG 2454 NUREG/CR-4639 V01 PARAMETCR 16168 NUR G/CR-4933 EGG 2516 NUREG/CA-4971 PNL4855 NUR G/CR-4605 R VQ1 EGG 2526 NUREG/CA 5072 PQ4 p g EGG-2540 NUREG/CR-5137 PNt'4391 NUR /CA 505$

, IE B-8043 NUREGICR4932 PNL4511 NUR 3 l IEB 4019 NURE G/CA-4933 7/3014 NUR 5150

, IE B-4344 NUREG/CR-4665 /3014 NUR 5151 KEl1559 NUREG/CR-5159 3023 NUREG/ 5106 LA-11176 MS NUREG/CR 5044 AN0661936 NUR G/ -4720 5:!8,'s"506 "' m 128:t!!!i $"E8'8= voi t'A.'#9 $AND87-0671 NUREG/CR4636 ME A 2232 NUREG/CR 5013 '

ORNL/NOAC-232 NUREG/CR-4674 VOS f 7 h'53hA1 N 8""t'NBF2#

n, W:18',a:'a0 v07 N4 21:1;4$< *

• r > ;**'

edGagg; 01 OR~uNsc2x NUREG CR 2 NUREG,CR 5113 ORNL/NSC200 NUREG/CR-2000 YO7 N5 UCAL.15985 NUREGICR 5076 l

l l

2

)

i l

5 1

l 17 I

t 1

I I

I r

l l

l

Personal Author Index

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

ASE LK.H. SANNE S.C.R.

NUREG/CR 4479 YO1: DEMONSTRATION OF PERFORMANCE MOO- NUREG/CR-4082 V06: DEGRADED PIPtNG PROGRAM . PHASE il $ath EUNG OF A LOW LEVEL WASTE SHALLOW LAND BURLAL SITE A Program Report October 1986. September 1947.

Corr $anson Of Predetwo Radonychde Transport Modeling Versus Fie6d Observadons At the Nitrate Deposal Pit $.te. Chalk Rwer Nuclear SAUMJ.W.

Latt NUREG/CR 5034 OPTIM2ATiON OF THE CONTROL OF CONTAMINA-TION AT NUCLEAR POWER PLANTS NUREG/CR.5129 EXPER. MENTAL A$$ES$ MENT OF THE INFLUENCE ptNNETT,8.C.

OF DYNAMC LOADWG ON THE PERMEABiUTY OF WET AND OF NUREG/CR-6045. KANSASNEBRA$AA SEtSuiOTY STUDIES US:NG DRIED CEMENT BOREHOLE $EALS THE KANSAS-NEBRA$AA MCROEARTHOUAAE NETWORK. Final ,

Report AHMAD).

j NUREG/CR 4062 V06 DEGRADED PIPING PROGRAM PHASE 11 Sisih DERGER M M.P j Program Report October 1966. September 1967. NUREG/CR4879 V01: DEMONSTRATION OF PERFORMANCE MOO-AMICO,PJ. EUNG OF A LOW. LEVEL W ASTE SHALLOW. LAND BURLAL $1TE A NUREGICR-6076 AN APPROACH TO THE QUANTIFCATION OF $Eis. Compenson Of Predictwo Roonuchde Transport Modehng Vms  ;

MC MARGINS IN NUCLEAR POWER PLANTS The importance Of Fied Observations At The N trate Dsposal P4 $de. Cham Rwer Nuclear p B AR Plant Systems And Functons To Seesmic Margins. Labs.

ANDERSON.N R. DE ZLE R.P.

NUREG-1213 DAFT FC REGULATORY ANALYSIS FOR USI A 40, NUREG/CR $105. RESPONSE MARGINS INVESTc4 TION Or PIPING

"$El$MC DE$6N CRITERtA " DrsM Report For comment DYNAMC ANALYSES U$WG THE tNDEPE NDENT $UPPORT O

APOSTOLAKIS.G.

i NUREG/CR 6113 FINDINGS OF THE PEER REYlEW PANEL ON THE B6CKELJ.H.

DRAFT REACTOR RISK REFERENCE DOCUMENT,NUREG 1150 NUREG/CR.$113 FINDWGS OF THE PEER REY:EW PANEL ON THE APPtGNANI.P.L DRArt REACTOR RISK REFERENCE DOCUVENT.NUREG.'150.

NUREG/CR 5078 V01. A REUAStuTY PROGRAM FOR EMERGENCY BILHORNSQ. >

D GENERATOR $ AT NUCLEAR POWER PLANT $ Program NUREG isis TECHNCAL POSITION ON ITEMS AND ACTfVITIES IN d

THE HIGH-LEVEL W ASTE GEOLOGC REPO$iTORY PROGRAM i AUSTIN P.N. SUBJECT TO OVAUTY A$$URANCE REOutREMENTill NUREG/CR 4674 V06 PRECURSORS TO POTENTLAL SEVERE CORE DAM AGE ACCiOENTS 1986.A $7 ATUS REPORT DLOND.R M.

NUREG/CR4674 V06 PRECURSOR $ TO POTENTIAL SEVERE CORE NUREGICR.5113. FIND 4NGS OF THE PEER REVIEW PANEL ON THE DAMAGE ACODENTS 1986.A STATUS REPORT. DRAFT REACTOR RrSK REFERENCE DOCUMENT,NUAEG 1150 AYERJ E. DOARD.tJ.

NUREG-1320 NUC EAR FUEL CYCLE FActuTY ACCfDENT ANALY$i$ NUREG/CR-$113 FINDINGS OF THE PEER REVIEW PANEL ON THE ,

i MANOBOOK DRAFT REACTOR R:SK REFERENCE DOCUMENT.NUREG 1150 t B ADR.O. DOCCIOA NUREG/CR 5095 V01: THERMOOYN AMIC NONEOuiUBRIUM IN POST. NUREG/CR-5078 V01 A REUABiUTY PRC4 RAM FOR EMERGENCY CRITCAL-HEAT-FLUX BOluNG IN A ROO BUNDLE Desenphon Of D'ESEL GENERATOR $ AT NUCLEAR POWER PLANT $ Program N IN5 5 Vo E $NAMIC NONEOutuBRIUM IN POST.

CRITCAL-HEAT-FLUK BOIUNG IN A ROD BUNDLE Data For Stats- DOECKER,58.

kred Ovench Front Tests NLREG/CR-5067 EARLY AN.) CONTINUtNG EFFECTS OF COMBINED NUREGiCR 5095 YO3 THERMODYNAMC NONEOutuBRIUM IN POST

• ALPMA AND BE7A iRRADI ATiON OF ThE LUNG Phase II Report j CRITCAL HEAT FLUE BOlVNG 6N A ROD PUNDLE Data For Advanc.

ing Quench Front Tests DOHN,M P NUREG/CR 5095 V04 THERMOO1NAMC NONEOutuBRIUM IN POST. NUREG/CR 4436 APPROACHE$ TO (NCUTArNTY ANALY$tS W

, CRITCAL HE AT.FLUR BO8UNG IN A ROO BUNDLE Data For Retreat. PROBABrVSTC RISK ASSESSMENT.

ing 0; erd Front Tests BALOWIN.C A. DWCHEW NUREG/CR 5019 NEUTRON EEPOSURE PARAMETERS FOR THE NUREGICR4971. RESULTS OF SEM.$CALE MOCL2C FEtDWATER A D WW W BW MO MWW pts Mac team METALLURGCAL TEST $PEC1 MENS IN THE Ft7TH HE AVY.$tC. Line Sreas AccM Eapenmeds TON 5 TEEL TECHNOLOGV LRRADiATON $ ERIE $ CAPSULE $

f l DROOE S,5.

l BALLHeGE R.M.V. l NUREG 1MO NUCLE AR FUEL CYCLE FACIUTY ACCOENT ANALT$t$ NUREG.0713 V07. OCCUPATONAL RADIATION EaPOSURE AT COM MANDBOLX ME ROAI. NUCLE AR POWER RE ACTORS AND OTHER F ACIUttt$

DARANOWSEY P W.

NUREG-1032 EVALUATION OF STATION BLACAOllT ACODENT$ AT 94UST,F.

NUCLE AR POWER PLANTS Technical Fe*Jhngs Related To Unre. NUREG/CRadet V06 Ef/ GRADED P: PING PROGRAM . PHASE st $-sth soNed Satety issue A 44 Finat RepM Pmgram RepM October 1984 Septemter 1647 l a  !

l

i l

20 Personal Author index CAnspotLLDJ. CoeTAledJA i NUREG/CR-6021 Vot: USER S GU10tf FOR PRISM ARKAN$AS NV. NVREG/CR 5123 STUDES OF THE PATTERN AND AGES OF POST.-

CLE AR ONE . UN T 1. Volume 1 am For Inscocicts METAWORPHC FAULTS IN THE PiEDWONT Cf VIRGWtA AND NUREG/CR 6021 V07 USER'S G FOR PRt$lu ARKANSAS NV- NORTH CAROLINAL i CLEAR ONE . UNtf 1 Volume 2.Propam For RegJetors.

COMUOLJR ,

a CMAtsP.DA NUREG/CR.6077 DECAY HE AT REWOVAL USWG FEEDANDBLEED NUREG/CR 4479 Voi: DEWONSTRAflON OF PERFORWANCE WOO. FOR U S. PRESSURIZED W ATER REACTORS. ,

EUNG OF A LOW LE%EL WASTE $ HALLOW-LAND BURLAL STE.A l Componeon Of Pro <kirve Rasoruelee Tra% port Mosehng Versue 3AttetNJJ. '

F*M Ot+erratene At The Petrate Dsposal P9 Sne,ChaA Rwr Nucteer WREGICR.6129 EXPERMENTAL ASSESSWENT Cf THE INFLUENCE Late. OF DYNAWC LOADWG ON THE PERWEABUTY OF MT AND OF i

DRIED CEWENT SOREHOLE SEA'.S 1 CHENJ.C, NVREG/CR 5130: SENTONITE 80REHOLE PLUG FLOW TESTING NUREG/CR 509$ V01: THERWOOYNAWC NONEQUtVSRtVW IN POST. WtTH FIVE W ATER TYPE 3 CRITICAL-HEATJLUX BoluNG IN A ROO SUNOLE Dewston Of U*

Esponments And Same Results  !

NUREG/CR 6095 V02. THERWOOYNAWC NONEOuttlBRIUM tN POST, NUREG/CR4763. SAFETY-RELATED EQU*WENT $URVfVAL IN HY.

CRITICAL HEAT-FLUX 90tuNG IN A ROD SUNDLE.De a For Stat,. DROGEN BURNS IN LARGE DRY PMI CONTAWWENT BUILDWGS.

trod Quench Front Tests NUREG/CR 6095 V03. THERWODYNAW3C NONEOUIU8Rly i IN POST. OAME- '

CRITICAL HEATILUX BOluNG W A ROO BUNDLE Data Nr A<henc- NVREG/CR4441: FisssON PRODUCT RELEASE 04ARACTERtSTCS rig M Front Tests INTO CONTAtNWENT UNDER DE$aGN BASS AND SEVERE ACCI.

NUREG/CR 5095 YO4. fMERWOOYNAWC NONEQU1UBRIUM tN POST. DENT CONDTIONS.

CRITICAL-NEAT-FLUX BOiUNG IN A ROO BUNOLE Data For Betreet- pggy,,4 t

rig Quench Front Tests.

NUREG/CR4465. CLOSEOUT OF IE SULLETIN 4344 ELECTRICAL CHOKSMt.N C. ORCUtT BREAKERS WITH AN UNDERVOLTAGE TRt? FE ATURE IN ,

NUREG-1233 DRFT FC: REGULATORY ANALYSS FOR USI A40. USE IN SAFETY.RELATED APPUCATIONS OTHER THAN THE RE.

"$EISVC DESCN CRITERIA? Draft Report For Comment #CT gypEO C 4 3 SEOUT OF tt BULLETIN 0043 LOSS OF CHAR.

I CHV,T.L. COAL FROW STANDARD TYPE u.TWOINCH. TRAY AD% ORDER I CELLS.

NUREG/CR 6015. lWPROVED REUA81UTY OF RESCUAL HEAT RE.

I WOVAL CAPA81UT NVREG/CR-4933. CLOSEOUT OF tE SULLETW 801t FAftuRES OF gggggg ggggg ,,Y IN PWRS AS RELATED TO RESOt UTION OF WERCURY WETTED WATRIX RELAYS IN REACTOR PROTECTIVE

~

SYSTEMS OF OPERATING NUCLEAR PC7ATR PLANTS DE$1GNED CHUNG.Y. SY COW 8USTION ENGINEERWG NUREQ/CR-6045 KANSAS-NEBRASKA $ELSMCITY STUDES USWG H KANSAS-NEBRASKA WCROEARTHOUAKE NETWORK Frsal M

NRfG Soft Voi: A REUA8tuTY PROGRAW FOR EWERGENCY a DE$EL GENERATORS AT NUCLEAR PCWER PLANTS Program CLAleORNE.E. Structure NUREG/CR.5134 VALCATION OF GENERC COST ESTlWATES FOR TRUC De LATED ACTIVITIES AT NUCLEAR POWER 6078 vot: A REUASIUTY PROGRAW FOR EWERGENCY NUREG/CR-616a GUCELINES FOR THE USE OF THE EEDS AT THE M E *** # *# D E R " U W **

• q SUB40WFONENT AND SUBSYSTEW LEVEL Frsal Report I**

00ERGE.DX i l

CLARK.A.T'320 NUREG1 NUCLE AR FUEL CYCLE FAOUTY NUREG/CR4316 ACCCENT V09 R1: EVALUATION OF NUCLEAR FAOUTY DE.

AN4Y$1S HANDBOCK- ,.M.U ,me Wes,e m.--. "" "

CLARK.RA I

D NUREG/CR-6016 COMPENDtUM AND COMPARISON OF tNTERNA. gEG TION 4 PRACTCE FOR PLUGGWG REPAIR ANO INSPECTION OF 4728 EQUIPMENT QUAUFiCATsON RESEARCH TEST OF f

} A HtG4 RANGE RADAT10N MONITOR STE AM GENERATOR TUBNG 4

CLETCHERJ.W.

]

j NUREG/uv4674 V05 PRECURSOR $ TO POTENTIAL SEVERE CORE DUNCAN.A NUREG 131 5's TECHNCAL PO$ TION ON ITEMS AND AC THE H GH4EVEL W ASTE GEOLOGC REPOSITORY PROGRAW I DAWAG ACCCENTS 1966.A ST ATUS REPORT. '

$UBJECT TO QUAUTY ASSURANCE REQUtREWENTS~

NUREG/C44674 YO6 PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCCENTS iD64.A ST ATVS REPORT. OYCUS.F.td.

M NM NUREG/CR-6021 V01: USER'S GUCE FOR PRISM ARKANSAS NU- l l

ft,AEG-0837 Yo? N04 NRC TLD DIRECT RADATION WON 1TORING CLE AR ONE . UN!T 1 Volume i.Propam For inapeetort NUREGICR-6021 VOL USER S Gutot FOR PRisiW ARKANSAS PAJ- 1 NE1 WORK Prt,gess Report. Octoter-Decemtier 1947. CLE AR ONE . UNIT 1 Voume 2. Program For Reputators a CORLE YJ.H. giogoNAp, .

] NUREG 1311 FUNDNG THE NRC TRAtNWG PROGRAW FOR NVREG/CR-Sc47. E ARLY AND CONTINUWG EFFECTS OF COWBtNED JTATES ALPHA ANO DETA sRRADATION OF THE LUNG Fhese a Report i CORNE LL.A. gLueON e C.

WREGrCR 6000 WETHOD* JNCERTArNTY ESTMAflON NUREG/CR 5021 YO1: USEWS GUCE FOR PR:SW ARKANSAS NU.

tN WREG 1150 (DR AFT)/ A Revow Paw CLE Am ONE . (W

71 Voeume 1 Program For inspectors

) NUREG/CR 6021 V02 USER'S QUCE FOR PR:5W ARKANSAS NU-4 CORUM.C. CLE AR ONE . UNIT 1 Voume 2. Program For Repators NUREG/CR 5123 STUC't . TERN AND AGES OF POST-

) WETaWORPMC FAUD .CMONT OF V'RGWtA AND tesRITA NORTH CAROUNA NVREG4933 $07: A PRiORITt2ATION OF GENERC SAFETY ISSUES 1

CORWIN.W R EPSTEIN 08.

NUREG/CR 4219 V04 N2 HEi45ECTION STEEL TECHNCtOGY WREGICR 5113 FWOWGS OF THE PEER REVIEW PANEL ON THE PRCGRAW 5em.annwe! Process Rescr1 For Apro Sep**mter 1987. DRAFT REACTOR R:SK REFERENCE DOCUWENT.NUREG-1150 l

f

Personal Author index 21 f2CALANTE.L OLOYERA.

NUREG/CR-4735 V03. EVALUATION AND COMPtLATION OF DOE NUREG/CA-5123 STUDIES OF THE PATTERN AND AGES OF POST.

WASTE PACKAGE TEST DATA. 8. annual ReportFettua y4/y 1H7. METAMORFMC F AULTS IN THE Pif DMONT OF VIRGINTA AND NORTH CAROUNA l NUREG/CP S000 METMODOLOGY FOR UNCERTAINTY ESTMATION 000FREY,P.

IN NUREG 1160 (ORAFT)Concivme Of A Rem Panet NUREG/CR 6160. GUOEUN($ FOR THE USE OF THE EED8 AT THE i SUS COMPC6ENT AND $UBSYSTEM LEVEL Final Report FARQUAHARBON).

NUREG/CR 5021 V01: U$ER'$ GUCE FOR PRISM ARKAN$AS NV- gnggogy,w g, N NVREG 3 NUC(EAR FUEL CYCLE FACMTV ACCCENT ANALYSIS j

/C 21 V02 DUhE ARKANSAS NU- '

CLEAR C6E . UNIT 1 Voksne 2. Program For Regulatort GROM.M R FITZPATRICKA NUREG/CR 501$ IMPROVED REUAB*LITY OF RE50 VAL HE AT RE. NUREG/CR4639 V01: NUCLEAR COMPUTERt2ED UBRARY FOR A$-

MOVAL CAPABILITY IN PWR$ AS RELATED TO RESOLUTION Op SES$WG REACTOR REL'A8tuTY (NUCLARR) Vodume i Summary De.

GENERC t$$UE 99. SC'9D0"

^

FLANASAN.G.F. GUARRO.S.

NUREG/CR-5021 V01: U$ER'$ GUCE FOR PR$M ARKAN$AS NV. NUREG/CR-5113. FIND (NGS OF THE PEEP REVIEW PANEL ON THE CLE AR ONE . UNIT 1 Volume 1 Proaram Fct inspectors DRAFT REACTOR RISK REFERENCE DOCUMENT.NUREG 1150.

NUREG/CR-5021 V02 USER S 6UCE FOR PRi$;M ARKANSAS NV.

j CLEAR ONE . UNIT 1. Volume 2.Prcgr6m For Regulators. QUE RRIERI.D.

NUREG/CR-4042 V06 DEGRADED PiPtNG PROGRAM . PHASE !! Sath FOLEY,WJ. Program Report October 1986. septeace 1967.

, NUREG/CR4665. CLOSEOUT OF lt BULLETIN 83-04 ELECTRICAL i CIRCUlf BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN QUTHRIE,V H.

NUREG/CR-5021 V01: USER $ GUCE FOR FRi$:M ARKANS4 -

USE IN SAFETY.RELATED APPUCATONS OTHER THAN THE RE-ACTOR TRIP SY$ TEM CLE AR ONE . UNIT 1 Volume 1. Program For inspectors NUREG/CR 4932: CLOFEOUT OF IE BULLETIN SM3 LOSS OF CHAR. NUREG/CR-5021 V02 USER S GUCE FOR PRISM ARKANSA. w -

d COAL FROM STANDARD TYPE II.TWOINCH, TRAY AOSORSER CLEAR ONE UNIT 1 Volume 2, Program For Reguistors CELLS i NUREG/CR-4933. CLOSEOUT OF IE BULLETIN so 10 FAILURES OF HAFFNER.D.R.

MERCURY WETTED MATRIX RELAYS W REACTOR PROTECTIVE NUREG/CR.4315 V09 Rt. EVALUATON OF NUCLEAR FACluTY DE.

SYSTEMS OF OPERATWG NUCLE AR POWTR PLANTS DESGNED COMMt$$Of0NG PROJECTS Sisnmarf Status Report,Three Ude BY COMBUSTCH ENGWEERING. 161and Urut 2,Radcoctrve Weste And Laundry $Npments FRAGOLAJ.R. HAgEN,E.W.

NUREG/CR 5078 V01: A RELIABIUTY PROGRAM FOR EMERGENCY NUREG/CR-4674 VOS PRECURSORS TO POTENTAL SEVERE CORE j DtESEL GENERATOR $ AT NUCLEAR POWTR PLANTS Program DAMAGE ACCCENTS 1968.A $TATU$ REPORT.

$1ructure NUREG/CR4674 YO6 PRECURSOR $ TO POTEN'LAL SEVERE CORE FRARERA NVREGICR-473E V03 EVALUATION AND COMPILATCN OF DOE HANN.F.F, i WA$TE PACKAGE TEST DATA. 84nrual Report February 4/y 1987- NUREG/CR 5067. EARLY AND CONTWUWG EFFECTS OF COM8fNED ALPHA AW 8 ETA IRWATON W THE U,M h M Repod FRANK 1 NUREG/CR 515D STEAM GENERATOR OPERAtlN3 H ALg,F,y, EXPERIENCE bpdate For 1964-1966 NUREG/CR4664 V01: THERVODYNAMC TABLES FOR NUCLEAR GALVE AN,WJ. WASTE ISOLATON A<peove SJutens Datatese

, NUREG/CR4639 Vf1; NUCLEAR COMPUTERt?t0 UBRA9Y FOR Ab-SES$1NG REACTOR REUA8iUTY (NUCLARR) Volume i Summary De- HALLD'G/CA gygg 4735EVALUATION V03 AND COMPtLATION OF DOE

' **

• W ASTE PACKAGE TEST DATA. 84nnual Reps . ettuary-Juty 1987.

GAUDETTEXV. "

NUR / 6 SE ON TE BOREHOLE PLUG FLOW TESTWG NUR G/CR 5000 METHOOOLOGY FOR UNCERTAfNTY ESTIMATON W NUREG 1150 (DRAFT)ConcA4cns Of A Rom Panet.

GENTILLON.CA HARRIS .0.

1 NUREG/CR4639 V01: NUCLEAR COMPUTERIZED UBRARY FOR AS.

l SESSING REACTOR REUABtUTY (NUCLARR). Volume i Summary De-NUREG/CR4674 V05 PRECURSORS TO POTENE SEVERE CORE DAMAGE ACCCENTS 1996,A STATUS REPORT '.

1. NUREG/CR4674 V06 PRECURSORS TO PCTENTML SE%TRE CORE i i GE RTMAN.D.L DAMAGE ACCCENTS 1966.A STATVS REPORT.

i NUREG/CR-4639 V01: NUCLE AR COMPUTERt?ED UBRARY FOR A$-

5 NG REACTOR REUA8tuTY (NUCLARR) Volume L$ummary De-MN NUA C 4735 YO3 EVALVATiON AND COMP 1LATON OF DOE WA$TE PACAAGE TEST DATA Dennual Rep:vtFettua y JuPy 1987.

l OHADIAllX  !

I NUREG/CR4062 V06 DEGRADED PiPWG PROGRAM PMASE N $ath H A WRINS.F. I Program Report October 1986 - Septerreer 1987. NURE G/CR-5151. PE RFORM ANCE.8 ASED INSPECTONS OILSERT,8 Q. HEMPHILL.G M.

NUREG'CR4639 V01: NUCLE AR COMPUTER! ZED UBRARY FOR AS. NUREG/CR 504a ESTiMATON TECHNOVE$ FOR COMMON CAUSE SE55WG RE ACTOR REUA8 UTY (NUCLARR) VcAme L Summary De. FAILURE EVENTS HE NNIC K,A. l G4LMORE,W E. NUREG/CR4M5 CLOSEOUT OF it SULLETW 6Me ELECTRICAL 1 NUREG/CR4639 V01 NUCLEAR COMPUTERIZED UBRARY FOR AS- CIRCt/T BREAAER$ WITH AN UNCERVOLTAGE TRIP FEATURE tN I SE S$WG RE ACTOR REuASIUTY (NUCLARR) vchme i Surree y De- USE W EAFETv RELATED APPUCATONS OTHER THAN THE RE.  !

l ocrphort ACTOR TRIP $Y$ TEM NUREG'CR4932 CLOSEOUT OF lt BULLETW eM3 LOSS OF CHAR- l GILPtW.K E- COAL FROM $1 ANDARD TYPE m.TWCHNCH.TR AY ADSORSER NUREG'CR 5106 USER $ GUCE FOR THE TACTS COMPUTER CODE. CELLS

( 22 Personal Author Index NUREG!CR 4933 CLOSEQUT or if BULLETIN so-19 FArLUAE$ OF Corr (anson Of Preectue Pa$onucwe Transport Mccevg versus UE RCURL AETTED MATR:X RFt AY$ IN PE ACTOR PROTECTIVE Fed Ceserve$ons At The Ntiste Disposal P4 Site.Chan Rwer Nuclear i $YSTEV$ OF OPE RAT 43 NUCLE AR PCWER PLANTS DE$tGNED La$s L BY COUSU$ TON ENGWE ER.NG l

KING.D 5.

HILDE BR AND.G M. NUREG'CA 4763 $AFETY.RELATED EQV;PVENT $URVIVAL IN HY.

NUREG/CR 5045 AANSA$ NEBRASm_A SEiSVOTY $TUDES USWG 3 THE pt ANSAS-NE B R AS AA UCRO( ARTHQU A> E NE TWORs Final OROGEN BURN 5 IN t ARGE ORY PWR CONTA:NVENT DutLDWGS Z

Reput giya,y,g, E

HOF M ANN.P MENSM3 NWS & W W MM MR M M

$ NUREG/CR 5113 FiNDiNCS OF THE PEER REVIEW PANEL ON THE MW MM@ R S t WW W WTW W,%M H1M

{ ORAFT RE ACTOR RtSA REFEAENCE DOCUVENT.NUREG 1150 ggyg HOR $T.C L NUREG 1226 DEVELOPVENT AND UTIU2 AT ON OF THE NRC NUREGICA 5153 FRED +CTON OF CHECK V ALVE PERFORVANCE POLCY STATEMENT ON THE REGULATON OF ADVANCED NV.

AND DEGHADATON W NUCLE AR POAER n ANT SYSTEU$ CLE AR POWER PLANTS IN TE RR A N TE.C. KIRCHNE RJ R.

NUREG/CR 4735 V03 EVALVATON AND COVPtLATON OF DOE NUREG/CR-5021 V01: USER $ GUCE FOR PR $.V ARKANSAS NV-W ASTE FACAAGE TEST DATA B annual Repor1FsWay#y 1987. CLE AR ONE . UNIT 1. Volume 1.Pecgram For inspectwa r NUREG/CR $021 YO2 USER $ GUCE FOR PRSM ARKANSAS NV. .s N REG /CR 5082 $ VULATON EuPt R. VENTS ON TWGPHASE N AT.

x UR AL CIRCULATON IN A Fr.EC4113 Ft OW V8UAlt2ATON LOOP. KIRK M AN) Q.

f J ACOBUS.M J NUREG/CR-5021 V01: U$ER $ GUCE FOR PR$V ARKANSAS NV-NUREGtCR 4726 EQU$ VENT QUAUFICATON RESE ARCH TEST OF CLEAR ONE UNIT 1 Volun LPrwam Fw ws

? A H;GH %NGE RADIATON MOPOTOR NUREG/CR 5021 V02 USER $ GU CE FOR PR6V ARKANSAS NV.

CLE AR ONE UNIT 1. volume 2.Prcyrem Fw Rejpstors N J AECH.J L NUREG/CR 4605 TRAW NG M ANUAL C4 $7AT!STICAL VETHODS KLEIN S M-C FOR NUCLE AR MATERIAL MAN AGEVENT. NUREGICR 5147; FUNDAVENTAL ATTR'BUTES OF A PRACTCAL k CONFiGURATON MANAGEVENT PROGRAM FOR NUCLEAR PLANT JOHNSONJ- DE$tGN CONTROL NURE G'CR 5151 PERFOAMANC' 9 ASED INSPECTON$

KNAPP,R.

NVA G R 5142 DUCTILE TO BRITTLE TOUGHNESS TRANSITON

[ CHARACTER.2ATON OF A5339 STEEL HE KANSADE BRAMA WCAOE ARTHOU Ak E NETWOR A Final Report

, ($1 M $.

'p 1

AJAEG'CR 5153 FREDCTON OF CHECK V ALVE PE RFOAM A>'.E MOUTSX t

AND DE GR ADATON IN NUCLE AR POWE R PLANT Sv 5TEUS NUREGtCR 5000 UETHOOOLOGY FOR UNCERTAWTY E$TIMATION A

e K AM.F B.

IN NUREG 1150 (DRAFT) Comiusons Of A Rem Panel F

NUREG/CR 5019 NEUTRON E tPOSUAE PARAVETERS FOR THE KR AME R.G.

UCTALLURG' CAL TE ST SrEC:VENS IN THE FIFTH HE AVY SEC. NUREG/CR 4062 V06 DEGR.59ED P#tNG PAOGRAM , PHASE 11 Sat'i TON STE EL TECHNOLOGY IRR AD: ATON SE R:ES CAPSULES Prcvam Repyt October 1966 Septemter 1987 K A M M E R E R.C. KUgyg,q J, NUREG 1311 F UND>NG THE NRC TR A:N NG PROGRAM FOR STATES NUREGrCR $016 COVPENDIUM AND COUPARiSON OF INTERNA.

TlONAL Pr;ACTICE FOR PLUGGW3 REPA6R AND INSPECTION OF j

K ANNINEN.M F. STE AM GtNERATOR TUBW3 g NUPE G'CP@75 )ROCEEDMS OF CSNUNRC WORKSHOA ON ggwoop,y g DUCTILE PPWG FR ACTUAE VECHANCS gyggg,CR 4082 V06 DEGR ADED PIPING PROGRAM . PHASE H Siath i K ASTENSERG.W E. IVctam Report October 1969. Septemt4r 1647.

7 NUREG/CR 5113 F ND!NGS OF THE PEER REV En PANEL ON THE OR art AE ACTOA R,SK REF ERENCE DOCUVENT.NUREG 1150 LE

KATHRENRL.

N RfG/CR.5082 S MULATON ExPERIVENTS ON TWGPHASE N URAL CiRCULATON IN A FREON 113 JLOW ViSJ ALLZATON LOC'.

?

t NvREG'CPK93 PROCEEDINGS OF THE MEETIN3 ON ULTR ASEN-5,TrvE TECHNQUES FOR UC ASUREMENT OF URANtuu W BO- L E WINJ.A.

LCGCAL SAMPLE S AND THE NEPHROTOUC4TY CS UR ANtu NUREG'CR-4728 EQU$ VENT OUALIFICATION RESE ARCH TEST OF A HiGH RANGE RAD:ATON MON: TOR

} NUAEG rCR 5344 EST:V ATON TECHNQUES FOR COVVON CAUSE LIG G E TT.W.

F A! LURE ESENTS NUREG/CR 4735 V03 EV ALUATON AND COMPtLATON OF DOE I KENNEDYJE. ' ^ '

• M g NURE G 1318 TECHN' CAL POSiTON CN ITEUS AND ACTIVIT:E S IN Lly g g,g,y, u THE H'G4 L E VE L WASTE GE Ot.OGC REPOSITORY PROGRau gynga,CR 5151 PERFORVANCE P ASED MPECTONS p SUBJECT TO QuauT( ASSUR ANCE AECUSEVENTS KHAN.T.A LINZ E R.M.

! NUAE G 'CR 5036 Ort U 2 ATICW OF THE CCNTROL OF CONT AVWA- WREG/CA-4735 VO3 E V ALV ATON AND CCVPILATON OF DOE F TKyd AT NUCLE AR PCWE R PL ANTS W A$TE PACKAGE TEST DATA B.awat Rooort FetWaWuh i&47.

K H Af tB-R AMB AR LOFORENLY.

NUFt G 'CR AMI FISSON PC'A>C' AE LE ASE CHAR ACTER:SilC$ NUAEG'CR 5078 VC1 A REUABiUTY PAOGRAW FOR EVERGENCY WTO CONT A NVENT UNDER DESIGN BAS!S AND SEVERE ACC; D ESEL GENERATOR $ AT NUCLEAR POWER PL ANT $ Pecgram DE NT CO*OTONS 5truct.s e h tLL E Y.R W. LOOMi$.G NJRE G'CR 48?9 W1 DE VONSTH ATON Of pg AF OAV ANCE UDO.

NUAEG'CR 5072 DECAY HE AT REMOV AL US:NG FEED ANJBLEED E UN3 CV A LCA LE n E L W ASTE SH ALLCW L AND BUR. AL SITE A FOR U S PRESSUR ZED W ATER RE ACTOR 5

\

Personal Author Index 23 LOYA* *e F. NUREG/CR.5095 V04: THERMODYNAMIC NONEQUluBRIUM IN POST-flVREG 1320: NUCLEAR FUEL CYCLE FACluTY ACCOENT ANALYSIS CRITICAL-HEAT FLUX BOluNG IN A ROD BUNDLE. Data For Retreat.

HANDBOOK- ing Quench Front Tests.

LUSENAU,J.O. NEWTON,0.J.

NUREG 1311: FUNDING THE NRC TRAINING PROGRAM FOR NUREG/CR-5067: EARLY AND CONTINUING EFFECTS OF COMBINED STATES. ALPHA AND BETA IRRADIATON OF THE LUNG. Phase 11 Report.

MARSCHALLC.W. NICHOLS.B.D.

NUREG/CR-4082 V06: DEGRADED PIPING PROGRAM PHASE li.Sath NUREG 1320: NUCLEAR FUEL CYCLE FACluTY ACCOENT ANALYSIS Program Report October 1986 September 1987. HANDBOOK-MAUDERLY,J.L NICOLETTE V.F NUREG/CR 5067: EARLY AND CONTINUING EFFECTS OF COMBINED NUREG/CR-4763: SAFETY RELATED EQUIPMENT SURVIVAL IN HY-ALPHA AND BETA IRRADIATION OF THE LUNG. Phase ll Repod DROGEN BURNS IN LARGE DRY PWR CONTAINMENT BUILDINGS.

MCCONNM.J.W. NOUR8AKHSH.H P NUREG/CR-5137: BIODEGRADATON TESTING OF TMI 2 EPtCOR-il NUREG/CR-4881: FISSON PRODUCT RELEASE CHARACTERISTICS WASTE FORMS.

INTO CONTAINMENT UNDER DESIGN BASIS AND SEVERE ACCI-MCLAUGHUN,M. DENT CONDITIONS NUREG/CR 5138: VAUDATION OF GENERIC COST ESTIMATES FOR CONST UC ON LATED ACTMTIES AT NUCLEAR POWER O R.

P ogram Report October 1986 September 1987.

MCNAMARA,N.

NUREG-0837 V07 N04: NRC TLD DIRECT RADIATON MONITORING OSTRACH S.

NETWORK.Prooress Report. October-December 1987. NUREG/CR 5113: FINDINGS OF THE PEER REVIEW PANEL ON THE NUREG-0837 V08 N01: NRC TLD DIRECT RADIATON MONITORING DRAFT REACTOR RISK REFERENCE DOCUMENT,NUREG-1150.

NETWORK. Progress Report. January March 1988.

MILLER.LF. NUREG 1320- NUCLEAR FUEL CYCLE FACIUTY ACCIDENT ANALYSIS NUREG/CR 5019 NEUTRON EXPOSURE PARAMETERS FOR THE HANDBOOK.

METALLURGCAL TEST SPECIMENS IN THE FIFTH HEAVY SEC-TON STEEL TECHNOLOGY IRRADIATON SERIES CAPSULES. PAPASPYRCPOULOS NUREG/CR-4082 V06: DEGRADED PIPING PROGRAM PHASE II. Sixth NU C'R-5045: KANSAS-NEBRASKA SEISMICITY STUDIES USING THE KANSAS NEBRASKA M. 7;ROEARTHOUAKE NETWORKFinal PARRY,G.W.

Repod NUREG/CR 4836: APPROACHES TO UNCERTAINTY ANALYSIS IN MILSTEAD,W.

PROBAB'LISTIC RISK ASSESSVENT.

NUREG-0933 S07: A PRORifl2ATION OF GENERIC SAFETY ISSUES. pAULA.H.M.

MINARICK,J.W. NUREG/CR-5021 V01: USER'S GUCE FOR PRISIM ARRANSAf NU.

NUREG/CR-4674 V05: PRECURSORS TO POTENTIAL SEVERE CORE CLEAR ONE UNIT 1. Volume 1,Progrsm For inspectors.

DAMAGE ACCOENTS 1986.A STATUS REPORT. NUREG/CR-5021 V02 USER S GUloE FOR PRISIM ARKANSAS NU-NUREG/CR 4674 V06: PRECURSORS TO POTENTIAL SEVERE CORE CLEAR ONE UNIT 1. Volume 2. Program For Regulators.

DA.VAGE ACCOENTS:1986.A STATUS REPORT. PER$1NKO,D.

MISHIMA.J. NUREG 1214 R03: HISTORICAL DATA

SUMMARY

OF THE SYSTEMA 1 NUREG-1320: NUCLEAR FUEL CYCLE FACluTY ACCIDENT ANALYSIS IC ASSESSMENT OF UCENSEE PERFORMANCE.

PHILLIPS,S.L MOCHIO.T. NUREGICR 4864 V01: THERMODYNAMIC TABLES FOR NUCLEAR NUREG/CR-3509: POWER SPECTRAL DENSITY FUNCTONS COM- WASTE ISOLATON. Aqueous Solubons Database.

PATIBLE WITH NRC REGULATORY GUIDE 1.60 RESPONSE SPEC-TRA. PITTMAN,J.

NUREG-0933 $07: A PRIORITIZATION OF GENERIC SAFETY ISSUES.

MOLTY ANER,0.L NUREG/CR-4879 V01: DEMONSTRATION OF PERFORMANCE MOD- PRASSINOS,P.G.

EUNG OF A LOW LEVEL WASTE SHALLOW-LAND BURIAL SITE.A NUREG/CR 5042 S01: EVALUATION OF EXTERNAL HAZARDS TO NU-Companson Of Pre $ctus Radeonuchde Transport Modehng Versus CLEAR POWER PLANTS IN THE UNITED STATES.Seisnic Hazard.

Field Observatorts At The Nitrate Dsposal Pit Sate.Challt Rever Nuclear Labs. PUTN AM C.H.

NUREG/CR 5151: PERFORMANCE-8ASED INSPECTIONS.

MYERS.D.A.

NUREG/CR 4879 V01: DEMONSTRATION OF PERFORMANCE MOD. R AMSDE LLJ.V.

EUNG OF A LOW LEVEL WASTE SHALLOW-LAND BURIAL SITEA NUREG/CR 5055: ATMOSPHERIC 0 FrUSION FOR CONTROL ROOM Compenson Of Predictue RadonucMe Transport Modeling Versus HABITABluTY ASSESSMENTS.

ie Observabons At The Nitrate Dsposal Pit Sete. Cham Rwer Nuclear l

NUREG/CR-5000 METHODOLOGY FOR UNCERTAINTY ESTIMATION l NAKAGAKI,M. IN NUREG 1150 (DRAFT) Concluwons Of A Review Panet.

NUREGICR 4082 V06: DEGRAvED PIP!NG PROGRAM PHASE II. Sixth Program Report. October 1986. September 1987. R E E D.J.W.

NUREG/CR 5113: FINDINGS OF THE PEER REVIEW PANEL ON THE NETI,S. DRAFT REACTOR RISK REFERENCE DOCUMENT.NUREG 1150.

NUREG/CR-5095 V01: THERMODYNAMIC NONEOUluBRIUM IN POST-CRITICAL HEAT-FLUX BOlUNG IN A ROD BUNDLE Desenption Of REICH,M.

Expenments And Sample Results NUREG/CR-5105: RESPONSE MARGtNS INVESTIGA.10N OF PIP 1NG NURLG/CR 5095 V02: THERMODYNAMIC NONEQUlUBRIUM IN POST- DYNAMIC ANALYSES USING THE INDEPENDENT SUPPORT CRITICAL HEAT FLUX BOtUNG IN A ROD BUNOLE Data For Stabi- MOTION METHOD AND PVRC DAMPING hred Ovench Front Tests NUREG/CR 5095 V03: THERMODYNAMIC NONEOUfUBRIUM IN POST. RICHARDS.E.H.

CRITICAL HUT FLUX BOluNG IN A ROD BUNDLE. Data For Advanc. NUREG/CR-4728. EQUIPMENT OUAUFICAT'ON RESEARCH TEST OF ing Ovench Front Tests. A HIGH RANGE RADIATON MONITOR.

24 Personal Author index RfCKER.R. SHINOZUK tM.

NUREG'CR-4735 V03: EVALUATON AND COMPILATON OF DOE NUREG/CR-3509: POWER SPECTRAL DENSITY FUNCTONS COM-WASTE PACKAGE TEST DATA. Biannual ReportFebruary July 1987. PATIBLE WITH NRC REGULATORY GUCE 1.60 RESPONSE SPEC-RIGGS.R.

NUREG-0933 507: A T'RORIT12ATON OF GENFF SAFETYISSUES. SHULL,R.

NUREG/CR-4735 V03: EVALUATION AND COMPILATON OF DOE EG CR-5138: VAUDATON OF GENERIC COST ESilMATES FOR A A Bennual AmbMM M CONSTRUCTON RELATED ACTIVITIES AT NUCLEAR POWER SIEGEL J.J.

NU DELINES FOR THE USE OF THE EEDB AT THE NUREG/CR 3899 S01: UTIUTY FINANCIAL STABluTY AND THE SUB-COMPONENT AMD SUBSYSTEM LEVEL.Fr,a' Report.

^ 0 Internal And External Funding.

I RITZMAN,R.L l NUREG/CR-5113; FINDINGS OF THE PEER REVIEW PANEL ON THE SIEGEL,M.D.

DRAFT REACTOR RISK REFERENCE DOCUMENT,NUREG-1150. NUREG/CR-4864 V01: THERMODYNAMC TABLES FOR NUCLEAR l

i WASTE ISOLATON. Aqueous Solutions Database.

, RORERTSON.D.E.

NUREGICR-4879 V01: DEMONSTRATON OF PERFORMANCE MOO. SILVESTER,LF.

ELING OF A LOW-LEVEL WASTE SHALLOW LAND BURIAL SITE.A NUREG/CR-4864 V01: THERMODYNAMIC TABLES FOR NUCLEAR Companson Of Predictue Radonucide Transport Modeling versus WASTE ISOLATON Aqueous Solutions Database.

Observatons At The Neate Disposal Pit Site.Cha rk Rrver Nuclear

^

ggg NUREG/CR-5138: VAUDATON OF GENERIC COST FSTIMATES FOR ROSINSON,T, CONSTRUCTION RELATED ACTIVITIES AT NUCLEAR POWER PUREG/CR 5160: GUOELINES FOR THE USE OF THE EEDB AT THE PLANTS Final Report SUB COMPONENT AND SUBSYSTEM LEVELFinal Report NUREG/CR-5160: GUlOELINES FOR THE USE OF THE EEDB AT THE SUB-COMPONENT AND SUBSYSTEM LEVEL.Fanal Report ROGERS.R.D.

NUREG/CR-5137: BIODEGRADATION TESTING OF TMI 2 EPICOR.li SNIPES,M.8.

WASTE FORMS. NUREG/CR-5067: EARLY AND CONTINUING EFFECTS OF COMBINED ALPHA AND BETA IRRADIATON OF THE LUNG. Phase il Report RMmu NUREG/CR 4082 V06. OEGRADED PIPING PROGRAM PHASE ILSixth SPLETZER,8.L Program Report October 1986 September 1987. NUREG/CR-4763: SAFETY-RELATED EQUIPMENT SURVIVAL IN HY.

DROGEN CURNS IN LARGE DRY PWR CONTAINMENT BUILDINGS.

ROTH8ERGA NUREG 1296: THERMAL OVERLOAD PROTECTION FOR ELECTRC STA LLM AN N,F.W.

MOTORS ON SAFETY RELATED MOTOROPERATED VALVES - GE* NUREG/CR 5019: NEUTRON EXPOSURE PARAMETERS FOR THE NERIC ISSUE 11 E 6.1.

METALLURGICAL TEST SPECIMENS IN THE FIFTH HEAVY-SEC-RUBIN,A.M. TION STEEL TECHNOLOGY 1RRADIATON SERIES CAPSULES.

NUREG 1109: REGULATORY /BACKFIT ANALYSIS FOR THE RESOLU-STEEPLES.D W '

TON OF UNRESOLVED SAFETY ISSUE A-44. STATION BLACKOUT.

NUREG/CN-5045: KANSAS-NEBRASKA SEISMICITY STUDIES USING RUSPl.J. THE KANSAS-NEBRASKA MCROEARTHOUAKE NETWORK. Final NUREG/CR-4735 V03: EVALUATON AND COMPILATION OF OOE Report.

WASTE PACKAGE TEST DATA. Biannual ReportFebruary July 1987.

STETKAR,J.W.

SAMARAS.E.F. NUREG/CR 5113: FINDINGS OF THE PEER REVIEW PANEL ON THE NUREG/CR-3509: POWEP SPECTRAL DENSITY FUNCTIONS COM- ORAFT REACTOR RISK REFERENCE DOCUMENT,NUREG 1150.

PATIBLE WITH NRC REGULATORY GUOE 1.60 RESPONSE SPEC.

TRA. STOKLEY,J.

NUREG/CR-5150: STEAM GENERATOR OPERATING SCHWARTZ,l. EXPERIENCE. Update For 1984-1986.

NUREG4020 V12 NO3: UCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of February 29.1988 (Gray Book 1) STRUCKMEYER,R.

WUREG4020 V12 N04: UCENSED OPERATING REACTORS STATUS NUREG 0837 V07 N04. NRC TLD DIRECT RADIATON MONITORING

SUMMARY

REPORT. Data As Of March 31.19881 Gray Book I) NETWORK Progress Report. October-December 1987.  :

NUREG 0020 V12 N05. UCENSED OPERATING REACTORS STATUS NUREG-0837 V08 Not: NRC TLD DIRECT RADIAT ON MONITORING

SUMMARY

F.EPORT. Data As Of Apnl 30,1988 (Gray Book 1) NETWORK. Progress Report, January-March 1988.

SCIACC A.F. SZUKIEWICZ,A.J.

NUREG/CR 5138: VAUDATION OF GENERIO COST ESTIMATES FOR NUREG 1217 ORFT FC: EVALUATON OF SAFETY IMPUCATIONS OF CONSTRUCTON-RELATED ACTIVITIES AT NUCLEAR POWER CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS.Techrwcal NUR $1 DELINES FOR THE USE OF THE EEDB AT THE Fegs Relaw To UnreM Sa% lasue A6aM RepM N SUB-COMPONENT AND SUBSYSTEM LEVELFinal Repoa NU 8 ORFT FC: REGULATORY ANALYSIS FOR PROPOSED SCOTT,8.R. RESOLUTION OF USI A 47. Safety implicatons Of Control NUREG/CR.5067: EARLY AND CONTINUtNG EFFECTS OF COMBINED Systems Draft Rept For Comment ALPHA AND BETA IRRADIATON OF THE LUNG Phaa 11 Report fERRELL J.B.

SCOTT,P. NUREG/CR 5013: FATIGUE UFE CHARACTERIZATION OF SMOOTH WUREG/CR 4082 V06: DEGRADED PIPING PROGRAM PHASE ILSrith AND NOTCHED PIPlNG STEEL SPEOMENS IN 288 DEGREE C AIR Program Report October 1986 September 1987. ENVIRONMENTS SERKlZ,A.W. THEOFAHOUS,T.G.

NUREG 1273- TECHNICAL FINDINGS AND REGULATORY ANALYSIS NUREG/CR.5113: FINDINGS OF THE PEER REVIEW PANEL ON THE FOR GENERIC SAFETY ISSUE 11 E.4 3. "CONTAINMENT INTEGRITY ORAFT REACTOR RISK REFERENCE DOCUMENT,NUREG 1150.

THOMAS,C.W.

SHAUKAT,S.K. NUREG/CR-4879 V01: DEVONSTRATON OF PERFORMANCE MOD-NUREG 1233 DAFT FC: REGULATORY ANALYSIS FOR USl A 40, ELING OF A LOW. LEVEL WASTE SHALLOW. LAND BURIAL SITE A

' SEISM C DESIGN CRITERIA." Oraft Repor1 For Comment Companson Of Predictwo Ratonuclide Transport Modeling Versus

P;rsonal Author index 25 Feld Observatens At The Nitrate Disposal Pit Site. Chalk River Nuclear WATUNGTON.B.

Labs. NUREG/CR-5138: VAUDATON OF GENERC COST ESTIMATES FOR CONSTRUCTON-RELATED ACTIVITIES AT NUCLEAR POWER TINGLEA PLANTS Final Report.

NUREG/CR 5015: IMPROVED REUABluTY OF RESICUAL HEAT RE. NUREG/CR 5160- GUOELINES FOR THE USE OF THE EEDB AT THE MOVAL CAPABILITY IN PWRS AS RELATED TO RESOLUTON OF SUB COMPONENT AND SUBSYSTEM LEVEL Fanal Report.

GENERC ISSUE 99.

WEBER,J.R.

TUZLA,K- NUREG/CP-0093: PROCEEDINGS OF THE MEETING ON ULTRASEN-NUREG/CR 5095 V01: THERMODYNAMIC NONEQUluBRIUM IN POST- SITIVE TECHNOUES FOR MEASUREMENT OF URANIUM IN BIO-CRITCAL HEAT FLUX BOILING IN A ROD BUNDLE.Desenption Of LOGICAL SAMPLES AND THE NEPHROTOXICITY OF L'RANIUM.

Erpenments And Sar.mple Results.

NUREG/CR 5095 V02: THERMOOYNAMC NONEQUIUBRIUM IN POST- WEST,0.B.

CRITCAL-HEAT-FLUX BOluNG IN A ROD BUNDLE. Data For Stabi- NUREG/CR 5106: USER'S GUIDE FOR THE TACT 5 COMPUTER CODE.

lized Quench Front Tests.

NUREG/CR-5095 V03: THERMOOYNAMC NONEOUluBRIUM IN POST- WHEELER,T.A.

CRITICAL HEAT # LUX BOluNG IN A ROD BUNDLE. Data For Advanc. NUREG/CR 4836: APPROACHES TO UNCERTAINTY ANALYSIS IN ing Quench Front Tests. PROBABIUSTC RISK ASSESSMENT.

NOREG/CR-5095 V04: THERMODYNAMIC NONEQUIUBRIUM IN POST-CRITCAL NEATJLUX BOluNG IN A ROD BUNDLE. Data For Retreat. WILKOWSKI.G.M.

ing Quench Front Tests. NUREG/CR-4082 V06: DEGRADED PtPING PROGRAM PHASE II. Sixth Program Report. October 1986. September 1987.

UNAL,C.

NUREG/CR 5095 V01: THERMODYNAMIC NONEQUlUBRIUM IN POST- WILUAMS.P.M.

CRITCAL-HEAT-FLUX BOluNG IN A ROO BUNDLE. Description Of NUREG 1226: DEVELOPMENT AND UTIU2ATON OF THE NRC Expenments And Sample Results. POUCY STATEMENT ON THE REGULATION OF ADVANCED NU- l NUREG/CR-5095 V02: THERMODYNAMIC NONEQUluBRIUM IN POST. CLEAR POWER PLANTS. I CRITICAL-NEAT # LUX BOlUNG IN A ROD BUNDLE. Data For Stabi-kzed Quench Front Tests. WISSEY,S.J. )

NUREG/CR 5095 V03: THERMODYNAMIC NONEQUluBRIUM h DOST. NUREG/CR4778: PREUMINARY STUDIES OF THE MORPHOLOGY OF CRITICAL-HEAT FLUX BOtuNG IN A ROO BUNDLE. Data For Advanc. THERMAL GRADIENT TUBE DEPOSITS FROM FISSON PRODUCT m' g Ouench Front Tests. RELEASE EXPERIMENTS.

NUREG/CR-5095 V04: THERMODYNAMIC NONEQUluBRIUM IN POST.

CRITCAL-HEATELUX BOILING IN A ROD BUNDLE. Data For Retreat. YAMASHITA.T.

ing Ovench Front Tests. NUREG/CR-4777: STEAM OXIDATON OF ZlRCALOY CLAODING IN THE ORNL FISSION PRODUCT RELEASE TESTS.

VISKANTA.R.

NUREG/CR 5113: FINDINGS OF THE PEER REVIEW PANEL ON THE YOON,W.H.

DRAFT REACTOR RISK REFERENCE DOCUMENT,NUREG-1150. NUREG/CR 5015: IMPROVED RELIABlUTY 0: RESOUAL HEAT RE.

MOVAL CAPABluTY IN PWRS AS RELATED TO RESOLUTION OF W ANO,J.K. GENERIC ISSUE 99.

NUREG/CR-5159. PREDICTON OF CHECK VALVE PERFORMANCE AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS. YOUNG.J.L NUREG/CR-4879 V01: DEMONSTRATON OF PERFORMANCE MOD-WANG,Y.K. EUNG OF A LOW LEVEL WASTE SHALLOW-LAND BURIAL SITE.A NUREG/CR 5105: RESPONSE uARGINS INVESTIGATION OF PtPING Compenson Of Prodctrve Radeonuchde Transpod Modehng Versus DYNAMIC ANALYSES USING THE INDEPENDENT SUPPORT Feld Observat>ons At The Nrtrate Disposal Pit Sde, Chalk Rrver Nuclear MOTON METHOD AND PVRC OAMPiNG Labs.

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

A533B Steel Blodegradation NUREG/CR-5142: DUCTILE TO BRITTLE TOUGHNESS TRANSITION NUREG/CR 5137: BODEGRADATION TESTING OF TMI 2 EPICOR-il CHARACTERIZATION OF A5338 STEEL WASTE FORMS.

ACRS Reports B6ological Sample NUREG 1125 V09: A COMPILATON OF REPC9TS OF THE ADVISORY NUREG/CP 0093. PROCEEDINGS OF THE MEETING ON ULTRASEN-COMMITTEE ON REACTOR SAFEGUARDS.1987 Annual. SITIVE TECHNIQUES FOR MEASUREMENT OF URANIUM IN BIO-LOGICAL SAMPLES AND THE NEPHROTOXICITY OF URANIUM.

Abnormal Occurrence NUREG 0090 V10 NO3: REPORT TO CONGRESS ON ABNORMAL Bolling Water Reactor OCCURRENCES July September 1987. NUREG-1217 DRFT FC: EVALUATON OF SAFETY IMPLICATIONS OF NUREG-0090 V10 N04: REPORT TO CONGRESS ON ABNORMAL CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS. Technical OCCURRENCES October-December 1987. Findogs Related To Unresolved Safety issue A-47.Drgt Report For Comment.

Accident Analysis NUREG/CR 5076. AN APPROACH TO THE QUANTIFICATION OF SELS.

NUREG 1320: NUCLEAR FUEL CYCLE FACILITY ACCIDENT ANALYSIS MIC MARGINS IN NUCLEAR POWER PLANTS.The importance Of HANDBOOK. BWR Ptant Systems And Functions To Seismic Margins.

NUREG/CR 5160 GUIDELINES FOR THE USE OF THE EEDB AT THE Accident Sequence SUB-COMPONENT AND SUBSYSTEM LEVELFinal Report.

NUREG/CR-4674 V05. PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS 1986.A STATUS REPORT.

Borehole Plug NUREG/CR-4674 V06: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-5130 BENTONITE BOREHOLE PLUG FLOW TESTING DAMAGE ACCIDENTS:1986.A STATUS REPORT. WITH FIVE WATER TYPES.

Borehole Sealing Advenced Reactor NUREG 1226: DEVELOPMLlT AND UTluzATON OF THE NRC NUREG/CR-5129: EXPERIMENTAL ASSESSMENT OF THE INFLUENCE POLICY STATEMENT ON THE REGULATON OF ADVANCED NU. OF OYNAMic LOADING ON THE PERMEABluTY OF WET AND OF CLEAR POWER PLANTS. DRIED CEMENT BOREHOLE SEALS.

NUREG/CR5131 BENTONITE BOREHOLE PLUG FLOW TESTING Agreement States WITH FIVE W ATER TYPES.

NURE 1311: FUNDING THE NRC TRAINING PROGRAM FOR gg NUREG/CR 5142: OUCTILE TO BRITTLE TOUGHNESS TRANSITON Alpha Emitter CHARACTERIZATON OF A533B STEEL.

NUREG/CR 5067: EARLY AND CONTINUING EFFECTS OF COMBINED CSNI ALPHA AND BETA IRRADIATION OF THE LUNG Phase ll Report NUREG/CP 0075: PROCEEDINGS OF CSNI/NRC WORKSHOP ON Annual Report DUCTILE PIPING FRACTURE MECHANICS.

COMM & MEN NUREG 0975 V06: COMPILATION OF CONTRACT RESEARCH FOR TiONAL PRACTICE FOR PLUGGING. REPAIR AND INSPECTION OF THE MATERIALE ENGINEERING BRANCH.DIVISON OF STEAM GENERATOR TUBING.

ENGINEERING Annut Report For FY 1987.

O*

Atmospheric Diffusion N EGICR 5019: NEUTRON EXPOSURE PARAMETERS FOR THE NUREG/CR 5055. ATMOSPHERIC OlFFUSON FOR CONTROL ROOM METALLURGICA'. TEST SPECIMENS IN THE FIFTH HEAVY-SEC.

HABITABluTY ASSESSMENTS. TION STEEL TECHNOLOGY IRRADIATION SERIES CAPSULES.

B-Factor Technique Cement Borehole Plug NUREG/CR-5044: EST1MATON TECHNIOUES FOR COMMON CAUSE NUREG/CR-5129: EXPERIMENTAL ASSESSMENT OF THE INFLUENCE FAILURE EVENTS. OF DYNAMIC LOADING ON TH5 PERMEABIUTY OF WET AND OF DRIED CEMENT BOREHOLE SEALS.

BWR NUREG 1217 DRFT FC: EVALUAliON OF SAFETY IMPUCATONS OF Cement Permeability CONTROL SYSTEMS !N LWR NUCLEAR M)WER PLANTS.Techrveal NUREG/CR-5129: EXPERIMENTAL ASSESSMENT OF THE INFLUENCE Findings Related To Vrvesolved Safety Issue A-47. Draft Report For OF DYNAMtC LOADING ON THE PERMEABluTY OF WET AND OF NU $076: AN APPROACH TO THE QUANTIFICATION OF SEIS-MIC MARGINS IN NJCLEAR PCNER PLANTS.The Importance Of Charcoal Tray Adsorber Cell BWR Plant Systems And Function. To Seismic Marges- NUREG/CR-4932: CLOSEOUT OF IE BULLETIN 80 03. LOSS OF CHAR.

NUREG/CR 5160. GUIDELNES FC 4 THE USE OF THE EEDB AT THE COAL FROM STANDARD TYPE II,TWO-INCH. TRAY ADSORBER SUBCOMPONENT AND SUBSYS TEM LEVEL Fnal Report. CELLS.

Bentonite Pellet Check Valve NUREG/CR 5130. OENTONITE BOREHOLE PLUG FLOW TESTING NUREG/CR$159: PREDICTON OF CHECK VALVE PERFORMANCE WITH FIVE WATER TYPES AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS.

Beta Emitter Circuit Breaker NUREG/CR.5067; EARLY AND CONTINUlNG EFFECTS OF COMB.NED NUREGICR4665: CLOSEOUT OF IE BULLETIN 83 08 ELECTRl CAL ALPHA AND BETA IRRADIATON OF THE LUNG Phase 11 Report CLRCUIT BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN 27

28 Subject Ind;x USE IN SAFETY RELATED APPUCATIONS OTHER THAN THE RE- Crocked Pipe ACTOR TRIP SYSTEM- NUREG/CR-4082 V06: DEGRADED PIPING PROGRAM PHASE ILSixth Program Report October 1986. September 1987.

CW %m NUREG 0683 S03 DRFT: PROGRAMMATIC ENVIRONMENTAL IMPACT DOE STATEMENT RELATED TO DECONTAMINATON AND DISPOSAL OF NUREG/CR-4735 V03: EVALUATION AND COMPILATION OF DOE RADIOACTIVE WASTES RESULTING FROM MARCH 28.1979 WASTE PACKAGE TEST DATA. B4 annual ReportFebruaryduty 1987.

ACCOENT THREE MILE ISLAND NUCLEAR STATION,0 NIT 2. Docket No. 50-320.(GPU Nuclear, Incorporated) Camping NUREG/CR-5105: RESPONSE MARGINS INVESilGATION OF PIPtNG Cloteout DYNAMIC ANALYSES USING THE INDEPENDENT . SUPPORT NUREG/CR 4665: CLOSEOUT OF IE BULLETIN 8348 ELECTRCAL MOTION METHOD AND PVAC DAMPING.

CIRCUlf BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN USE IN SAFETY RELATED APPLCATONS OTHER THAN THE RE. Decay Heat Removal ACTOR TRIP SYSTEM. NUREG 1032: EVALUATON OF STATION BLACKOUT ACO9ENTS AT NUREG/CR 4932: CLOSEOUT OF IE BULLETIN 80-03 LOSS OF CHAR- NUCLEAR POWER PLANTS.Tectncal Firdngs Related To Unre.

COAL FROM STANDARD TYPE II.TWO INCH, TRAY ADSORBER solved Safety issue A-44 Fnal Report.

CELLS. NUREG/CR 5072: DECAY HEAT REMOVAL USING FEED AND BLEED NUREG/CR-4933: CLOSEOUT OF IE BULLETIN 80-19 FAILURES OF FOR U.S. PRESSURIZED WATER REACTORS.

MERCURY WETTED MATRIX RELAYS IN REACTOR PROTECTIVE SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DEslGNED Decommissioning l BY COMBUSTION ENGINEERING. NUREG 1221:

SUMMARY

. ANALYSIS AND RESPONSE TO PUBUC j COMMENTS ON PROPOSED AMENDMENTS TO 10 CFR PARTS I R /CR 639 V01: NUCLEAR COMPUTERIZED LIBRARY FOR AS- A F CI'llT'IES SESSING REACTOR REUABILITY (NUCLARR). Volume I. Summary De-NUREG/CR 3899' S01: UTILITY FINANCIAL STABluTY AND THE sc@ ton. AVAILABILITY OF FUNDS FOR DECOMMISSONING An Analysis Of intemal And Ertemal Fundmg G/ -514 N AMENTAL ATTRIBUTES OF A PRACTICAL NUREG/CR4315 V09 R1: EVALUATON OF NUCLEAR FACluTY DE.

CONFIGURATON MANAGEMENT PROGRAM FOR NUCtEAR PLANT SS G NEM Sumrnary hus W.Ne We DESIGN CONTROL island Urv12.Radcactrve Waste And Laundry Stupments.

j Containment Decontamination NUREG-0683 S03 DRFT: PROGRAMMATC ENVIRONMENTAL IMPACT l

NUREG/CR 4763. SAFETY-RELATED EQUIPMENT SURVIVAL IN HY. j DROGEN BURNS IN LARGE DRY PWR CONTAINMENT BUllDINGS. STATEMENT RELATED TO DECONTAMINATION AND DISPOSAL OF i NUREG/CR4881: FISSION PRODUCT RELEASE CHARACTERISTICS RADIOACTIVE WASTES RESULTING FROM MARCH 28,1979 INTO CONTAINMENT UNDER DESIGN BASIS AND SEVERE ACCl. ACCIDENT.THREE MILE l' LAND NUCLEAR STATION. UNIT 2. Docket DENT CONDITIONC. No. 50-320 (GPU Nuctear, Incorporated) i NUREG/CR-5106: USER'S GUIDE FOR THE TACT 5 COMPUTER CODE.

Degradation Containment Enytronment NUREG/CR 5159: PRED8CTION OF CHECK VALVE PERFORMANCE NUREG/CR 5038:OPTIMl2ATON OF THE CONTROL OF CONTA%NA- AND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS.

TION AT NUCLEAR POWER PLANTS.

Degraded Piping Containment integrity NUREG/CR-4082 V06: DEGRADED PtPING PROGRAM . PHASE II.Sath NUREG 1273: TECHNICAL FINDINGS AND REGULATORY ANALYSIS Program Report. October 1986. September 1987.

FOR GENERC SAFETY ISSUE 11 E.4 3 "CONTAINMENT INTEGRITY CHECK." Design Control NUREG/CR-5147: FUNDAMENTAL ATTRIBUTES OF A PRACTCAL R R 514 DUCTILE TO BRITTLE TOUGHNESS TRANSITON CHARACTERIZATON OF A533B STEEL SGN NT OL Contamination Control Diesel Generator Reliability NUREG/CR 5078 V01: A REUABluTY PROGRAM FOR EMERGENCY NUREG/CR 5038 OPTIM12ATON OF THE CONTROL OF CONTAMINA-TION AT NUCLEM POWER PLANTS. OlESEL GENERATORS AT NUCLEAR POWER PLANTS Program Structure Contractor urbance NUREG-0975 V06: COMPILATON OF CONTRACT RESEARCH FOR THE MATERIALS ENGINEERING BRANCH. DIVISION OF NUREG/CR-5159- PREDICTON OF CHECK VALVE PERFORMANCE ENGINEERING Annual Report For FY 1987. ^

Contiof Room HatHtablity Dose Radiation NUREG/CR-5055: ATMOSPHERIC DIFFUSION FOR CONTROL ROOM NUREG/CR 5038: OPTIMl2ATON OF THE CONTROL OF CONTAMINA-HABITABluTY ASSESSMENTS. TION AT NUCLEAR POWER PLANTS.

Control System Dynamic Loading NUREG 1218 DAFT FC: REGULATORY ANALYSIS FOR PROPOSED NUREG/CR-5129: EXPERIMENTAL ASSESSMENT OF THE INFLUENCE RESOLUTON OF USI A-4 7. Safety implications Of Control OF DYNAMC LOADING ON THE PERMEABluTY OF WET AND OF Systems Draft Rept For Comment. DRIED CEMENT BOREHOLE SEALS NUREG/CR 5142: DUCTILE TO BRITTLE TOUGHNESS TRANSITION Core Damage CHARACTER 12ATION OF A533B STEEL NUREG 1032 EVALUATION OF STATION BLACKOUT ACCIDENTS AT NUCLEAR POWER PLANTS.Techrwcal Fedings Related To Unre. Dynamic Etrain Aging solved Safety Issue A44 Fnal Report. NUREG/CR 5013. FATlGUE LIFE CHARACTER 12ATION OF SMOOTH NUREG/CR4674 V05- PRECURSORS TO POTENTIAL SEVERE COAE AND NTCHED PIPING STEEL SPECIMENS IN 288 DEGREE C AIR DAMAGE ACCIDENTS 1986.A STATUS REPORT. ENVIRONMENT!

NUREG/CR4674 V06. PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS 1986.A STATUS REPORT. EE80 NUREG/CR 5042 S01: EVALUATON OF EXTERN AL HAZARDS TO NU- NUREG/CR-5160 GUOELINES FOR THE USE OF THE EEDB AT THE CLE AR POWER PLANTS IN THE UNITED STATES Se,struc Hazard. SUB-COMPONENT AND SUBSYSTEM LEVEL Foal Report Cost Analysis EPICOR il NUREG/CR-5160- GUIDEllNES FOR THE USE OF THE EEDB AT THE NUREG/CR 5137: BODEGRADATION TESTING OF TMI 2 EPICOR-ll SU8 COMPONENT AND SUBSYSTEM LEVEL Feal Report. W ASTE FORMS.

Subject Ind;x 29 Elbow Effect Freon-113 Loop NUREG/CR 5159: PREDICTON OF CHECK VALVE PERFORMANCE NUREG/CR-5082: SIMULATON EXPERIMENTS Otv TWO-PHASE NAT -

AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS. URAL CIRCULATON IN A FREON I t3 FLOW VISUAUZATION LOOP.

Enforcement Action Generic Cost Estimate NUREG-0940 V07 N01: ENFORCEMENT ACTONS.SIGNIFICANT AC. NUREG/CR 5138: VAUDATON OF GENERIC COST ESTIMATES FOR-TONS RESOLVED.Quarterty Progress Report, January March 1988. CONSTRUCTION-RELATED ACTIVITIES AT NUCLEAR POWER PLANTS.F nal Report NUREG/CR4864 V01: THERMOOYNAMIC TABLES FOR NUCLEAR Generic Safety issues WASTE ISOLATON. Aqueous Solutaons Database. NUREG 0933 S07: A PRORJTIZATON OF GENERIC SAFETY ISSUES. j NUREG 1273: TECHNICAL FINDINGS AND REGULATORY ANALYSIS '

EnvironmentalImpact Statement FOR GENERIC SAFETY ISSUE II E.4.3, "CONTAINMENT INTEGRITY NUREG-0683 S03 DRFT: PROGRAMMATIC ENVIRONMENTAL IMPACT CHECK." ~l STATEMENT RELATED TO DECONTAMINATION AND DISPOSAL OF  :

RADIOACTIVE WASTES RESULTING FROM MARCH 28,1979 Groundwater i ACCIDENT,THREE MILE ISLANO NUCLEAR STATION. UNIT 2 Docket NUREG-1308: RADCACTIVE MATERIAL IN THE WEST LAKE I NU / 87 1: ONSTRATON OF PERFORMANCE MOO-Equipment Failure EUNG OF A LOW-LEVEL WASTE SHALLOW-LAND BilRIAL SITE.A NUREG 1320- NUCLEAR FUEL CYCLE FACluTY ACCIDENT ANALYSIS Companson Of Predictive Radionucide Transport Modeing Versus HANDBOOK. Field Observations At it.e N:trate Disposal Pit Sde. Chalk River Nuclear Labs.

Equipment Qualification NUREG/CR4728: EOUlPMENT OUALIFICATON RESEARCH TEST OF HEATING 6 A HIGH-RANGE RADIATION MONITOR. NUREG/CR 4777: STEAM OXIDATON OF ZlRCALOY CLADOING !N THE ORNL FISSION PRODUCT RELEASE TESTS.

Equipment Survival NUREG/CR4763. SAFETY-F. ELATED EQUIPMENT SURVIVAL IN HY- HSST OROGEN BURNS IN LARGE DRY PWR CONTAINMENT BUILDINGS. NUREG/CR-5019: NEUTRON EXPOSURE PARAMETERS FOR THE METALLURGICAL TEST SPECIMENS IN THE FIFTH HEAVY SEC-Estimation Technique TON STEEL TECHNOLOGY IRRADtATION SERIES CAPSULES.

NUREG/CR-5044. ESTIVATION TECHNIQUES FOR COMMON CAUSE FAILURE EVENTS. Heat Capacity NUREG/CR-4864 V01: THERMODYNAMIC TABLES FOR NUCLEAR External Hazard WASTE ISOLATION. Aqueous Solutions Database.

NUREG/CR 5042 S01: EVALUATION OF EXTERNAL HAZAROS TO NU-CLEAR POWER PLANTS IN THE UNITED STATES Seismic Hazard Heat Transfer NUREG/CR 5095 V01: THERMODYNAMIC NONEOUILIBRIUM IN POST-FLsw Oscillation CRITICAL-HEAT FLUX BOfuNG IN A ROO BUNDLE.Desenption Of NUREG/CR 5082: SIMULATICN EXPERIMENTS ON TWO-PHASE NAT- Expenments And Sample Results.

URAL CIRCULATION IN A FREON 113 FLOW VISUAUZATON LOOP- NUREG/CR-5095 V02: THERMODYNAMIC NONEQUluBRIUM IN POST-CRITICAL-HEAT FLUX BOLLING IN A ROD BUNOLE. Data For S'.abi-FaHure Evd Iced Ouench Front Tests.

NUREG/CR-5044. ESTIMATON TECHNIQUES FOR COMMON CAUSE NUREG/CR-5095 V03; THERMOOYNAMIC NONEOUluBRIUM IN POST-FAILURE EVENTS- CRITICAL-HEAT FLUX BotLING IN A ROO BUNDLE. Data For Advanc-Quench Front Tests.

I*W NU EG/CR-5095 V04: THERMOOYNAMIC NONEQU1UBRIUM IN POST-NUREG/CR 5013. FATIGUE LIFE CHARACTERIZATON OF SMOOTH CRITICAL HEAT FLUX BOluNG IN A ROD BUNDLE. Data For Retreat-AND NOTCHED PIPING STEEL SPECWENS IN 288 DEGREE C AIR ing Ovench Front Tests.

ENVIRONMENTS.

Heavy Section Steel Technology Fatigue Damage NUREG/CR4219 V04 N2; HEAVY-SECTON STEEL TECHNOLOGY NUREG/CR-5159. PREDIC7 ION OF CHECK VALVE PERFORMANCE PROGRAM Serniannual Progress Report For Apni September 1987.

AND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS.

H6gh Level Nuclear Weste Repository Faun NUREG 1318: TECHNICAL POSITON ON ITEMS AND ACTIVITIES IN NUREG/CR-5123. STUDIES OF THE PATTERN AND AGES OF POST- THE HIGH-LEVEL WASTE GEOLOGIC REPOslTORY PROGRAM METAMORFHlC FAULTS IN THE P;4DMONT OF VIRGINIA AND SUBJECT TO OVAUTY ASSURANCE REQUIREMENTS.

NORTH CAROUNA.

High-Level Waste Feed And-Bleed NUREG/CR4735 V03: EVALUATON AND COMPtLATION OF DOE NUREG/CR 5072: DECAY HEAT REMOVAL USING FEED ANO-BLEED WASTE PACKAGE TEST DATA. Bianrnal Report. February Jufy 1987.

FOR U S. PRESSURIZED WATER REACTORS.

H6gh-Range Radiation Monitor Fission NUREG/CR-4728: EQUIPMENT OUAUF;CATON RESEARCH TEST OF NUREG/CR-4778. PREUM; NARY STUDIES OF THE MORPHOLOGY OF A HIGH-RANGE RADIATON MONITOR.

! THERMAL GRADIENT TUBE DEPOSITS FROM FISSON PRODUCT l

RELEASE EXPERIMENTS Historical Data Summary l NUREG 1214 R03: HISTORICAL DATA SUMM ARY OF THE SYSTEMAT.

l Fission *roduct IC ASSESSMENT OF UCENSEE PERFORMANCE.

NUREG/CR4777: STEAM OXIDATION OF ZlRCALOY CLADOING IN i

THE ORNL FISSON PRODUCT RELEASE TESTS Hydraulic Conductivity NUREG/CR-4881: FISSON PRODUCT RELEASE CHARACTERISTICS NURE(.s/CR 5130: BENTONITE BOREHOLE PLUG FLOW TESTING INTO CONTAINVENT UNDER DESIGN BASIS AND SEVERE ACCl- WITH FIVE WATER ~YPES.

DENT CONOtTONS.

Hydrogen Burn Fracture Mechanics NUREG/CR4763. SAFETY-RELATED EOUIPMENT SURVIVAL IN HY.

NUREG/CP 0075: PROCTEOtNGS OF CSNI/NRC WORKSHOP ON DROGEN BURNS IN LARGE ORY PWR CONTAINVENT BUILDINGS.

DUCTILE PIPING FRACTURE MECHAN!CS NUREG/CR-4082 V06 DEGRADED PtPING PROGRAM PHASE 11Sath IE Bulletin 80 03 Program Report Octecer 1988 September 1987. NUREG/CR 4932: CLOSEOUT OF IE BULLETIN 80-03 LOSS OF CHAR.

NUREG/CR4215 V04 N2- HEAVY SECTION STEEL TECHNOLOGY COAL FROM STANDARD TYPE II.TWO-INCH. TRAY ADSORBER PROGRAM Semiannual Progress Report For Apnt September 1987. CE LLS.

l l

l 30 Subject Index l

l O Sulietin 8019 Licensed Operating Reactors i NUREG/CR-4933; CLOSEOUT OF IE BULLETIN 8019 FAILURES OF NUREG 0020 V12 NO3: UCENSED OPERATING REACTORS STATUS I MERCURY WETTED MATRIX RELAYS IN REACTOR PROTECitVE

SUMMARY

REPORT, Data As Of February 29.1988 (Gray Book I)

SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DESIGNED NUREG 0020 V12 N04: UCENSED OPERATING REACTORS STATUS BY COMBUSTION ENGINEERING.

SUMMARY

REPORT. Data As Of March 31.1988 (Gray Book I)

NUREG4020 V12 N05: UCENSED OPERATING REACTORS STATUS IE Busietin 83 ^8

SUMMARY

REPORT. Data As Of Aprd 30,1988(Gray Book 1)

NUREG/W 4665: CLOSEOUT OF IE BULLETIN 8348 ELECTRICAL CIRCUIT BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN Ucensee Event Report USE IN SAFETY RELATED APPLICATONS OTHER THAN THE RE' NUREG/CR-2000 V07 N3: UCENSEE EVENT REPORT (LER)

ACTOR TRIP SYSTEM. COMPILATON For Month Of March 1988.

NUREG/CR 2000 V07 N4: UCENSEE EVENT REPORT (LER)

RE /CR 5067: EARLY AND CONTINUtNG EFFECTS OF COMBINED NU EG/ V07 N5 ALPHA AND BETA IRRADIATON OF THE LUNG Phase il Report EN E EVENT REPORT (LER)

COMPILATION For Month Of May 1988.

Inspection AU . Quart R Ja '"$

c NUR 1 4 H ST ICAL ATA THE SYSTEMAT.

NUREG/CR 51 RFORMANCE-BASED INSPECTONS.

Ught Water Reactor installation Cost NUREG-1217 DRFT FC: EVALUATON OF SAFETY IMPLICATIONS OF NUREG/CR-5138: VAUDATION OF GENERO COST ESTIMATES FOR CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTSTechncal CONSTRUCTON-RELATED ACTMTIES AT NUCLEAR POWER Findings Related To Unresolved Safety issue A-47. Draft Report For PLANTS Final Report Comtrent.

NUREG 1218 DRFT FC: REGULATORY ANALYSIS FOR PROPOSED Intergranular Stress Corrosion Cracking RESOLUTION OF USl A 47. Safety Impicatons Of Control NUREG/CR 5150: STEAM GENERATOR OPERATING Systems Draft Rept For Cornment.

EXPERIENCE Update For 1984 1986. NUREG/CR-4674 V05: PRECURSORS TO POTENTIAL SEVERE CORE D/ MAGE ACCIDENTS:1982.A STATUS REPORT.

N E 072 R PUBLC INFORMATON CIRCULAR FOR SHIP- NUREG/CR 4674 V06: PA2 CURSORS TO POTENTIAL SEVERE CORE MENTS OF IRRADIATED REACTOR FUEL DAMAGE ACCIDENT 01986.A STATUS HEPORT.

NUREG/CR-4881: FISSION PRODUCT RELEASE CHARACTERISTICS frradianon INTO CONTAINMENT UNDER DESIGN BASIS AND SEVERE ACCI-NUREG/CR 5019; NEUTRON EXPOSURE PARAMETERS FOR THE CENT CONDITIONS.

METALLURGCAL TEST SPECIMENS IN THE FIFTH HEAVY-SEC-TON STEEL TECHNOLOGY IRRADIATION SERIES CAPSULES. Loss-Of Coolant Accident NUREG/CR 5067; EARLY AND CONTINUING EFFECTS OF COMBINED NUREG/CR-4728: EQUIPMENT OUAUFICATON RESEARCH TEST OF ALPHA AND BETA IRRADIATON OF THE LUNG Phase 11 Report A HIGH RANGE RADIATON MONITOR.

LER Low Level Weste NUREG/CR-2000 V07 N3: UCENSEE EVENT REPORT (LF.R) NUREG/CR-4879 V01: DEMONSTRATION OF PERFORMANCE MOD-COMPILATION For Month Of March 1988. EUNG OF A LOW LEVEL WASTE SHALLOW LAND BURIAL Si?E.A NUREG/CR 2000 V07 N4: UCENSEE EVENT REPOh. '.t!R) Companson Of Predictrve Radonuclide Transport Modehng Versus NU G V07 5 CEN E EVENT REPORT (LER) ,

COMPILATION For Month Of May 1988-NUREG/CR-5137: BIODEGRADATON TESilNG OF TMI-2 EPICOR il LOCA WASTE FORMS.

l NUREG/CR 4728. EOutPMENT OUALIFCATON RESEARCH TEST OF A HIGH-RANGE RADIATON MONITOR.

N E /CR 5019' NEUTRON EXPOSURE PARAMETERS FOR THE LWR METALLURGCAL TEST SPECIMENS IN THE FIFTH HEAVY SEC-NUREG 1217 DRFT FC: EVALUATION OF SAFETY IMPUCATIONS OF TON STEEL TECHNOLOGY IRRADIATION SERIES CAPSULES.

CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS Techncal Ferengs Related To Unresolved Safety issue A-47. Draft Report For Microcartteuske Network

, Comment. NUREG CR-5045: KANSAS-NEBRASAA SEISMCITY STUDIES USING l NUREG 1218 DRFT FC: REGULATORY ANALYSIS FOR PROPOSED THE KANSAS-NEBRASKA MCROEARTHOUAKE NETWORK Final l RESOLUTON OF USl A-4 7. Safety Impications Of Control Repart Systems Draft Rept For Comment NUREG/CR-4674 V05: PRECURSORS TO POTENTIAL SEVERE CORE Mit gauon DAMAGE ACCIDENTS 1986.A STATUS REPORT. NUREG 1318: TECHNICAL POSITON ON ITEMS AND ACTIVITIES IN NUREG/CR-4674 V06: PRECURSORS TO POTENTIAL SF'.ERE CORE THE HIGH-LEVEL WASTE GEOLOGIC REPOSITORY PROGRAM DAMAGE ACCIDENTS 1988.A STATUS REPORT- SUBJECT TO QUAUTY ASSURANCE REQUtREMENTS.

NUREG/CR 4881: FISSION PROOUCT RELEASE CHARACTERISTICS INTO CONTAINMENT UNDER DESIGN BAS!S AND SEVERE ACCI- Motor Operated Valve DENT CONDITIONS. NUREG 1296: THERMAL OVERLOAD PROTECTON FOR iLECTRC p MOTORS ON SAFETY RELATED MOTOR OPERATED VALVES . GE.

NERIC ISSUE II.E 6.1-l NUREG/CR-5138 VAUDATON OF GENERC COST ESTIMATES FOR CONSTRUCTON-RELATED ACTMilES AT NUCLEAR POWER NUCLARR PLANTS. Final Report NUREG/CR 4639 V01: NUCLEAR COMPUTERIZED UBRARY FOR AS-Legal Issuances SESSING REACTOR REllAB'UTY (NUCLARR). Volume I. Summary De-NUREG4750 V26101: INDEXES TO NUCLEAR REGULATORY COM. senption.

MISSON ISSUANCES Jt#y September 1987.

NUREG-0750 V26102. INDEXES TO NUCLEAR REGULATORY COM. Natural Circulabon M!SSON ISSUANCES. Jt#y-December 1987. NUREG/CR-5082: SrMULATION EXPERIMENTS ON TWO. PHASE NAT.

NUREG4750 V27101: INDEXES TO NUCLEAR REGULATORY CCM. URAL CIRCULATION IN A FREON 113 FLOW VISUAUZATON LOOP.

MISSON ISSUANCES January March 1988 NUREG-0750 V27 NO2 NUCLEAR R2GULATORY COMMISSON IS. Nephrotoxicity SUANCES FOR FEBRUARY 1988. Paoes 41255 NUREG/CP4093. PROCEEDINGS OF THE MEETING ON ULTRASEN-NUREG4750 V27 NO3. NUCLEAR REGULATORY COMViSSON IS. SITIVE TECHNIOUES FOR MEASUREMENT OF URANtVM IN BIO-SUANCES FOR M ARCH 1988. Pages 257 334. LOGICAL SAMPLES AND THE NEPHROTOXCITY OF URAN!UM.

Subject index 31 Neutron Exposure Parameter Pipe NUREG/CR 5019: NEUTRON EXPOSURE PARAMETERS FOR THE NUREG/CP 0075: PROCEEDINGS OF CSNI/NRC WORKSHOP ON METALLURGICAL TEST SPECIMENS IN THE FIFTH HEAVY SEC- DUCTILE PLPtNG FRACTURE MECHANICS.

TION STEEL TECHNOLOGY IRRADIATION SERIES CAPSULES.

Nuclear Accident Risk "8 NUREG/CR 50lt METHODOLOGY FOR UNCERTAtNTY ESTIMATON NUREG/CR 5105. RESPONSE MARGINS INVESTIGATON OF PIPING IN NUREG 1150 (DRAFT) Conclus ons Of

• Rewew Panet.

DYNAMC ANALYSES USING THE INDEPENDENT SUPPORT MOTION METHOD AND PVRC DAMPING.

Nuclear Fuel Cycle NUREG-1320: NUCLEAR FUEL CYC".2 FACIUTY ACCIDENT ANALYSIS Piping Steel HANDBOOK. NUREG/CR 5013: FATIGUE LIFE CHARACTERIZATON OF SMOOTH ANO NOTCHED PIPING STEEL SPECIMENS IN 288 DEGREE C AIR Nuclear Meterial Managment ENVIRONMENTS.

NUREG/CR-4605: TRAINING MANUAL ON STATISTICAL METHODS FOR NUCLEAR MATERIAL MANAGEMENT. Plugging NUREG/CR 5150: STEAM GENERATOR OPERATING R G 23 S FETY EVALUATION REPORT ON TENNESSEE ERENCEWe 6 NM VALLEY AUTHORITY. Sequoyah Nuclear Perfcrmance Plan.

Policy Statement Nucles' Safety Research NUREG 1226; DEVELOPMENT AND UTIUZATON OF THE NRC NUREG-1325: DISPOSITION OF RECOMMENDATIONS OF THE NA. POLCY STATEMENT ON THE REGULATION OF ADVANCED NU.

TONAL RESEARCH COUNCIL IN THE REPORT *REVITAUZlNG NU. CLEAR POWER PLANTS.

CLEAR SAFETY RESERCH."

Nuclear Waste toolation NUREG/CR-5123: STUDIES OF THE PATTERN AND AGES OF POST.

NUREG/CR-4864 VOI: THERMODYNAMC TABLES FOR NUCLEAR METAMORPHIC FAULTS IN THE PIEDMONT OF VIRGINIA AND WASTE ISOLATON. Aqueous Solutions Database. NORTH CAROUNA-Occupational Radiation Power Spect al Density NUREG-0713 V07: OCCUPATONAL RADIATON EXPOSURE AT COM-NUREG/CR 3509: POWER SPECTRAL DENSITY FUNCTIONS COM-MERCIAL NUCLEAR POWER REACTORS AND OTHER FACluTIES 1985 Eighteenth Annual Repet PATIBLE WITH NRC REoVLATORY GUCE 1.60 RESPONSE SPEC.

TRA.

Operational Event NUREG/CR-4674 V05: PRECURSORS TO POTENTIAL SEVERE CORE Pressure Yessel DAMAGE ACCIDENTS 1986.A STATUS REPORT. NUREG/CR-4219 V04 N2- HEAVY SECTON STEEL TECHNOLOGY NUREG/CR 4674 V06: PRECURSORS TO POTENTIAL SEVERE CORE PROGRAM.Serniannual Progress Report For Apni-September 1987 DAMAGE ACCCENTS.1986.A STATUS REPORT.

Pressurized Water Reactor PRA NUREG/CR-5016: COMPENDIUM AND COMPAPISON OF INTERNA.

NUREG/CR-4836. APPROACHES TO UNCERTAINTY ANALYSTS IN TIONAL PRACOCE FOR PLUGGING. REPAIR AND INSPECTION OF PROBABluSTIC RISK ASSESSMENT STEAM GENERATOR TU8ING NUREG/CR-5076: AN APPROACH TO THE QUANTIFICATION OF SEIS-MC MARGINS IN NUCLEAR POWER PLANTS.The importance Of NUREG 1217 DRFT FC: EVALUATON OF SAFETY IMPLICATONS OF BWR Plant Systems And Functions To Se<smic Margins. CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS. Technical F s Rm To Unrew Sakty issw A47 Dan Reput For PRISIM Comment NUREG/CR-5021 V01: USER S GUIDE FOR PRISIM ARKANSAS NU- NUREG/CR 4763: SAFETY-RELATED EQUIPMENT SURVIVAL IN HY-CLEAR ONE - UNIT 1. Volume 1, Program For Inspectors DROGEN BURNS IN LARGE DRY PWR CONTAINMENT BUILDINGS.

NUREG/CR 5021 V02- USER'S GUIDE FOR PAISIM ARKANSAS NU. NUREG/CR-5013. FATIGUE UFE CHARACTER 12ATON OF SMOOTH CLEAR ONE - UNfT 1 Volume 2. Program For Regulators. AND NOTCHED PtPING STEEL SPECIMENS IN 288 DEGREE C AIR ENVIRONMENTS.

PVRC NUREG/CR 5015: IMPROVED REUABluTY OF RESIDUAL HEAT RE-NUREG/CR-5105: RESPONSE MARGINS INVESTIGATON OF PIPING MOVAL CAPABluTY IN PWAS AS RELATED TO RESOLUTION OF DYNAMC ANALYSES USING THE INDEPENDENT SUPPORT GENERC ISSUE 99.

MOTION METHOD AND PVRC DAMPING.

NUREG/CR 5072- DECAY HEAT REMOVAL USING FEED ANDLBLEED PWR FOR U.S. PRESSURIZED WATER REACTORS.

NUREG/CR 5150: STEAM GENERATOR OPERATING NUREG 1217 DRFT FC: EVALUATON OF SAFETY IMPUCATONS OF CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS. Technical Related To Unresobed Safety issue A-47. Draft Report For NUREG 1 : DE E THE USE OF THE EEDB AT THE SUB-COMPONENT AND SUBSYSTEM LEVELFeat Report NUREG/CR-4763: SAFETY RELATED EOUiPMENT SURVIVAL IN HY-DROGEN BURNS IN LARGE DRY PWR CONTAINMENT BUILD 4NGS. Priorittaation NUREG/CR 5013: FATlGUE UFE CHARACTERIZATION OF SMOOTH NUREG 0933 S07: A PRORITIZATION OF GENERC SAFETY ISSUES.

AND NOTCHED PIPING STEEL SPECIMENS IN 288 DEGREE C AIR .

ENVIRONMENTS Probabilistic Risk Analysis NUREG/CR 5015: IMPROVED REUABILITY OF RESIDUAL HEAT RE- NUPEG/CR 5076: AN APPROACH TO THE QUANTIFICATION OF SEIS-MOVAL CAPABluTY IN PWRS AS RELATED TO RESOLUTON OF MC MARGINS IN NUCLEAR POWER PLANTS.The importance Of GENERIC LSSUE 99. BWR Plant Systems And Functions To Sersmic Margens.

NUREG/CR 5072: DECAY HEAT REMOVAL USJNG FEED AND-BLEED FOR U S. PRESSURIZED WATER REACTORS Probabilistic Risk Assessment NUREG/CR 5150. STEAM GENERATOR OPERATING EXPERIENCE Update For 1984 1986 NUREG/CR-4836: APPROACHES TO UNCERTAINTY ANALYSIS IN PROBADIUSTO RISK ASSESSMENT l NUREG/CR 5160' GUCEUNES FOR THE USE OF THE EEDB AT THE NUREG/CR 5021 VOI: USER S GUCE FOR PRISiM ARKANSAS NU-SUB COMPONENT AND SUBSYSTEM LEVEL Final Rem CLEAR ONE UNIT 1. Volume 1. Program For inspectors.

Peer Review Panel NUREG/CR 5021 V02: USER'S GUCE FOR PRIS M ARKANSAS NU-NUREG/CR-5113: FINDINGS OF THE PEER REvtEW PANEL ON THE CLEAR ONE UNIT 1. Volume 2. Pro 0 ram For Regulators.

DRAFT REACTOR RISK REFERENCE DOCUMENT.NUREG 1150.

OW Performance History NUREG 1318: TECHNCAL POSITON ON ITEMS AND ACTIVITIES IN NUREG 1214 R03. HISTORCAL DATA

SUMMARY

OF THE SYSTEMAT- THE NfGH-LEVEL WASTE GEOLOGC REPOSITORY PROGRAM C ASSESSMENT OF UCENSEE PERFORMANCE SUBJECT TO QUALITY ASSURANCE REQUIREMENTS,

I 32 Subject index Quality Assurance Regulatory Analysie NUREG 1318: TECHNICAL POSITON ON ITEMS AND ACTIVITIES IN NUREG-1218 DRFT FC: REGULATORY ANALYSIS FOR PROPOSED "

THE HIGH-LEVEL WASTE GEOLOGIC REPOSITORY PROGRAM RESOLUTON OF USl A 47. Safety irnplacabons Of Control SUBJECT TO QUAUTY ASSURANCE REQUIREMENTS. Systems Draft Rept For Comment NUREG/CR-5151: PERFORMANCE BASED INSPECTONS.

Regulatory And Technical Report

• • 1. • "** 9'** NUREG 0304 V13 N01: REGULATORY AND TECHNICAL REPORTS NUREG 1306: NRC SAFETY SIGNIFICANCE ASSESSMENT TEAM (ABSTRACT INDEX JOURNAL). Compelation For Fast Quarter REPORT ON ALLEGATONS RELATED TO THE SOUTH TEXAS 1988 January March.

PROJECT, UNITS 1 & 2.

Relay REIRS NUREG4713 V07: OCCUPATIONAL RAOtATON EXPOSURE AT COM. NUREG/CR49.0: CLOSEOUT OF IE BULLETIN 80-19 FAILURES OF MERCURY. WETTED MATRIX RELAYS IN REACTOR PROTECTIVE MERCIAL NUCLEAR POWER REACTORS AND OTHER FACluTIES 1985 Eighteenth Annual Report. SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DESIGNED BY COMBUSTON ENGINEERING.

Radiation Dooe NUREG/CR 5106: USER'S GUlOE FOR THE TACT 5 COMPUTER CODE. Report To Congress NUREG4090 V1G NO3: REPORT TO CONGRESS ON ABNORMAL Redletlon Monitoring Network OCCURRENCES. July September 1987.

NUREG-0837 V08 N01: NRC TLD DIRECT RADIATION MONITUO NUREG-0090 V10 N04: REPORT TO CONGRESS ON ABNORMAL NETWORK. Progress Report, January-March 1988. OCCURRENCES. October-December 1987.

Radletion Protection Repository Seeling NUREG/CA-5038. OPTIMIZATION OF THE CONTROL OF CONTAMINA* NUREG/CR 5129: EXPERIMENTAL ASSESSMENT OF THE INFLUENCE TON AT NUCLEAR POWER PLANTS. OF DYNAMIC LOADING ON THE PERMEABluTY OF WET AND OF DRIED CEMENT BOREHOLE SEALS.

Radioactive Material NUREG/CR 5130: BENTONITE BOREHOLE PLUG FLOW TESTING NUREG 1308. RADIOACTIVE MATERIAL IN THE WEST LAKE WITH FIVE WATFR TYPES.

LANDFILLSummary RW Red 6oactive Weste Research NUREG-0683 S03 DRFT; PROGRAVMATO ENVIRONMENTAL IMPACT NUREG-0975 V06: 00MPILATON OF CONTRACT RESEARCH FOR STATEMENT RELATED TO DECONTAMiNATON AND DISPOSAL OF THE MATERIALS ENGINcERING BRANCH,OrVISON OF RADCACTIVE WASTES RESULTING FROM MARCH 28,1979 ENGINEER lNG.A'inual Report For FY 1987.

ACCIDENT.THREE MILE ISLAND NUCLEAR STATON. UNIT 2. Docket No. 50-320 (GPU Nuclear. incorporated) Residual Heat Rernoval NUREG-1308-. RADCACTIVE MATERIAL IN THE WEST LAKE NUREG/CR 5015: IMPROVED REUABIUTY OF RESOUAL HEAT RE-LANDFILLSummary Report. MOVAL CAPAB:UTY IN PWRS AS RELATED TO RESOLUTON OF NUREG/CR4315 V09 R1: EVALUATON OF NUCLEAR FACILITY DE- GENERIC ISSUE 99.

COMMISSIONING PROJECTS. Sumrnary Status Report.Three Mile Island Orvt 2.Radioactwe Weste And Laundry Shipments. Response Spectral NUREG/CR 3509: POWER SPECTRAL DENSITY FUNCTIONS COM-UR -4 FISSON PRODUCT RELEASE CHARACTERISTICS INTO CONTAINMENT UNDER DESIGN BASIS AND SEVE9E ACCI-DENT CONDITIONS Rod Bundle Rad 6onuc5de Tronoport Modeling NUREG/CR 5095 V01: THERMOOiNAMO NONEOUlVBRIUM IN POST.

CRITOAL-HEAT FLUX BOluNG IN A ROD BUNDLE.Desenptor **

NUREG/CR 4879 V01: DEMONSTRATION OF PERFORMANCE W Experiments And Sample Results.

EUNG OF A LOW-LEVEL WASTE SHALLOW LAND BURIAL SITL A Companson Of Predictive Radionuchde Transport Modehng Versus NUREG/CR-5095 V02: THERMODYNAMIC NONEQUILtBRlVM IN POST-Feld Observatons At The N4 rate Disposal Pit S te, Chalk River Nuclear CRITICAL HEAT FLUX BOluNG IN A ROD BUNDLE Data For Stat >

Labs. kred Quench Front Tests.

NUREG/CR-5095 V03: THERMODYNAMC NONEOUILfBRIUM IN POST-Reactor Core CRITCAL-HEAT FLUX BOluNG IN A ROD BUNDLE. Data For Advanc-NUREG/CR 5015: IMPROVED REUABIUTY Of RESOUAL HEAT RE. ing Quench Front Tests.

MOVAL CAPABlUTY IN PWRS AS RELATED TO RESOLUTION OF NOREG/CR-5095 V04: THERMODYNAMIC NONEOUlUBRIUM IN POST-GENERC ISSUE 99 CRITICAL-HEAT FLUX BOluNG IN A ROD BUNDLE Data For Retreat-NUREG/CR-5106: USER'S GUIDE FOR THE TACT 5 COMPUTER CODE. Ing Quench Front Tests Reactor Protective System SALP NUREGiCR4933: CLOSEOUT OF IE BULLETIN 8019 FAILURES OF NUREG-1214 803. HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT-MERCURY WETTED MATRIX RELAYS IN REACTOR PROTECTIVE IC ASSESSMENT OF UCENSEE PERFORMANCE SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DESIGNED BY COMBUSTION ENGINEERING.

Safety Evaluation Report NUREG 1002 S06: SAFETY EVALUATON REPORT RELATED TO THE Reactor Risk OPERATION OF BRACWOOO STATON. UNITS 1 AND 2. Docket Nos.

NUREG/CR-5113. FLNDiNGS OF THE PEER REVIEW PANEL ON THE 50-456 Arid 50457.(Common *ealth Eve Company) 1 DRAFT REACTOR RISK REFERENCE DOCUMENT,NUREG 1150.

NUREG 1232 V02: SAFETY EVALUATON REPORT ON TENNESSEE Reactor Safety Study VALLEY AUTHORITY. Sequoyah Nr clear Performance Plan.

NUREG 1283. SAFETY EVALUATION REPORT RELATED TO THE RE-NUREG/CR4836 APPROACHES TO UNCERTAINTY ANALYSIS IN PROBABiUSTO RISK ASSESSMENT. NEWAL OF THE OPERATING U(ENSE FOR THE RESEARCH REAC-TOR AT PURDUE UNIVERSITY.

Reactor Trip System NUREG /CR4665: CLOSEOUT OF lE BULLETIN 8348 ELECTRICAL Safety Coal CIRCULI BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN NUREG 1226: DEVELOPMENT AND UTluZATON OF THE NRC USE IN SAFETY RELATED APPUCATONS OTHER THAN THE RE. POUCY STATEVENT ON 'HE REGULATON OF ADVANCED NU-ACTOR TRIP SYSTEM CLEAR POWER PLANTS Regulation Safety Research NUREG 1266 V02: NRC SAFETY RESEARCH IN SUPPORT OF RiGU- NLREG-1266 V02: NRC SAFETY RESEARCH IN SUPPORT OF REGU-LATON 1987. LATON 1987.

Subject Index 33 Safety Research Program Steam Generator Tubing NUREG 1325: OlSPOSITON OF RECOMMENDATONS OF THE NA- NUREG/CR 5016: COMPENDlUM AND COMPARISON OF INTERNA-TIONAL RESEARCH COUNCIL IN THE REPORT *REVITAUZING NU- TIONAL PRACTICE FOR PLUGGING. REPAIR AND INSPECTON OF CLEAR SAFETY RESERCH." STEAM GENERATOR TUBING.

Safety S9nificance Assessment Team Steam Line Break NUREG 1306: NRC SAFETY SIGNIFICANCE ASSESSMENT TEAM NUREG/CR-4971: RESULTS OF SEMISCALE MOO 2C FEEDWATER REPORT ON ALLEGATIONS RELATED TO THE SOUTH TEXAS AND STEAM LINE BREAK (S FS) EXPERIMENT SERIES Main Steam PROJECT,0 NITS 1 & 2. L,no BreA Acedent Expenments.

Safety System Steam Oxidation NUREG/CR-5147: FUMAMENTAL ATTRIBUTES OF A PRACTICAL NUREG/CR-4777: STEAM OXIDATION OF ZlRCALOY CLADDING IN CONFIGURATON MANAGEMENT PROGRAM FOR NUCLEAR PLANT THE ORNL FISSION PRODUCT RELEASE TESTS.

DESIGN CONTROL Se6emic Structuralintegrtty NUREG/CR 5123: STUDIES OF THE PATTERN AND AGES OF POST- NUREG/CR 4219 V04 N2: HEAVY-SECTION STEEL TECHNOLOGY METAMORPHIC FAULTS IN THE PIEDMONT OF VIRGINIA AND PROGRAM Semiannual Progress Report Fot April-September 1987

" ^' Systematic Assosoment Seismic Design Crtteria NUREG 1214 R03: HISTORCAL DATA

SUMMARY

OF THE SYSTEMAT.

NURFG 1233 ORFT FC: REGULATORY ANALYSIS FOR USI A-40, C ASSESSMENT OF LICENSEE PERFORMANCE.

"SEISMC DESIGN CRITERIA." Draft Report For Comment TACT 5 Seismic Hazard NUREG/CR-5106: USER'S GUlOE FOR THE TACT 5 COMPUTER CODE.

NUREG/CR 5042 S01: EVALUATON OF EXTERNAL HAZAROS TO NU-l CLEAR POWER PLANTS IN THE UNITED STATES Seismec Hazard.

g Seismic Margin NETWORK Progress Report, October-December 1987. )

NUREG/C45076: AN APPROACH TO THE QUANTIFCATION OF SEIS- NUREG-0837 V08 N01: NRC TLD DIRECT RADIATON MONITORlNG MIC MARGINS IN NUCLEAR POWER PLANTS.The importance Of NETWORK. Progress Popo 1, Janua/y-March 1988.

BWR Plant Systems And Functions To Seismic Margins Tectonics Seismicity NUREG/C45045. KANSAS NEBRASKA SEISMCITY STUOFS USING NUREG/CR-5045: KANSAS NEBRASKA SEISMCITY STUDIES USING THE KANSAS-NEBRASKA MCROEARTHOUAKE NETWORK. Final THE KANSAS-NEBRASKA MCROEARTHOUAKE NETWORK. Final Report Report NUREG/CR-5123: STUDIES OF THE PATTERN AND AGES OF POST-Semiscale Mod-2C METAMORPHIC FAULTS IN Tr4E PIEDMONT OF VIRGINIA AND NUOEG/C44971: RESULTS OF SEMISCALE MOD-PC FEEDWATER NORTH M IR AND STEAM .INE BREAK (S FS) EXPPIMENT SERIES Main Steam Thermal Grodient Tube Une Break Accdent Expenments NUREG/CR-4778: PREUMINARY STUDIES OF THE MORNOLOGY OF Severe Accident THERMAL GRADIENT TUBE DEPOSITS FROM FISSION PROOUCT NUREG 1226: DEVELOPMENT AND UTIUZATION OF THE NRC RELEASE EXPERIMENTS.

L TEM N THE AEGULATON CF ADVANCED NU- Thermal Overload Protection NUREG/CR-4881: FiSSON PRODUCT RELEASF CHARACTERISTICS NUREG 1296: THERMAL OVERLOAD PROTECTON FOR ELECTRIC INTO CONTAINMENT UNDER DESIGN BAS!S AND SEVERE ACCl- MOTORS ON SAFETY-RELATED MOTOR OPERATED VALVES

• GE- t DENT CONDITONS. NERIC ISSUE 11 E.61. f NUREG/CR-5042 S01: EVALUATION OF EXTERNAL HAZARDS TO NU.

Th CLEAR POWER PLANTS IN THE UNITED STATES.Seesmc Hazard.

N RE / - 5V THERMOOYN AMC NONEQUlUBRIUM IN POST.

Severe Accident Risk CRITICAL-HEAT FLUX BOILING IN A ROO BUNDLE Description Of NUREG/C45000- METHODOLOGY FOR UNCERTAINTY ESTIMATON Expenments And Sample Results IN NUREG-1150 CRAFT)Concluses Of A Review Panet. NUREG/CR-5095 YO2: THERMOOYNAMIC NONEOUILIBRIUM IN POST-CRITICAL HEAT-FLUX BOluNG IN A ROO BUNDLE.0ata For Stabb Source Term lued Quench Front Tests.

NUREG 1320- NUCLEAR FUEL CYCLE FACluTY ACCCENT ANALYSIS NUREG/CR-5095 V03: THERMODYNAMC NONEQUlUBRIUM IN POST-HANDBOOK. CRITCAL HEAT FLUX BOILING IN A ROO BUNDLE.0ata For Advanc.

ing Quench Front Tests.

Spent Fuel Shipment Route NUREG/CR 5095 V04: THERMOOYNAMC NONEOUluBRIUM IN POST-NUREG 0725 R06: PUBLIC INFORM ATION CIRCULAR FOR SHIP. CRITICAL-HEAT FLUX BOlUNG IN A ROO BUNDLE. Data For Retreat.

MENTS OF 1RRADtATED REACTOR FUEL ing Quench Front Tests.

Spent Fuel Storage Thermal Hydraulles NUREG-1320: NUCLEAR FUEL CYCLE FACILITY ACCCENT ANALYSIS NUREG/CR 4971: RESULTS OF SEMtSCALE -CO 2C FEEDWATER HANOBOOK.

AND STEAM UNE BREAK (S FS) EXPER' MENT SERIES Main Steam Station Blackout Line Break Accident Expenments.

NUREG-1032. EVALUATON OF STATCN BLACKOUT ACCCENTS AT Thermodynamic NUCLEAR POWER PLANTS. Technical Fnings Related To Unre.

NUREG/CR 4864 V01: THERMOOYNAMC TABLES FOR NUCLEAR NV 1 RGt T Y AC ANAlYS!S FOR THE RESOLU- ^8T N REG /C 5 0: 00 O EQUlUBRlVM IN POST-NURE / 4 78 A IAB i A E ENC) CRITICAL-HEAT-FLUX BotuNG IN A ROD BUNDLE Oeservan of L GENERATORS AT NUCLEAR POWER PLANTS Program NVQQjo95 V TE NAMIC NONEQUluBRIUM IN POST-CRITICAL HEAT FLUX BOIUNG IN A ROD BUNDLE. Data For Stets-Statistical Method bred Quench Front Tests.

NUREG/CR 4605. TRAINING MANUAL ON STATISTICAL METHOOS NUREG/CR 5095 V03. TRAMOOYNAMC NONEQUlUBRlVM IN POST-FOR NUCLEAR MATERIAL MANAGEMENT. CRITICAL HEAT-FLt i 80tUNG IN A ROO BUNOLE Data For AcNanc-ing Quench Front TWs.

Steam Generator NUREG/CR 5095 V04. '.NERMOOYNAMC NONEOUlUBRit,M IN POST.

NUREG/CR5150 STEAM GENERATOR OPERATING CRITICAL HEAT FLUX BOluNG IN A ROO BUNDLE Data For Retreat-EXPERIENCE Upda'e For 1984 1986. ing Quench Front Tests.

4

34 Subject Index Thermoluminescent NUREG 1109. REGULATORY /8ACKFIT ANALYSIS FOR THE RESOLU.

NUREG 0837 V07 N04: NRC TLD DIRECT RADIATION MONITORING TION OF UNRESOLVED SAFETY ISSUE A44. STATION BLACKOUT.

NETWORK Progre,s Report. October-December 1987.

Thermoluminescent Dosimeter NU'h.? 1218 DAFT FC: RE3ULATORY ANALYSIS FOR PROPOSED NUREG4837 V08 N01: NRC TLD DIRECT RADV ' 'W MONITORING RESOLUTON OF USI A4 7. Safety Imphcatons Of Control NETWORK Progress Report. Juuary March 198( Systems. Draft Rept For Comment Through Wall Crack Uncertainty Estination NUREG/CP4075: PROCEEDINGS OF CSNI/NRC WORKSHOP ON NUREG/CR5000: METHODOLOGY FOR UNCERTAINTY ESilMATION DUCTILE PIPING FRACTURE MECHANICS- IN NUREG 1150 (DRAFT) Conclusions Of A Revurw Panel, Title List Uranium Toxicity NUREG4540 V10 N02: TITLE LIST OF DOCUMENTS MADE PUBLICLY NUREG/CP4093. PROCEEDINGS OF THE MEETING ON ULTRASEN-SITIVE TECHNIQUES FOR MEASUREMENT OF URANIUM IN BIO-NURE O V1 3? Tike T OF DOCUMENTS MADE PUBLICLY LOGICAL SAMPLES AND THE NEPHROTOXICITY OF URANIUM.

AVAILABLE. March 1-31,1988.

NUREG-0540 V10 N04. TITLE LIST OF DOCUMENTS MADE PUBLICLY Value-Impact Analysis AVAILABLE' Apnl 1 M'1988-NUREG/CR 5138 VAllOATION OF GENERIC COST ESTIMATES FOR Train 6ng Program CONSTRUCTION RELATED ACTivtilES AT NUCLEAR POWER NUREG i311: FUNDING THE NRC TRAINING PROGRAM FOR PLANTS Fenal Report.

STATES.

Ventilati m Sr stem Two-Phase Flow NUREG/CR-4932: CLOSEOUT OF IE BULLETIN 80-03 LOSS OF CHAR.

NUREG/CR 5082: StMULATION EXPERlMENTS ON TWO PHASE NAT. COAL FROM STANDARD TYPE II.TWO-INCH, TRAY ADSORBER URAL CIRCULATION IN A FREON-113 FLOW VISUALIZATON LOOP. CELLS.

USl A-40 Waste Form NUREG 1233 DAFT FC: REGULATORY ANALYSin FOR USl A-40, NUREG/CR 5137: BODEGRADATON TESTING OF TMI.2 EPICOR-il "SEISMIC DESIGN CRITERIA " DraN Report For Cev. ment. WASTE FORMS.

NUREG R3509 POWER SPECTRAL DENSITY FUNCTIONS COM-PATIRLE WITH NRC REGULATORY GUIDE 160 RESPONSE SPEC. Waste Package TRA NUREG/CR-4735 V03. EVALUATON AND COMPILATION OF DOE WASTE PACKAGE TEST DATA B.annusi Report February Jufy 1987.

NUREG 1032: EVALUATON OF STATON BLACKOUT ACCIDENTS AT Zircaloy Cladding NUCLEAR POWER PLANTS. Technical Findrngs Related To Unre. NUREG/CR 4777: STEAM OUDATON OF Z'ACALOY CLADDING IN solved Safety issue A-44 Foal Report THE ORNL FISSION PRODUCT RELEASE TESTS 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 followed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

ADYlSORY COYMITTEE(S) DIVISION OF INLAISTRIAL & MEDCAL NUCLEN< SAFETY (POST ACRS ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 870729) j NUREG 1125 V09. A COMPILATON OF REPORTS OF THE ADVISO- NUREG 17 8: RADIOACTIVE MATERIAL IN THE WEST LAKE 1 RY COMMITTEE ON REACTOR SAFEGUARDS.1987 Annual. LANDFILLSummary Report.

OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) 33 i REGION 1. OFC OF THE DIRECTOR '

NUREG4837 YO7 N04: NRC TLD DIRECT RADIATION MONITORING DIVISON OF HIGH l'EVEL WASTE MANAGEMENT (POST 870413)

NUREG-1318: TECHNCAL POSITION ON ITEMS AND ACTIVITIES IN NURE 1: N T E TIO MONITORING THE HIGH-LE"5L WASTE GEOLOGIC REPOSITORY PROGRAM NETWORK Progress Repcwt, January March 1988. SUBJECT TO QUAUTY ASSURANCE REQUIREMENTS OFC OF ENFORCEMENT (POST 870413)

NUREG-0940 V07 N01: ENFORCEMENT ACTONS SIGNIFICAr4T 0 U.S. NUCLEAR REGULATORY COMMISSION TONS RESOLVED Quarteriy Progress Report. January-March 1988. NRC NO DETAILED AFFILIATION GIVEN OFC OF SPECIAL PROJECTS NUREG/CR 5151: PERFORMANCE 8ASED INSPECTONS.

NUREG-1232 V02: SAFETY EVALUATON RFPORT ON TENNESSEE VALLEY AUTHORITY. Sequoyah Nuclear Performance Pian' OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 4/05/81)

OFFICE OF NUCLEAH REGULATORY RESEARCH, DIRECTOR (POST EDO OFFICE FOR ANALYSIS t IVALUATiON OF OPERATIONAL

^

860720)

DATA NUREG 1032: EVALUATIOW OF STATON BLACKOUT ACCOENTS OFFCE FOR ANALYSIS & EVALVATON OF OPERATIONAL DATA, DI- AT NUCLEAR POWER PLANTS.Techncal Findings Related To Un-RECTOR resolved Safety issue A 44Fnal Report.

NUREG4090 V10 NO3: REPORT TO CONGRESS ON ABNORMAL NUREG 1109: REGULATORY /BACKFIT ANALYSIS FOR THE RESO-OCCURRENCES. July September 1987. LUTON OF UNRESOLVED SAFEl f ISSUE A-44 STATON BLACK-NUREG-0090 V10 NO4: REPORT TO CONGRESS ON ABNORMAL OUT.

OCCURRENCES October December 1987.

NUREG 1226: DEVELOPMENT AND UTIUZATON OF THE NRC OFFICE OF GOVERNMENTAL & PUtfUC AFFAIRS POUCY STATEMENT ON THE REGULATION Of ADVANCED NU-STATE. LOCAL & INDIAN TRIBE PROGRAMS CLEAR POWER PLANTS.

NUREG 1311: FUNDING THE NRC TRAIN NG PROGRAM FOR NUREG-1266 V02: NRC SAFETY RESEARCH IN SUPPORT OF REG-STATES. ULATION .1987.

NUREG 1325: DSPOSmON OF RECOMMENDATONS OF THE NA-OFFICE OF INFORMATION RESOURCES MANAGEMENT TIONAL RESEARCH COUNCIL IN THE REPORT "REVITAUZING DIVISION OF FREEDOM OF INFORMATON & PUBLICATON SERV- NUCLEAR SAFETY RESERCH."

ICES (POST 880515) OfVISION OF ENGINEERING (POST 870413)

NUREG4304 V13 N01: REGULATORY AND TECHNICAL REPORTS NUREG-1217 DRFT FC: EVALUATON OF SAFETY IMPUCATIONS (ABSTRACT INDEX JOURNAL). Compilation For First Quarte' OF CONTROL SYSTEMS IN LWR NUCLEAR POWER NUR G 54 ' "*

0 04: TITLE UST OF DOCUMENTS MADE PUBLC. R NU EG O 50 V I Ox TO NUCLEAR REGULATORY COM. NUREG 1218 DPFT FC: REGULATORY ANALYSIS FOR PROPOSED MISSON ISSUANCES. Jaricary-March 1988 RESOLUTON OF USl A-4 7. Safety impleatons Of Control DVISON OF PUBUCATON SERVICES (870413-880514) Systems Draft Rept For Comment.

NUREG4540 V10 NO2. TITLE UST OF DOCUMENTS MADE PUBLO. NUREG 1221:

SUMMARY

, ANALYSIS AND RESPONSE TO PUBUC LY AVAILA8tE. February 1 29,1988. COMMENTS ON PROPOSED AMENDMENTS TO 10 CFR PARTS NURF.G-0540 V10 NO3: TITLE UST OF DOCUMENTS MADE PUBUC. 30.40,50,51.70 AND 72: DECOMMISSIONING CRITERIA FOR NU-LY AVAILABLE. March 1 31.1988. CLEAR FACIUTIES.

NUREG-0750 V26101: INDEXES TO NUCLEAR REGULATORY COM- NUREG 1233 DAFT FC: REGULATORY ANALYSIS FOR USI A-40, i MISSION ISSUANCES. JuPy-September 1987. "SEISMC DESIGN CRITERIA." Draft Report For Comment.

I NUREG-0750 V26102: INDEXES TO NUCLEAR REGUI.ATORY COM- NUREG 1236: THERMAL OVERLOAD PROTECTON /OR ELECTRC l M:SSON ISSUANCES. July-Decord er 1987.

Ms ORS ON SAFETY RELATED MOTOR-OPERATED VALVES -

NUREG-0750 V27 NO2: NUCLEV RCGULATORY COMM:SSION IS- GENERIC ISSUE ll E 6.1 SUANCES FOR FEBRUARY 1968. Pages 41255-MATERIALS ENGINEERING' BRANCH NUREG4750 V27 WO3: NUCLEAR REGULATORY COMMISSION IS.

NUREG-0975 V06: COMPILATON OF CONTRACT RESEARCH FOR OfVI N COM T M THE MATERIALS ENGINE ERING BRANCH, DIVISION OF ATONS SERVCES (POST 870413) ENGtNEER!NG Annual Report For FY 1987.

NUREG-0020 V12 NO3. UCENSED OPERATING REACTORS STATUS DIVISON OF REACTOR & PLANT SYSTEMS (870413-880716)

SUMMARY

REPORT. Data As Of February 23.1988 (G 7v Book 1) NUREG 1273: TENCAL FINDINGS AND REGULATORY ANALYSl$

NUREG-0020 V12 N04 UCENSED OPERATING REACTORS STATUS FOR GENERC SAFETY ISSUE 11 E.4 3. "CONTAINVENT INTEGRI.

SUMMARY

REPORT Data As Of March 31,1988 (Gray Book 1) TY CHECK."

NUREG 0020 V12 N05: UCENSED OPERATING REACTORS STATUS DIVISON OF REGULATORY APPUCATONS (POST 870413)

SUMMARY

REPO"T. Data As Of Aptd 30.1988 (Gray Book i) NUREG4713 V07. OCCUPATONAL RADIATION EXPOSURE AT COVVERCIAL NUCLEAR POWER REACTORS AND OTHER FA.

OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS CIUTIES 1985 Eghteenth Annual Report.

DVISON OF SAFEGUARDS & T9ANSPORTATON (POST 8704t31 NUREG 0933 S07. A PRCRITIZATON OF GENERIC SAFETY NUREG4725 R06 PUBLP INFORMATON CIRCULAR FOR SHIP. ;ggggg' MENTS OF IRRADATED REACTOR FUEL 35

36 NHC Originating OrganizatlOn Index (Staff Reports)

OFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80) NUREG 1306: NRC SAFETY SIGNIFICANCE ASSESSMENT TEAM OFFICE OF NUCLE AR REACTOR REGULATION, DIRECTOR (POST REPORT ON ALLEGATONS RELATED TO THE SOUTH TEXAS 870411) PROJECT, UNITS 1 & 2.

NUREG-0683 S03 DAFT: PROGRAMMATIC ENVIRONMENTAL STANDARDl2ATON & NON-POWER REACTOR PROJECT DIRECTOR.

IMPACT STATEMENT RELATED TO DECONTAMINATION AND ATE DISPOSAL OF RADIOACTIVE WASTES RESULTING FROM NUREG 1283: SAFETY EVALUATON REPORT RELATED TO THE MARCH 28.1979 ACCIDENT.THME MILE ISLAND NUCLEAR RENEWAL OF THE OPERATING LICENSE FOR THE RESEARCH STATION. UNIT 2 Docket No. 50-320 (GPU Nuclear incorporated) REACTOR AT PURDUE UNIVERSITY, NUREG 1032. EVALUATON OF STATION BLACKOUT ACCIDENTS DIVISION OF REACTOR INSPECTON & SAFEGUARDS (POST AT NUCLEAR POWER PLANTS Technecal Findings Related To Un- 870411) resolved Safety issue A44 Final Report NUREG-0040 V12 N01: LICENSEE CONTRACTOR AND VENDOR IN.

NUREG-1109. REGULATORY /BACAFIT ANALYSIS FOR THE RESO- SPECTION STATUS REPORT. Quarterty Report, January March LUTON OF UNRESOLVED SAFETY ISSUE A-44, STATION ELACK- 1988.(White Book)

OUT. OlVISION OF LICENSEE PERFORMANCE & QUAllTY EVALUATION DIVISION OF REACTOR PROJECTS HIJV,V & SPECIAL PROJECTS (POST 870411)

(POST 870411 NUREG 1214 R03: HISTORICAL DATA

SUMMARY

OF THE SYSTEM-NUREG 1002 S06 SAFETY EVALUATION REPORT RELATED TO ATO ASSESSMENT OF LICENSEE PERFORMANCE.

THE CPERATON OF BRAIDWOOD STATION, UNITS 1 AND 2 Docket Nos. 50-456 And 50457 (Cornmormeatth Edison Cornpany) l l

l E

I NRC Originating Organization Index (International Agreements)

This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where (appropriate.

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.

There were no NUREG/lA reports for this quarter, I

37

1 i

l l

l l

l

NRC Contract Sponsor Index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) pre 3ared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.

EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR 5019. NEUTRON EXPOSURE PARAMETERS FOR THE DATA METALLURGCAL TEST SPECIMENS IN THE FIFTH HEAVY SEC.

OFFICE FOR ANALYSIS & EVALUATON OF OPERATIONAL DATA. DI- TION STEEL TECHNOLOGY IRRADIATION SERIES CAPSULES.

RECTOR NUREG/CR 5044: ESTIMATION TECHN OUES FOR COMMON NUREG/CR 2000 V07 N3: UCENSEE EVENT REPORT (LER) CAUSE FAILURE EVENTS.

COMPfLATION For Month Of March 1988. NUREG/CR 5045: KANSAS-NEBRASKA SEISMCITY STUDIES NUREG/CR 2000 V07 N4: UCENSEE EVENT REPORT (LER) USING THE KANSAS-NEBRASKA MICROEARTHOUAKE COMPILATON For Month Of Apnl 1988. NETWORK.Fmal Report.

NUREG/CR-2000 V07 N5: LCENSEE EVENT REPORT (LER) NUREG/CR 5076: AN APPROACH TO THE QUANTIFICATION OF COMPILATION Fca Month rJf May 1988, SEISMC MARGINS IN NUCLEAR POWER PLANTS.The importance NUREG/CR-4674 V05: PRECURSORS TO POTENTIAL SEVERE Of BWR Plant Systems And Functions To Seesmic Margens.

CORE DAMAGE ACCOENTS:1986.A STATUS REPORT. NUREG/CR-5105: RESPONSE MARGINS INVEST 6GATION OF NUREG/CR 4674 V06: PRECURSORS TO POTENTIAL SEVERE PIPING DYNAMIC ANALYSES USING THE INDEPENDENT SUP.

CORE DAMAGE ACCOENTS:1986.A STATUS REPORT. PORT MOTON METHOD AND PVRC DAMPING.

NUREG/CR-5123: STUDIES OF THE PATTERN AND AGES OF OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS POST METAMORPHIC FAULTS IN THE PIEDMONT OF VIRGINIA DfVISON OF HIGH LEVEL WASTE MANAGEMENT (POST 870413) AND NORTH CAROUNA.

NUREG/CR-4735 Va3: EVALUATON AND COMPILATION OF DOE NUREG/CR-5129 EXPELMENTAL ASSESSMENT OF THE INFLU.

WASTE PACKAGE TEST DATA. Bennval ReportFebruary July ENCE OF DYNAMC LOADING ON THE PERMEABILITY OF WET 1987. AND OF DRIED CEMENT BOREHOLE SEALS.

NUREG/CR4864 V01: THERMODYNAMIC TABLES FOR NUCLEAR NUREG/CR-5130: BENTONITE BOREHOLE PLUG FLOW TESTING WASTE ISOLATON. Aqueous Solutions Database. WITH FIVE WATER TYPES.

NUREG/CA 5137: BIODEGRADATION TESTING OF TMI 2 EPICOR-il OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 4/05/81) WASTE FORMS.

OFFICE OF NUCLEAR REGULATORY RESEARCH, DIRECTOR (POST NUREG/CR 5142: DUCTILE TO BRITTLE TOUGHNESS TRANSITION 860720) CHARACTER 12ATION OF A533B STEEL NUREG/CR-4777: STEAM OXOATION OF ZlRCALOY CLADOING IN NUREG/CR 5159. PREDICTION OF CHECK VALVE PERFORMANCF THE ORNL FISSON PRODUCT RELEASE TESTS- AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS NUREG/CR4971: RESULTS OF SEMISCALE MOD 2C FEEDWATER DIVISION OF REACTOR ACCOENT ANALYSIS (870413-880716)

AND STEAM UNE BREAK (S FS) EXPERIMENT SERIES Main NUREG/CR-3509: POWER SPECTRAL DENSITY FUNCTIONS COM-Steam Ure Break Accdont Expenments PATIBLE WITH NRC REGULATORY GUIDE 1.60 RESPONSE NUREG/CR-5021 V01: USER'S GUOE FOR PRISIM ARKANSAS NU* SPECTRA.

CLEAR ONE . UNIT 1. Volume 1, Program For inspectors. NUREG/CR-4605: TRAINING MANUAL ON STATISTCAL METHODS NUREG/CR 5021 V02: USER'S GUOE FOR PRIS!M ARKANSAS NU- FOR NUCLEAR MATERIAL MANAGEMENT.

CLEAR ONE UNIT 1. Volume 2. Program For Regulators NUREG/CR 4778. PRELIMINARY STUDIES OF THE MORPHOLOGY NUREG/CR-5082: SIMULATION EXPERIMENTS ON TWO-PHASE OF THERMAL GRADIENT TUBE DEPOSITS FROM FISSON PROD-NATURAL CIRCULATON IN A FREON 113 FLOW VISUAUZAllON UCT RELEASE EXPERIMENTS.

LOOP. NUREG/CR 4881: FISSION PRODUCT RELEASE CHARACTERISTOS PROGRAM MANAGEMENT, POLCY DEVELOPMENT & ANALYSIS INTO CONTAINMENT UNDER DESIGN BASIS AND SEVERE ACCI-STAFF (POST 870413) DENT CONDITONS.

NUREG/CR 4315 V09 R1: EVALUATON OF NUCLEAR FACluTY DE' NUREG/CR-5000. METHODOLOGY FOR UNCERTAINTY ESTIMA-COMMISSION!NG PROJECTS Summe'y Status Report.Three Md*

TON IN NUREG 1150 (DRAFT) Conclus.ons Of A Renew Panet Island Unst 2.Ra$oactrve Waste And Lautry Shoments- NUREG/CR 5113: FtNDINGS OF THE PEER REVIEW PANEL ON THE l

O(VISION OF ENGINEERING (POST 870413) DRAFT REACTOR RISK REFERENCE DOCUMENT.NUREG 1150.

NUREG/CR-3899 S01: UTILITY FINANCIAL STABluTY AND THE DIVISON OF REACTOR & PLANT SYSTEMS (870413-880716)

AVAILABIUTY OF FUNDS FOR DECOMMISSON:NG An Arialyses Of NUREG/CR-4639 V01: NUCLEAR COMPUTERI2ED UBRARY FOR Internal And External Funding. ASSESSING REACTOR REUABluTY (NUCLARR) Volume NUREG/CR4082 V06: DEGRADED PIPING PROGRAM . PHASE I. Summary Descretion.

11 S<xth Program Report. October 1986 September 1987. NUREG/CR4836; APPROACHES TO UNCERfAINTY ANALYSIS IN NUREG/CR4219 V04 N2: HEAVY SECTON STEEL TECHNOLOGY PROBABlUSTC RISK ASSESSMENT.

PROGRAM. Semiannual Progress Report For Apni September 1987. NUREG/CR 5015: IMPROVED REUABluTY OF RESOUAL HEAT RE.

NUREG/CR4728. EOUtPMENT QUAUFICATION RESEARCH TEST MOVAL CAPABluTY IN PWR$ AS RELATED TO RESOLUTION OF OF A HIGH-RANGE RADIATON MONITOR- GENERIC ISSUE 99.

NUREG/CR-4763. SAFETY RELATED EQUIPMENT SURVIVAL IN 1Y. N*IREG/CR-5042 S01: EVALUATION OF EXTERNAL HAZARDS TO DROGEN BURNS IN LARGE ORY PWR CONTAINVENT BUILD- NUCLEAR POWTR PLANTS IN THE U"lTED STATES Seismic INGS. Hazard NUREG/CR-4879 V01: DEMONSTRATION OF PERMAMANCE MOD- NUREG/CR-5072 DECAY HEAT REMOVAL USING FE E D. AND-EUNG OF A LOW-LEVEL WASTE SHALLOW LAND BURtAL SITE A BLEED FOR U S PRESSURlZED WATER REACTORS.

Companson 08 PreGetico Radonuclide Transport Modehng Versus NUREG/CR-5078 V01: A RELIAB:UTY PROGRAM FOR EMERGENCY Field Observatons At The Nrtrate Disposal Pd S4e,Chaik Arror Nu- DIESEL GENERATO9S AT NUCLEAR POWER PLANTS Program clear Labs. Structure NUREG/CA-5013 FAtlGUE LIFE CHAR ACTERIZATION OF SMOOTH NUREG/CR-5095 V01: THERMODYNAMIC NONEOutuBRIUM IN AND NOTCHED P PING STEEL SPECIMENS IN 284 DEGREE C POST CRITICAL-HEAT FLUX BOtUNG IN A ROD AIR ENVIRONMENTS BUNDLE Deserction Of Erpentnents And Sampfe Results NUREG/CA-5016. COMPENDtVM AND COMPARISON OF INTERNA. NUREG/CR-5095 V02: THERMODYNAMIC NONEQUfUBRIUM IN TiONAL PRACTICE FOR PLUGG!NG. REPAIR AND INSPECTON OF POST CRITICAL HEAT FLUX BO'UNG LN A ROD BUNDLE Data For STEAM GENERATOR TUBING. Stathed Quench Front Tests 39

40 NRC Contract Sponsor Index NUREG/CR-5095 V03: THERMODYNAMIC NONEQUILfBRIUM IN NUREG/CR-4933. CLOSEOUT OF IE BULLETIN 80-19 FAILURES OF POST-CRITICAL HEAT-FLUX BOtLING IN A ROD BUNDLE Data For MERCURY WETTED MATRIX RELAYS IN REACTOR PROTECTIVE Advaneng Quench Front Tests. SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DE-NUREG/CR-5095 V04: THERMODYNAMIC NONEQUILIBRIUM IN SIGNED BY COMBUSTON ENGINEERING.

POST CRITICAL-HEAT FLUX BOILING IN A ROD BUNDLE. Data For Retreatng Quanch Front Tests. DIVISION OF ENGINEERING & SYSTEMS TECHNOLOGY (P(.sST NUR CR 5 7 Y AND CON UI FFE OF COM. NU G/ R-5150: STEAM GENERATOR OPERATING BINED ALPHA AND BETA IRRADIATION OF THE LUNG Phase 11 EXPERIENCE. Update For 1984 1986.

Report DIVISION OF RADIATON PROTECTION & EMERGENCY PREPARED-NUREG/CR 5138. VAllDATON OF GENERIC COST ESTIMATES NESS (POST 87041i)

FOR CONSTRUCTION-RELATED ACTivlTIES AT NUCLEAR NUREG/CR-5038: OPTIMl2ATON OF THE CONTROL OF CONTAMi-POWER PLANTS Foal Report NATION AT NUCLEAR POWER PLANT 3.

NUREG/CR 5160 GUIDE'INES FOR THE USE OF THE EEDB AT NUREG/CR 5055: ATMOSPHER!C OlFFUSON FOR CONTROL THE SUS-COMPONENT AND SUBSYSTEM LEVELFoal Report ROOM HABITABILITY ASSESSMENTS.

OFFICE OF NUCLEAR REACTOR REGULATIOgOST 4/28/60) DE U G/CR-46 : L SE lE ULLETI 3 ET1 L DIYlSION 'OF LCENSEE PERFORMANCE & QUALITY EVALUATION CIRCUlT BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE (POST 870411) tN USE IN SAFETY-RELATED APPLICATIONS OTHER THAN THE NUREG/CR-5147: FUNDAMENTAL ATTRIBUTES OF A PRACTICAL REACTOR TRIP SYSTEM. CONFIGURATON MANAGEMENT PROGRAM FOR NUCLEAR i NUREG/CR-4932: CLOSEOUT OF IE BULLETIN B0-03 LOSS OF PLANT DESIGN CONTROL CHARCOAL FROM STANDARD TYPE II,TWOlNCH, TRAY A D- NUREG/CR 515*: PERFORMANCE BASED INSPEC'ONS.

! SORBER CELLS.

1 l

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

APPUED RISK TECHNOLOGY CORP. EG4 G IDAHO, INC. (SUS $. F NUREG/CR-5076: AN APPROACH TO THE QUANTIFICATION OF SEIS- NUREG/CR4639 V01: h ,. "W'-9~

MC MARGINS IN NUCLEAR POWER PLANTS.The importance Of SESSING REACTOR RELIA" ~-+

BWR Plant Systems And Fenetions To Seesmic Margins. senption.

• NUREG/CR-4971: RESLN " OF L

• ARGONNE NATIONAL LABORATORY AND STEAM LINE B' ~ M) fr NUREG/CR 5082: SIMULATION EXPER!MENTS ON TWO PHASE NAT. Une Break Accident URAL CIRCULATION IN A FREON-113 FLOW VISUALIZATION LOOP. NUREG/CR-5072 DE' Ww -

FOR U.S PRESSUR ed 4  % 9S. i ARI2ON A, UNIV. OF. TUCSON, A2 NUREG/CR-5137: BCDEGhxDA 'ES f1NG  :

NUREG/CR 5129. EXPER: MENTAL ASSESSMENT OF THE INFLUENCE WASTE FORMS. l OF DYNAMC LOADING ON THE PERMEABfUTY OF WET AND OF DRIED CEMENT BOREHOLE SEALS.

ENGINEERING & ECONOMICS RESEARCH,INC.

NUREG/CR-5130; t;ENTONiTE BOREHOLE PLUG FLOW TESTING NUREG/CR-3899 S01: UTILITY FINANCLAL STABlUTY AND THE WITH FIVE WATER TYPES. AVAILABILITY OF FUNDS FOR DECOMMISSIONING.An AnaPyses Of BATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES NUREG/CR4082 V06: DEGRADED PIPING PROGRAM PHASE ILSerth KRC INTERN ATION AL, INC.

Program Report October 1986 September 1987. NUREG/CR 5147: FUNDAMENTAL ATTRIBUTES OF A PRACTCAL CONFIGURATION MANAGEMENT PROGRAM FOR NUCLEAR PLANT BATTEllE MEMORIAL INSTITUTE, PACIFIC NORTHWEST DESIGN CONTROL LACORATORY NUREG 1320; NUCLEAR FUEL CYCLE FACIUTY ACCIDENT ANALYSIS IDAHO NATIONAL ENGINEERING LA90filATORY HANDBOOK- NUREG/CR-5072: DECAY HEAT REMOVAL USING FEED-AND BLEED NUREG/CP-0093: PROCEEDINGS OF THE MEETING ON ULTRASEN- FOR U.S. PRESSURIZED WATER REACTORS SITIVE TECHNCUES FOR MEASUREMENT OF URANIUM IN 30-LOGCAL SAMPLF S AND THE NEPHROTOX1 CITY OF URANillM. J8F ASSOCIATES NUREG/CR-4605: TRAIN:NG MANUAL ON STATISTCAL METHOOS NUREG/CR 5021 V01: USER'S GUCE FOR PRislM ARKANSAS NU-FOR NUCLEAR MATERIAL MANAGEMENT. CLEAR ONE . UNIT 1 Yolume 1.Prefam For lespectors.

NUREG/CR4879 V01: DEMONSTRATION OF PERFORMANCE MOD- NUREG/CR-5021 V02: USER'S GUCE FOR PRIS!M ARKANSAS NU.

EUNG OF A LOW LEVEL WASTE SHALLOW LAND BURIAL SITEA CLEAR ONE . UNIT 1. Volume 2. Program For Regulators.

Compenson Of Predietrve Radionuchde Transport Modeling Vrwous Feld Observations At The N4 rate Disposal Pit Site.Cha'k het Nuclear KALSI ENGINEERING, INC.

Labs NUREG/CR-5159. PREDICTION OF CHECK VALVE PERFORMANCE NUREG/CR-5016. COMPENDtVM AND COMPARISON OF INTERNA- AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS.

TONAL PRACTICE FOR PLUGGINGBEPAIR AND INSPECTON OF STEAM GENERATOR TUBING KANSAS, UNIV. OF LAWRENCE, KS NUREGICR 5055 ATMOSPHERIC DiFFUSON FOR CONTROL ROOM NUREG/CR 5045: KANSAS-NEBRASKA SEiSMCITY STUDIES USING HABITABluTY ASSESSMENTS. THE KANSAS-NEBRASKA MCROEARTHOUAKE NETWORK Final BROOKHAVEN NATIONAL LA80RATORY NUREG/CR4881: FISSON PROOUCT RELEASE NARACWRISTCS LAWRENCE BERKELEY LAPORATORY INTO CONTAINMENT UNDER DESIGN BASIS nND $EVERE ACCI. NUREG/CR 4864 V01: THERMODYNAMC TABLES FOR NUCLEAR CENT CONDITONS WASTE ISOLATON Aqueous Solvtsons Database.

HUREG/CR-5000: METHOOOLOGY FOR UNCERTA:NTY ESTiMATON IN NUREG 1150 (DRAFT) Conclusons Of A Rowew Panel. LAWRENCE UVERMORE NATIONAL LADORATORY NUREG/CR 5015. IMPROVED REUABluTY OF RESCUAL HEAT RE- NVAEG/CR-5042 S01:EVALUATON OF EXTERNAL HAZARDS TO NU-MOVAL CAPABiUTY IN PWAS AS RELATED TO RESOLUTION OF CLEAR POWER PLANTS IN THE UNITED STATES Sesmec Hazard GENERC ISSUE 99 NUREG/CR-5076. AN APPROACH TO THE QUANTIFICATION OF SEIS. I NUREG/CR 5038. OPTIM12ATCN OF THE CONTROL OF CONTAMINA. MC MARGtNS IN NUCLEAR POWER PLANTS.The Irmortance Of l TON AT NUCLEAR POWER PLANTS. BM Ptant Systems And Functions To Seismec Margins NUREG/CR 5105. RESPONSE MARGtNS INVESTIGATION OF PIPING NUREG/CR-5113: FlNDINGS OF THE PEER REVIEW PANEL ON THE DY NAM.C ANALYSES US!NG THE INDEPENDENT SUPPORT DRAFT REACTOR RISK REFERENCE DOCUMENT.NUREG 1150.

MOTON METHOO AND PVAC DAMP;NG LEHIGH UNIV BETHLEHEM, PA l

! COLUMBIA UNIV NEW YORK, NY NUREGICA 5095 V01: THERVODYNAMC NONEQUtUBRIUM IN POST.

NUREG/CR-3509 POWER SPECTRAL DENSITY FUNCTIONS CCM- CAITCAL HEAT-FLUX BCHUNG IN A ROD BUNDLE DescrSbon Of l l PATIBLE WTH NRC REGULATORY GUCE 160 RESPONSE SPEC. Espenments And Sampo Resufts '

l TRA. NUREG/CR 5095 V02: THERMOOYNAMC NONEOctuBRIUM IN POST.

CRITCAL-HEAT FLUX BOluNG IN A ROD BUNDLE Data For Stabe- l COMMERCE, DEPT. OF, NATION 4'. BURE AU OF STANDARDS lud Quench Front Tests.

NUREG/CR435 V03 EVALUATON AND COMPILATON OF DOE NUREG/CR-5095 YO3. THERMODYN AMC NONEQUfUBRIUM IN POST. )

WASTE PACKAGE TEST DATA. Bennual Report February Jufy 1947. CRITICAL-HEAT-FLUX BoluNG IN A ROO BUNDLE Data For Advanc-ing Ovench Froct Tests DAVID W. TAYLOR NAVAL RESEARCH & DEVELOPMENT CENTER NUREG/CA-5095 V04 THERVOOYNAMC NONEOutUBRlVM IN POST.

NUREGICR.5142 DUCTfLE TO BRITTLE TOUGHNESS TRANSITON CRITICAL HE AT FLUX BO'UNG IN A ROD BUNDLE Data For Retreat.

CHARCTERf2ATION OF A5338 STEEL ing Ovench Front Tests 41 l l

l

42 Contractor index LOS ALAMOS NATIONAL LABORATORY NUREG/CR4932: CLOSEOUT OF IE BULLETIN 80-03 LOSS OF CHAR.

NUREG 1320: NUCLEAR FUEL CYCLE FACluTY ACCOENT ANALYSIS COAL FROM STANDARD TYPE II,TWO INCH, TRAY ADSORBER HANDBOOK. CELLS.

NUREG/CR 5044: ESTIMATON TECHNIQUES FOR COMMON CAUSE NUREG/CR4933: CLOSEOUT OF IE BULLETIN 80-19 FAILURES OF FAILURE EVENTS. MERCURY WETTED MATRIX RELAYS IN REACTOR PROTECTIVE SYSTEMS OF OPERATING NUCLEAR POWER PLANTS DESIGNED LOVELACE BOMED & ENVIRONMENTAL RESEARCH INSTITUTE BY COMBUSTON ENGINEERING.

NUREG/CR 5067: EARLY AND CONTINUtNG EFFECTS OF COMBINED ALPHA AND BETA 1RRADtATON OF THE LONG Pnase 11 Report SAND NATI A RATOR MATERIALS ENGINEERING ASSOCIATES,INC- A HIGH-RANGE RADfATION MONITOR.

NUREG/CR-5013. FATIGUE UFE CHARACTERIZAT:OG OF SMOOTH NUREG/CR-4763. SAFETY-RELATED EQUIPMENT SURVIVAL IN HY-AND NOTCHED PlPING STEEL SPECIMENS IN 288 DEGREE C AIR DA E NS LA DRY PW IN N But NGg gyp ENVIRONMENTS.

PROBABlUSTO RISK ASSESSMENT.

M ATHTECH, INC # ^ " ^ ^

NUREG/CR-5138. VAUDATON OF GENERO COST ESTIMATES FOR NU EG/ 8V1 LIA P Rb FOR EMERGENCY CONSTRUCTION-RELATED ACTIVITIES AT NUCLEAR POWER DIESEL GENERATORS AT NUCLEAR POWER PLANTS. Program PLANTS Foal Report Structure.

NUREG/CR-5160. GUOEUNES FOR THE USE OF THE EEDB AT THE SUB-COMPONENT AND SUBSYSTEM LEVELFnal Report SCIENCE & ENGINEERING ASSOCIATES,INC.

NUREG/CR 5138. VAUDATON OF GENERO COST ESTIMATES FOR OAK ROGE NATIONAL LABORATORY CONSTRUCTON-RELATED ACTivlTIES AT NUCLEAR POWER NUREG/CR-2000 V07 N3: LICENSEE EVENT REPORT (LER) PLANTS Fnal Report COMP 1LATON For Month Of March 1988. NUREG/CR-5160 GUOEUNES FOR THE USE OF THE EEDB AT THd l NUREG/CR-2000 V07 N4. UCENSEE EVENT REPORT (LER) SUB COMPONENT AND SUBSYSTEM LEVELFnal Report l COMPILATON For Month Of Apnl 1988 l

NUREG/CR-2000 V07 NS- UCENSEE EVENT REPORT (LER) SCIENCE APPLICATIONS INTERNATIONAL CORP,(FORMERLY j COMPIL ATON For Month Of May 1988 SCIENCE APPLICATIONS, i NUREG/CR4219 V04 N2. HEAVY SECTON SiEF( TECHNOLOGY NUREG/CR 5078 voi: A RELIABlUTY PROGRAM FOR EMERGENCY (

PROGRAM Serrmannual Progress Report For AprLSeptember 1967. DIESEL GENERATORS AT NUCLEAR POWER PLANTS Prograrn l NUREG/CR4674 V05: PRECURSORS TO POTENTIAL SEVERE CORE Structure DAMAGE ACCOENTS 1986.A STATUS REPORT. NUREG/CR-5106 USER'S GUOE FOR THE TACT 5 COMPUTER CODE.

NUREGICR4674 V06. PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-5150- STEAM GENERATOR OPERATING DAMAGE ACCIDENTS:1966.A STATUS REPORT. EXPERIENCE Update For 1984 1986 NUREG/CR4777: STEAM OXOATON OF ZlRCALOY CLADOING IN NUREG/CR 5151: PERFORMANCE BASED INSPECTONS.

THE ORNL FISSON PRODUCT RELEASE TESTS.

NUREG/CR 4'78. PREUMJNARY STUDIES OF THE MORPHOLOGY OF SOUTHWEST RESEARCH INSTITUTE THERMAL GRADtENT TUBE DEPOSITS FROM FISSON PRODUCT NURFG/CP.0075 PROCEEDINGS OF CSNI/NAC WORKSHOP ON RELEASE EXPERIMENTS DUCTtLE PIPING FRACTURE MECHANCS.

NUREG/CR 5019 NEUTRON EXPOSURE PARAMETERS FOR THE VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSBURG, METALLURGICAL TEST SPECIMENS IN THE FIFTH HEAVY SEC- yA TON STEEL TECHNOLOGY IRRADIATO*4 6ERIES CAPSULES NUREG/CR 5123. STUOtES OF THE PATTERN AND AGES OF POST.

NUREG/CR 5021 V01: USER'S GUOE FOR PRIS.M ARKANSAS NU- METAMORPHIC FAULTS IN THE PIEDMONT OF VIRGINIA AND CLEAR ONE UNIT 1. Volume 1. Program For inspectors NORTH CAROUNA' NUREG/CR 5021 V02 USER'S GUIDE FOR PRIS M ARKANSAS NU.

CLEAR ONE UNIT 1. Volume 2. Program For Regulators WElRICH & ASSOCIATES PARAM E TE R, INC. NUREG/CR 5151: PERFORMANCE-BASED INSPECTONS.

NUREG/CR4665 CLOSEOUT OF IE BULLETIN 83-08 ELECTRICAL WESTINGHOUSE HANFORD CO.

CIRCUIT BREAKERS WITH AN UNDERVOLTAGE TRIP FEATURE IN NUREG/CR4315 V09 R1: EVALUATON OF NUCLEAR FACILITY DE.

USE IN SAFETY RELATED APPUCATONS OTHER THAN THE RE- COMMISSONING PROJECTS. Summary Status Report Three Mde ACTOR TR;P SYSTEM. Istand Urvt 2,Ra$oactrve Waste And Laundry SNpments l

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

There were no NUREG/lA reports for this quarter.

43

\ _ _ _ _ _ _ _ _ _ _

l 1

l i

l l

I r

I P

l

Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number, if further information is needed, refer to the main citation by the NUREG number.

S 313 Mesas twer One. Und t, Musas Pone NUAE3/CR 5021 VO1  % 328 Seah twer P. ant und 2. Tennessee NUREG1232 V02

& LgN Co. Vasey A#onty S 313 Maws twer One. Und 1, Mrsas Powa Wi3/C45C21 V02 STN S4M Saum fesas Propct und 1, Houston Lg*g & ME41306

& LgN Ce po.w Co STN S456 kadwwj Ste:n Urd 1. Comoreese E& son NURE11002 S06 STN-S4M Soum Texas Propct und 2, Houston Ughtrg & NUREG1306 1 Co Peev Co i STN S457 a m Urd 2. Comcreeat E$ son NURE11002 S06

&adwood S'  % 320 TW W/4 WW hr S'am Und 2. MEM M DRFT 1 1 en r Wm t., e ~4320 Thr wrd a Stam Und 2. NUPEG/CR 4315 V09 R1 ,

um w m m - i.1- NUnES,232 v02  %-=

vasey unoney r

9 1

45

y 3 RUCLE AA AtGULATon T Coue8188804 i Al' Oaf huweld tAuw er riOC, saa ver 4s, # says kmc F0m ) 33s f[ch,',',y- BIBLIOGRAPHIC DATA SHEET NUREG-0304, Vol. 13, No. 2 sit i%:TauCTs0NS ON Tat alvinst 2 TITLt A%o susTITLt 3 LE AVE SLANE Regulatory and Technical Reports (Abstract Index Journal)

Compilation for Second Quarter 1988 . o A Ti nt,OmT CO.,tt u o April - June oONT.

j

,IAm

& AUTMOm.si 6 D ATI mtPOR T t$5UED MONTM viAR August 1988 8 ,ROstCT;T ASK vromK W%lf NvW9tm 7 e tMOmWING Om3 ant 2 AfiON N Avt ANO Walu%G ADDRE55 tsevat te Code /

Division of Freedom of Information and Publications Services Office of Administration and Resources Management ' ~ oa ca ' * **" a U.S. Nuclear Regulatory Conmission Washington, DC 20555 10 &#0NSOa N3 0mO AN,2Af DOM % Avt A%D waekihG ADDatsS isaca v er le Coper l'a T vrt 07 me,Omf Reference Same as 7, above. . ,t m,Oo CO, t m:0 <, ...e --,

l April - June 1988 j 13 SUPPLEUt %f Am v NOf ts i 13 A t lT m ACT JtJo eeres or ess/

This journal includes all fomal reports in the NUREG series prepared by the NRC staff and contractors; proceedings 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.

i t o DOCyVt %T &% A sil l - e u t ' Aga;5 CISCa *'O*5 it ava4 Ac.u f ,

5fATIve%f compilation abstract index Unlimited

'S SECi,aiTY CL All'8#CATIC%

t ret seren

. ei%T,,,t se,t% n:taTi v, Unciassified f Fa g eseert/

Unc1assified

,,%so.tmc.. Acts

,...<a <

.v.3,emewer en =rias cniaim .rar.rerism:

1 NUCLEAR REE LAT 3Y OMMIS$10N NT D WASHINGTON, D.C. 20566 Z MWan??bh- #

n1AC19'19 ,E' Main citations l2oS551313h'ao"1 g S"CS <

and Abstracts gs n g poBLICAT1oNS DQs.90R NUREG OC 20555 .

g

(~g{hkNGTON g Secondary Report Number Index Personal Author Index 5

8 Subject Index k 2

NRC Originating Organization index (Staff Reports)

]d F9 iz Eh z r-m,

-m NRC Originating Organization Index (International Agreements) lly en 3

NRC Contractor 5 Sponsorindex ,

Contractor Index l

l g International Organization Index >

8 Li ensed Facility 10 Index l

. -