ML20065T586

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Third Quarter 1990,July-September

ML20065T586
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Issue date:	12/31/1990
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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References
NUREG-0304, NUREG-0304-V15-N03, NUREG-304, NUREG-304-V15-N3, NUDOCS 9012280235
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NUREG-0304 Vol.15, No. 3 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for Third Quarter 1990 July - September U.S. Nuclear Regulatory Commission Omce of Administration on asevy j

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PDR' 0304 R l

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

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

1 NUREG-0304 Vol.15, No. 3 Regulatory and Technica Reaorts (Abstract Inc ex Journal)

Compilation for Third Quarter 1990

- Ju_ly - September -

Date Published: December 1990 Regulatory Publications Ilranch Division of Freedom ofInformation and Publientions Services Of11ce of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555

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i CONTENTS Pref ace.....

y Index Tab Muin Citations and Abstracts.............

1

• Staff Reports

• Conference Proceedines

• Contiactor Reports -

• International Agreement Reports

- Secondary Report Number index,...

2 Fersonal Author index..,

3 Subject index.....

4 NRC Originating Organization index (Staff Reports),,,.......

5 NRC Originating Organization index (International Agreements).

6 NRC Contract Sponsor Index (Cnntractor Reports).

7 Contractor irdex....,.....

8

-international Organization index.

9_

Licensed Facility index..

10 i

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PREFACE This compilation cone.

! bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to pubiish thk compilation quarterly and to cumulate it annually. Your comments will be ap-preciated. Plecse 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. 20555 he main dictions end abstracts in this compilation are listed in NUREG number order: NUREG-XYAX, 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 Originating Organization index (Staff Reports)

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor Index (Contractor Reports)

Contractor Index Intemational Organization index Licensed Facility index A detailed explanation of the ent4s precedes each index.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0808: UMK 11 CONTAINMENT PROGRAM JALUATION AND ALCEPTANCE CRITERIA.

ANDERSON,C.s. 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) orp

.tional unit of

- author, (5) date report was published, (6) number of pages in the report, (7) the NF

'cument Control System accession number, (8) the mk:rofiche address (for internal NRC use).

Conference Report NUREG/CP 0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND REllABILITY ENGINEERING IN NUCLEAR RESULATION JANERP, J.S. Argonne National Laboratory.- May 1981.141 pp. 8105280299. ANL-81-3. 08632:070.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of page 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).

Contractor Report NUHEC 'CR 1506: STIJDY OF ALTERNATE DFCAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R.

Sandia Lnboratories. May 1981.100 pp. 8101010449. SAND 80 0929. 08912:242.

Where tne 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 peges in the report, (7) the NRC Decument Control System accession number, (8) the report number of the originating organization (if givca), and (9) the microfiche cddress (for NrlC intomal use).

v

Fa international Agreernent Report NUREG/l A 0001: ASSESSMENT Of TRAC PD2 USING SUPER CANNDN AND HDR EXPERIMENTAL DATA. NEUM ANN, U. Kraf twerk Union. August 1980. 223 pp. 8608270424. 37659:138.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) dato report was published (6) number of pages in the report, (7) the NRC Docurnent Control System accession number, (f.) 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 reoort:

ADD

- addendum APP append!x DRFT drcft ERR

- errata N

number R - revision S

supplement V - volume Availability of NRC Publications Copies of isRC staff and cnntractor reports reay be purchased eaher from the Government Printing Office (GPO) or from the National Technical Information Service, Springfield, Virginia 22161. To rurchase documents from the GPO, send a check or monei order, payable to the Superintendent of Documents, to tha following address:

Superintendent of Documents U.S. Government Printing Jffice Post Office Box 37082 Washington, DC 20013 7082 You may charge any purchase to your GPO Deposit Account, MasterCa;d char 00 card, or VISA charge card by calling the GPO on (2021275 2060 or (202)275-2171. Non U.S. customers must make payment in advance either by intemational 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.

NhC Report Codes The NUREG designation, NUREG-XX.XX, indicates t' Jt the do ument is a formal NRC staff-generated report. Contractor prepared formal NRC reports carr3 the report code NUREG/CR XXXX. This type of identification replaces contractor established cot.as st h as ORNL/NUREG/TM-XXX and TREE-NUREG XXXX, as vvell as various other numbers that would 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, j-NUREG/CR XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-r'ational agreernent report. The bibliographic inforrnation (see Preface for details) is followed by a brief abstract of this report.

NUREG 0020 V14 NO3: LICENSED OPERATING REAC10RS NUREG 0325 R14: U S. NUCLEAR REGULATORY COMMISSION STATUS

SUMMARY

REPOR T. Data As Of F ebruary F UNCilONAL ORGANIZATION CHARTS August 15, 1990 28,1990 (Gray Book 1) HARIF IEL D.R A. Dmsion of Computer &

Ofc of Personnoi (Post 870413) September 19n0. 02pp Telecommurucations Snrvices (Post 890205) May 1990. 53tpp 9010090054 55333 027 L

9008070321. 54800 231 Functionai organuation charts for the U.S Nucice Requiatory THE OPERATING UNITS ST ATUS REPORT LICENSED Commisson othces, desons, and brarches are pre sented OPERATING RE ACTORS provices data on the operation of nu-clear units as timely and accurately as possible This informa.

NUREG-03V 33 R07: UNITED ST Alw NUCLE AR REGULA.

tion is cellected by the Office of Informa:o' Resources Man.

TORY MMM!SSION STAFF PRACTICE AND PROCEDURE agement from the Headquarters staff of NRC's Office of En.

DIGEST Commisson, Appeal Board And LNensing Doard for ement (OE), from NRC's Regional Offices, and from utilitms Decisions July 1972 March 1990 Office of the General The three sections of the report are. monthly highlights and sta Counsel (Post 860701) August 1990 6Hpp 9009120095.

tistics for commercial operatmg units. and errata from previously

$5125145 reported data; a compilation of detailed information on each This Revision Number 7 of the fifth edition of the NRC Prac-unit, provided by NRC's Regonal Othces OE Headquarters and tice and Procedure Digest contains a digest of a number of the utilitier, and an appendix for misceDaneous information such Commission, Atomic Safety and Licenong Appeal Board, and as spent fuel storage capability, reactor-years of exponence and Atomic Safety and Licensing Board decisons is.ued donng the non power reactors in the U S. It is hoped the report.s helpful period July 1,1972 to March 31,1990, interpreting the NRC's to all agencies and ind xtuals interested in maintaining an Rules of Practice in 10 CFR Part 2.

awareness of the U.S. ene<ge situaton as a whole NUREG-0525 R 16: SAFEGUARDS

SUMMARY

EVENT LIST NUREG 0040 V14 N01: LICENSEE CONTRACTOR AND (SSEL)

Divison of Safeguards & 'iransportation (Post VENDOR INSPECTION STATUS REPORT. Quarterly 870413) July 1090. 369pp 9009070011. 55070.128 Report. January March 1990

• Divison of Reactor inspection &

The Safeguards Summary Event List provides brief summa-Safeguards (Post 87041I) July 1990 2t?pp, 90081404D9.

nos of hundreds of safeguards related events involving nuclear 54024 276.

matenal or facilites regulated by the U S Nuclear Regulatory This penodical covars the results of 6nspections performed by Commission. Events are descnbod under the categones bomb-NRC's Vendor Inspection Cranch that have been distnhuted to related, intruson, missing / allegedly stoico, transportation-relat.

the inspected organizations dunng the ponod trocn January ed, tampenng/ vandalism, arson, fvearms related, radiological 1990 through March 1990.

sabotage, non-radiological sabotage. alcohol and drug related.

and rniscellaneous Decause of pubhc interest, the miscellane.

NUREG 0090 Vl3 N01: REPORT TO CONGRESS ON ABNOR-ous section also includes events reported involving source ma-MAL OCCUR'VNCES January March 1990.

• Office for Analy-tonal byproduct matenal, and natural uranium, which are sis & Evaluation of Operational Data, Director. July 1990.42pp exempt from safeguards requirements. Information in the event 900H160098. 5494 7-281, descnptions were obtained from othcial NRC reports Section 208 of the Energy Reorganuaton Act of 1974 idents fies en abnorma! occurrence as an unscheduled incident or NUREG 0540 V12 NO3; TITLE LIST OF DOCUMENTS MADE event which the Nuclear Regulatory Commisson determines to PUBLICLY AVAILABLE March 1-31, 1990.

• Drvision of Free-be significant from the standpoint of public health and safety dom of Information & Pubhcations Services (Post 890205) July and requires a quarterfy report of such events to be made to 1990. 453pp 9008070384 54847,012.

Congress. This report covers the penod January 1 throut}h This document is a monthly publication containing descnp-March 31,1990 For this reporting penod, there wero 10 abnor-tions of information received and generated by the U S. Nuclear mal occurrences One involved the loss of vital ' power with a Regulatory Commission (NRC). This information fncludes (1) subsequent reactor coolant system heat up at the Vogtle Unit I docketed material a$sociated with civilian nuclear power plants i

power plant during shutdown. The event was investigated by an und other usns of radioactive matenals, and (2) nondocketed NRC incident iavestgation Team (IIT) The other nine abnormal matenal received and generated by NRC p(rtinent to its role as occurrences involved nuclear matenal iicensees and are do-a regulatory agency The following indexes are included Per-scnbed in detail under other NRC-issued licenses eight of sonal Autnor, Corporate Source, Report Number, and Cross these involved medical therapy misadminit*ations; the other in-Reference to Pnncipal Documents.

volved the receipt of an unshioided radioactive source at Amer-sham Corporation in Darlington. Massachusetts. The latter event NUREG 0540 V12 N04: TITLE LIST OF DOCUMENTS MADE was also investigated by an NRC lit No abnormat occurrences PUBLICLY AVAILAULE Apni 1-30. 1990

• Division of Freedom we.* reporhx1 by the Agreement States The report also con-of information & Publications Servic,1 (Post 890205) July 1990.

tuine informaton that updates a previously reported abnormal 322pp. 9008160107. 91940 016 occurrence See NUREG-0540.V12 NO3 abstract 1

l

2 Main Citations and Abstracts NUREG 0540 V12 N05: TITLE LIST OF DOCUMENTS MADE NUREG-0933 S11: A PRIORITIZATION OF GENERIC SAFETY PUBLICLY AVAILABLE May 1 31, 1990

• Divison of Freedom ISSUES EMRIT R.; R!GGS.R.; MILSTEAD.W., et al Divison of of Information & Pubhcations Services (Post 890205) July 1990.

Regulatory Appheations (Post 870413) July 1990. 180pp.

414pp 9008160102. 54947.322.

9008070346 54862 255.

See NUREG 0540.V12.NO3 abstract-The report presents the prionty rankings for genenc safety issues related to nuclear power plants The purpose of these NUREG-0540 V12 N06: TITLE LIST OF DOCUMENTS MADE.

ranongs is to assist in the timely and efficient allocahon of NRC PUBLICLY AVAILABLE. June 1 30. 1990

• Division of Freedom resources for the resoluton of those safety issues that have a of Informaton & Pubhcatons Services (Post 890205). August 1990. 333pk 9000040041 55050 227.

sign f' cant potential f or reducing nsk. The safety poority rankings are HIGH, MEDIUM, LOW, and DROP and have been assigned See NUREG-0540.V12,NO3 abstract.

on the basis of nsk significance estimates, the ratio of risk to NUREG 0540 V12 N07: TITLE LIST OF DOCUMENTS MADE costs and other impacts estimated to result it reso.utiors of the PUBLICLY AVAILABLE. July 1-31, 1990.

• Dtvmon of Freedom safety issues were implemented, and the consideratu of un-of Information & Pubhcations Sarvices (Post 890205) Septem-certaintms and other quantitative or quahtative factors. To the ber 1990 364pp. 9009210224. 55232.198-extent practical, estimates are quantitative.

See NUREG 0540,V12,NO3 abstiact NUREG 0750 V31 !01: INDEXES TO NUCLEAR REGULATORY y

3 N0h NM REWWW AMA&aWy deport,Apnl-June 1990., Divis on of Freedom of Informaton &

COMMISSION ISSUANCES. January. March 1990

• Division of a s c

(Post 890205) July 1990. 153pp.

Freedom of information & Pubhcations Services (Post 890205) g y, g

p9 July 1990. 53pp. 9009170093. 55202:102' The NRC Regulatory Agenda is a compilation of all rules on Digests and indexes for issuances of the Commission. the which tho NRC has proposed or is considenng a: tion and all Atomic Safety and Licensing Appeal Panel, the Atomic Safety petitions for rulemaking which have been received by the Com.

and Leensing Board Panel, the Administrative La* sudges, the mission and are ponding disposition by the Commission. The Directors Decisions, and the Denials of Pehtions for Rulemak.

Regulatory Agenda is updated and issued each quarter.

ing are presented NUREG-0750 V31 N05: NUCLEAR REGULATORY COMMISSION NUREG-0940 V09 NO2: ENFORCEMENT ACTIONS. SI'NIFl-ISSUANCES FOR MAY 1990 Pages 371481.

• Division of CANT ACTIONS RESOLVED.Ouarterly Progress Repo.Apol.

Freedom of information & Publications Services (Post 890205).

June 1990.

• Ofc of Enlorcement (Pust 870413). Se ember July 1990.117pp. 9008070350 54863.075.

1990 502pp Of

~ 'X)62. 55242:170 Legallasuances of the Commission, the Atomic Safety and Li.

This compilation,,ummaraes significant enforcement actions censing Appeal Panel, the Atomic Safety and Licensing Board that have been resolved dunng ono quarterly penod (Apnl Panel, the Administrative Law Judges, and NRC Program Of.

June 1990) and includes copie of letters, Noticos, and Orders fices are presented sont by the Nuclear Regulatory Commission to licensees with NUREG-bl50 V31 N06: NUCLEAR REGULATORY COMMISSION information in this pubhcation will be widely disseminat%d to ISSUANCES FOR JUNE 1990 Pages 483 604.

• Division of managers and employees engaged in activities hcensed by the Freedom of Informahon & Pubhcations Services (Post 890205)

NRC, so that actions can be taken to improve safety by avoid-August 1930.133pp. 9000040088 55046.178.

ing future violatons similar to those described in this pubhca-See NUREG-0750,V31,N05 abstract-tion.

NUREG 0750 V32 N01: NUCmEAR REGULATORY COMMISSION NUREG 1145 V06: U.S. NUCLEAR REGULATORY COMMISSION ISSUANCES FOR JULY 1990 Pages 155.

• Division of Free-1989 ANNUAL REPORT.

• Off ce of Administration (F ost dom of information & Pubbcations Services (Post 800205)~

800205) July 1990. 248pp. 9009040091. 55047:155.

August 1990. 62pp. 0000130045. 55194 041 This report covers the major activities, events, decisions, and See NUREG 0750,V31,N05 abstract.

planning that took place dunng fiscal year 1989 within the U.S NUREG-0800 17.3 ROO: STANDARD REVIEW PLAW FOR THE Nuclear Regulatory Comenssion (NRC) or involving the NRC.

REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition.Rev'sion 0 To SRP Sxtion 17.3, NUREG 1214 R06: HISTORICAL DATA

SUMMARY

OF THE SYS-

"Quahty Assurance Program Desenpt.on."

• Division of Licens.

TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.

ee Performance & Ouality Evaluation (Post 870411). August ALLENSPACH,F.; WHARTON,R. Division of Licensee Perform-1990. 20pp 900907000). 55071:137, ance & Quakty Evaluation (Post 870411), August 1990 114pp.

SRP Section 17.3. "Quahty Assurance Program Desenptiony 9008310213. 55043 056.

is a new section in Chapter 17. It puts in place a performance.

The Histoncal Data Su nmary of the Systematic Assessment oriented quality assurance program review plan that (1) mini.

of Licensee Performance (SALP) is produced penodicalty by the maes the current fragmentation and overlap of the self assess.

U S Nuclear Regulatory Commission. This summary provides ment function respor,sibehties, including salety committee activ,.

the results of the assessmnnt for each facilty by NRC region ties, audits, and other independent assessments, (2) simphfies and is further divided into the following sectons: Secton 1 pre-the format, clarifies the intent, and consohdates the text of the sents the most recent SALP report ratings for facihties in oper-present SRP Sect lons 171 and 17.2, (3) places emphams on aton and under construction. Section 2 presents a chronologi-management, performance /venficabon, and self assessment, cal hsting of all SALP report ratings for each operating facihty.

the three components of quakty assurance. and (4) permits the Section 3 presents a chronological hsting of all SALP report rat-use of up-to date industry consensus standards.

ings for each facihty under construction. For historical purposes, NUREG-0837 V10 NO2: NRC TLD DIRECT RADIATION MONI-TORING NETWORK. Progress Report. Apni-June 1990.

STRUCKMEYER,R.; MCNAMARA.N Region 1 (Post 820201)

NUREG 1272 V04 N01: OFFICE FOR ANALYSIS AND EVALUA-SM tember t 990. 226pp. 9010090064. 55319.345 TlON OF OPERATIONAL DATA 1989 ANNUAL REPORT Power This report provides the status and results of the NRC Ther-Reactors.

• Office for Analysis & Evaluation of Operatonal molum scent Dosimeter (TLD) Direct Radiation Monitonng Data Director. July 1990 264pp. 9009040081. 55048.295.

Netwsrx. It presend the radiation levels measured in the vicinity The annual report o' the U.S. Nuclear Regulatory Commis-of NRC bcensed facihties throughout the country for the second sion's Office for Anafysis and Eve'uabon of Operatonal Data quarter of 1990 (AEOO) is devoted to the activities performed d~ing 1989 The

. - = -

Main Citations and Abstracts 3

report is pubhshed in two separate parts NUREG 1272, Vol 4, Regulatory Commission. This report summanzes, highlights and fiv.1, covers power reactors and presents an overview of the analy70s how ne wide-ranging issues raised in these proceed-ope:ating expereence of the nuclear power industry from the ings were addressed by the Judges and Licensing Boards of NRC perspechve, includ:ng comments about the trends of some the ASLDP our ng the year.

key performance measures The report also includes the punch

. pal fincngs and issues identified in AEOD studies over the past NUREG-1377 ROI: NRC RESEARCH PROGRAM ON PLANT year urid summarizes information from such sources as Itcensee AGING-LISTINGS AND SUMMARIE i OF REPORTS ISSUED event reports, diagnostic evaluations, and reports to the NRC's THROUGH MAY 1990. KONDiC,N N HILLE.L. Dwision of En-Oparations Center. This report also compiles the status of staff gineenng (Post 870413). Juty 1 WO. 62pp. 9008070371, actions resultirg from previous incident Investigation Team (IIT) 54845'036.

reports. NUREG 1272, Vol 4 No. 2, covers nonreactors and The U.S. Nuclear Regulatory Commission is conducting the presente a review of the events and concerns dunng 1989 as.

Nuclear Plant Aging Research (NPAR) Program. This is a com-sociated with the use of bcensed matenal in nonreactor applica.

prehenswe hardware ononted enginevnng research program fo-tions, such as personnel overexposures and medical misadmin-cused on understanding the aging mechanisms of components istrations Each volume contains a hst of the AEOD reports and cystems in nuclear plants. The NPAR program also focuses issued for 1980 1989.

on methods for simulating and monitonng the aging related deg-NUREG-1272 V04 N02: OFFICE FOR ANALYSIS AND EVALUA-radation of these components and systems. In addition, it pro-TION OF OPERATIONAL DATA 1989 ANNUAL vKios recommendations for effective maintenance to manage REPORT.Nonreactors.

• Othce for Anatysis & Evaluation of aging and for the implantation of the research results in the Operationai Data, Director. July 1990. 68pp. 900004u059.

regulatory process. This document contains a hsting and index 5504L t 99 of rep rts g norated in the NPAR program that were issued See NUREG 1272,V04,N01 abstract-through May 1990 and summaries of those reports Each sum-mary descnbos the elements of the research covered in the NUREG 1339: RESOLUTION OF GENERIC SAFETY ISSUE report and outlines the signit cant results For the convenience

29. BOLTING DEGRADATION OR FAILURE IN NUCLEAR of the user, the reports are indexed by personal author, corpo-POWER PLANTS JOHNSON.R.E Division. of Safety issue Res-rate author, and subject.

olution (Post 880717). June.1090.

20pp. 9008t40466.

5492h158.

NUREG 1396: ENVIRONMENT AL ASSESSMENT OF THE THER.

This report desenbes the U.S. Nuclear Regulatory Qmmis-MAL NEUTRON ACTIVITATION EXPLOSlVE DETECTION sion's (NRC's) Genenc Safety issue 29, " Bolting Degrek.on or SYSTEM FOR CONCOURSE USE AT U.S.

AIRPORTS Fallure in Nuclear Power Plants." including the bases n estab-JONES.C G Division of Industnal & Medical Nuclos Salety lishing the issue and its historical highhghts The report also do-(Post 870729). August 1990.150pp. 9010090050. 55322.093.

senbos the activities of the Atomic tridusinal Forum (AIF) reic.

This oocument is an environmental assossment of a system vant to this issue, including its cooperation with the Mater,als designed to dctoct ino presence of explosives in checked air-Properties Couned (MPC) to organize a task group to help re-hne baggage or cargo The system is meant to bo installed at solve tne issue. The Electnc Power Research Institute, support-Ino concourse or lobby ticketing areas of U.S. commercial air-ed by the A1F/MPC task group, prepared and isnued a two-ports and uses a sealed radioactive source of californiurn 252 to volume document that provides, in part, the technical basis for irradiate bagaage items, The maior impact of the use of this

- resolving Genoric Safe'y issue 29. This report presents the system anses irom direct exposure of the public to scattered or NRC's review and evaluation of the two volume document and leakago radiation from the source and to induced radioactivity in NRC's conctusion that this document, in conjunction with otner baggage items. Under normal operation and the most likely ac.

Information from oath industry and NRC, provides the bases for cident scenarios, the environmental impacts that would be cre-resolving this issue.

aied by the proposed bcensing action would not be significant.

- NUREG 1362 DRFT FC: REGULATORY ANALYSIS FOR PRO-NUREG-1398 DRFT FC: ENVIRONMENTAL ASSESSMENT FOR POSED RULE ON NUCLEAR POWER PLANT LICENSE PROPOSED RULE ON NUCLEAR POWER PLANT LICENSE RENEWALDraft Report For Comment.

• Dwision of Safety issue Reso!ution (Post 880717), July 1990. 213pp. 9008070329 RENEWALDraft Report For Comment

• Dwision of Safety 54f.62:042.

Issue Resolution (Post 880717). July 1990. 57pp. 9008070358.

54845 250 This regulatory anaiysis provides the supporting information for a proposed rule that will dehne the Naclear Hegulatory Com-The possibie environmental effects of promulgating nuclear mission's requirements for renewing the operating hcenses of power plant hcense renewat standards by the proposed rulo,10 commercial nuclear power plants. A r.et of four specific alterna.

CFR Part 54. rather than applying requirements in an ad hoc tives for the safety review of license renewal apphcations is de-manner in indwntual heensing actions, nre assessed. The rule fined and evaluated These are. Alternative A current licensing Inquires the develvpment of information and analyseG to identify basis; AlternatNo 8b-extension of Altemative A to require as.

aging problems of systems, structures, and components that will sessment and manuging ut aging; AlternatWe C-extension of be of concern dunng the renewal term and will not be controlled Allematwe O to require assessment of design ditterences

.by existing regulatory programs. Required act;ons may be re-against selected rew plant standards using proba - % tic risk as-placement, refurb Shment, inspection, testing or monitonng sessment; and Altematwo D--extension of Asiernahve D to re-Such actions will genersity be within the range of simdar actions quire complianco with all new.piant standa-ds. A quantitative taken for plants dunng the initial oporating term They would be comparison of the four altematives in terms of impact to-value pomanly conhnod withir, t' a plants with potential for only minor rahos is presented, and Alternative B is the most cost-beneficial disruption to the environn int. It is unhkely that these actions safety review alternatwo would change the operating conditions of plants in ways that would change the environmental effects already being experi.

NUREG 1363 V02: ATOMtC SAFETY AND LICENSWG BOARD enced The promulgation of 10 CFR r> art 54 has clear advan-PANEL ANNUAL REPORT FISCAL YEAR 1989. COiTER,0.P.

tages relatwo to reg'alatory stabdity and PdministretNe efficiency.

Atomic Safety and Licensing Board Panet July 1990. 63pp.

Howeve6 it will not result in environmen.al effects signihcantly 9008070362. 54845 098 different from those ansing from reticensing under existing regu-In Fiscal Year 1989, the Atomic Safety and Licensing Dowd lations. The NRC concludes that promulgation of to CFR Part Panel (ASLBP) handled 40 proceedings involving the cr.astruc-54 would not significant!y affect the environmen' and, therefore, tion, operation and maintenance of commercial nuclear power a full environmental impact statement is not required and a teac' ors or other actwitres requinng a hconse f.om the Nuclear Finding of No Significant Imnact can be made.

~

=

-4 W,In Citations and Abstracts NUREG 1407 DAFT FC: PROCEDURAL AND SUBMITTAL GUID-cation and accordingty need not be made anew at the time of ANCE FOR INDIVIDUAL PLANT EXAM: NATION OF EXTER.

hconse renewal This analysis dosenbos the regulatory process-i NAL EVENTS (IPEEE0 FOR SEVERE ACCIDENT es that form the basis for such a finding. This document dis-VULNERA9iLITIES Draft Report For Cominent

• Dwision of cusses tow the kcensing process has evolved in maior safety Safety fssue Resolutroq. (Post 680717) July 1990. 41pp.

issue areas under existing regulatory processes that have on-D008070367. 54845 307.

sured continued adequacy of the keensing bases of all operat-Based on a Pohey Statement on Severe Acc dents, the h-ing plants The document presents the desenbod regulatory consee of each nuciear power plant is requested to perform an processes as the Commission's reasons for considenng it un-indmdual plar't exarrunaton The plant oxaminaton systemati-necessary to re review an operating plant's Ir.ensing basis, ca!!y looks for vulnerabihties to severe accidents and cost-effec, except for age related degradation concerns, at the time of h-two safety improvements that reduce or eliminate the impc' tant -

cense renewat This repon is a supplement to the Statement of vulnerabihbes. Thas document presents guidance for performing Comiderabons for the Nuclear Regulatory Commission's pro-and.reportinn 7., wsu2 *f the knowidual piant examinat*on of posed rule (10 CFR Part 54) that would estabhsh the entena

. extern 61 events (IPEEE). The guidance for reporting the results and standards goverrung nuclear power plant license renewal.

of the indwidual plant examinshon of internal events (IPE) is presented in NUREG 1335.

NUREG 1420: SPECIAL COMMITTEE REVIEW OF THE NUCLE.

AR REGULATORY COMMISSION'S SEVERE ACCIDENT

- NUREG41409:. BACKFITTING GUIDELINES. ALLISON,D P,;

RISKS REPORT (NUREG 1150)

KOUTS H J C.;

CONRAN,Jh; TROTTIER,C A Office for Ana!ysis & Evaluabon APOSTOLAKIS.G.; DIRKHOFER,E.Ha et al. Office of Nuclear i

of Operahonal Data. Director. July 1990.102pp 9008070378-Rogulatory Research (Post 860720L August 1990 90pp.

MON 2E 9009110129 55124:136 The backhtting process is the process by whr:h the U.S Nu~

In Apnl 1989, the Nucle.i Regulatory Commission's (NRC)-

cloor Regulatory Canmission (NRC) decides whetner to issue Office of Nuclear Regulato,y Research (RES) pubhshed a draft new or revised requirements or staff positions to ficer: sees of report " Severe Accident Risks An Assessment for Five U.S nuclear power rtuctot facihties. Requirements for proper justif" Nuclear Power Plants " NUREG 1150. This report updated < ex-cation of backfats and information requests are p.ovided by two

-tended and imprnved upon the information presented in the NRC rules (Title 10, Code of Federal Regulations, Sections 1974 Reactor Saluty Study 7 WASH-1400. Because the infor.

50.109 and 50,54(f)) NRC procedures include the charter of the maton in NUREG-1150 will play a signihcant role in impioment-comrr v to Review Genenc Reqwrements. NRC Manual ing the NRC's Severe Accident Pohey, its quahty and credibihty Cht + 514, and indwidual office procedures. Three types of are of critical importance. Accordingly, the Commission request-bact'

-are recognand Cost.jushhod substantial safety ink ed that RES conduct a pee review of NUREG 1150 to ensure provements require backfit analyses and findings of (1),.sbstan-that the methods, safety insights and conclusions presented are tial safety improvement and (2) lustihed costs Compliance e*

appropdate and adequate'y reflect the current state of knowl.

cephons and adequate protection exceptons do not require edge with respoct to reac'or safety. To this end. RES formed a

- findings of substantial safety improvements and costs are not special committee ;a June of 1989 under the provisions of the

- considered. However, they are stdl backfits and require docw Fcderal Advisory Committee Act. The Committee; composed of memed evaluahona to support the use of the exceptions. Infor' a group of recognaed national and international experts in nu-

- mahon requests (as opposed to backfits) require an analysis of clear reactor safety, was charged with prepanng a report reflect-the burden to be imposed to ensure that they are jusched in ing their review of NUREG<1150 with respect to the adequacy view of fne potential safety significance of the informahon re" of the methods, data analysis and conclusions it set forth. The 1

quested-repod which precedes reflects the results of this peer review.

NUREG-1411: RESPONSE TO PUBLIC COMMENTS RESULTING FROM! THE PUBLIC ' WORKSHOP ON NUCLEAR POWER NUREG-1425r WELDING AND NONDESTRUCTIVE EXAMINA-PLANT LICENSE RENEWAL.

• Office of Nuclear Regulatory TlON ISSl>ES AT SEABROOK NUCLEAR STATION An Inde-

. Research, (Post 860720). July 1990 75pp. 9006070323 pendent Review Team Report.- SPESSARD,R L: COLEY,J.;

i 54845:348,.

CROWLEY,W,; et at Ofc of the Executwe Director for Oper-On October 13. 1989, the U S. Nuclear Regulatory' Commis.

ations. July 1990. 404pp. 9008140491 54925.262 sion (NRC) issued an Advance Notice of Proposed Rulemaking in response tc. congressional concerns about the adequacy of L on nuclear power plant hcenso tenewal. The nobce presented the welding and nondestructwe examination (NDE) programs at

- the NRC's prehminary regulatory philosophy ano approach for the Seabrook Nuclear Stahon, NRC senior management estab--

r developing license renewal regulations and solicited comments fished an independent review team (IRT) to conduct an assess-on a number of technicel and po cy issues. It also announced mont Tne IRT focused on the quahty of the finished hardware u

plans for a pubhc woAshop to discuss the issues and to receive and associated records, as well as on the adequacy of tho comments and information. The workshop was he!d on Novem, overalt Quakty assuranc6 program as applied to the fabricahon

. ber 13-14,1989, in Reston, Virginia This document reports on and NDE programs for pipe welds. This report documents the the NRC's response to the pubhc comments from the workshop findings of that investigabon.

end wntten comments on the workshop topics recewed shortly NUREG/CP-0112 V01: PROCEEDINGS OF THE THIRD INTER +

'"9 ' '

h E **

• NATIONAL ATOMIC ENERGY AGENCY SPECIALISTS' MEET-l.

t in J EG C 0 09)'

ING ON SU0 CRITICAL CRAC) GROWTH. Opening session..

NUREO 1412 DRFT FC

FOUNDATION FOR THE ADEOUACY And Technical Session I.Helo At Moscow. USSR.May 14-OF THE LtCENSING DASES.A Supplement To The-Statement 17,1990. CULLEN,W.H. Materials Engineenng Associates, Inc.

• Of Considerations For The Proposed Rule On Nuclear Power Argonne Nabonal Laboratory. August

1990, 312pp.

hant License Renewal (10 CFR Part 54). Draft Report For Cnm-9009200013. ANL 00/22. 55214.324.

ment '-Office-of Nuclear Reactor Regufahon, Director #

This report is a comrulabon of papers which were presented at the Third lAEA Specialists' Meeting on Subentical Crack 070411) July 1990,100pp 9008070326. 54860125

~ Growth, held in Moscow, USSR, on May 14 17, 1990. Volume 1.

In order to hmit the Commission'a bconse renowal os case t consideration of wnether age-related degradahon hcs been ade-contains the welcoming remarks and attendance records, as quately addressed, the Part 54 rulemaking rnue m% a genenc weh as the contnbuted papers for Sossion I, covenna Corrosion hnding for all nuclear power plants that the f>nc % Jf reasor'.

'Fatmue Volume 2 contains the Contnbutsd papers for Sessions ble assu,ance of adequate protection for issuance of an op

.m it,1il, and IV, covenng Stress Corrosion Cracking Test Methods, ing hcense continue to be true at the hme of V-e re"ewa; 9-Models acd Mechanisms, and summaries of Nabonal Programs

Win Citations and Abstracts 5

in Argenhna and the United Kingdoni. Included as well are the vartous avtsrage dose commitments from the airborne pathways

-Conclusinns and Recommendations (Session V) devoicped by The btat dose commitments (froio both liquid and airbome the organi7:ng committee of the meeting. and discussed and ap-pathwayb) for each site ranged from a h:gh of 15 person rem to proved by the participants a low of 0 00tf; person rom for the vies with piants operating

- NUREG/CP.01:2 V02: PROCEEDINGS OF THE THIRD !NTER.

throughout the year with an anthmet:c mean of 1.1 person-tem.

NATIONAL ATOMIC ENERGY AGENCY SPECIALISTS' MEET.

The total population dose for au sites was estimated at 78 ING ON SUBCRITICAL CRACK GROWTH.Technica! Sessions pesom W N 150 nuhn peopW consded at 5

11. til, And IV And Recommendations And Conclusions Sesson NUREG/CH 3444 V07: THE IMPACT OF LWR DECONTAMINA-V. Held At Moscow. USSR.May 14 t 7.1990 CULLEN.W.H. Mate' TiONS ON SOllDIFICATION, WASTE DISPOSAL AND ASSO-rials Frigineenng Associates, Inc

• Argont e Natonal Laborato-CIATED OCCUPATIONA'. EXPOSURE. SOO,P.; MlUAN.LW.

ry August 1990. 219pp 9009200015. ANL 90/22. 55215:276-Brookhaven Nat!onal Laboratory. Juty 1090.74pp 9008070400.

See NUREG/CP 0112,V01 abstract BNL NUREG 51899. 54844:188L NUREG/CR 2000 V09 N6: LICENSEE EVENT REPORT (LER)

Studes were carned out to investigcte 6f simulated docon-COMPILATION For Month 01 June 1990

• 06k Rdge Nabonal taminshoh reagent / resin waste combinahons could give nse to Laboratory, July 1990. 89pp 9008140500. ORNL/NStC 200.

gas genershon and thermal excursions dunng dowatering

$4927:060-events The resutts of -temperature measurements and visual This monthly toport contains Licensee Event Report (LER; observahons are given, Some hmited work was also curried out operational informaton that was processed into tne LER data to determine " gamma triadiation of non-exchange resins causas file of the Nuclear Safety Information Center (NSIC) dunng the structural changes and losses in ion-exchange Capacity. In adUr one month penod idenhhed on the cover of the document The tron, the corrosion of various container materials in simulated LERS, frorn which this informaton is donved, are submitted to decontamination resin waste was studied in parbcular, the of-the Nuclear Regulatory Commission (NRC) by nuclear power facts of gamma irradiation were quantihed plant hcensees in accordance with federal regulations, Proco-dures for LLR reporting for revisions to those events occumng NUREG/CR,3469 V05: OCCUPA' TONAL DOSE REDUCTION AT pnor to 1984 are desenbod in NRC Regulatory Guide 1.16 and NUCLEAR POWER PLANTS ANNOTATED BIBLIOGRAPHY NUREG 0161, " Instructions for Preparation of Data Entry OF SELECTED READINGS IN RADIATION PROTECTION AND Sheets for Uconseo Event Reports." For those events occurring ALARA KHAN.T.Aa TANM; BAUM.J W.; et al Drookhaven Na-on and after January 1,1084. LERs are be ng submitted in ac.

tional Laboratory. September 1990. 93pp 9010^90020. BNL.

cordance with the revised rule contained in Title to Part 50 73 NUREG 51708. 55319160.

of the Code of Federal Regulations (10 CFR 50.73 Licensee Ono of the functons of the ALARA Center is to collect and Event Roport System) which was put ahed in tne Federal Reg.

@ssenunam Wmmahon on dose reduction at nuclear power inter (Vol 48 No 144) on July 26,1983. NUREG 1022, "LI.

plants. This is the fifth report in the senes of bibhograptwes of cenwo Event Report System. Desenplion of Systems and selected readings in radiahon protection and ALARA that the Guidelines for Reporung," provides supporting guedance and in, Center publishes perlo$calty. The abstracts in this bibliograpny format 6on on the revised LER rule. The LER summanos in this wwo selacted from proceeongs of tochrvcal meetegs journalt report are arranged alphabetically by facihty name and then research reports, searches of information data bases and re-

. chronologically by event -da's for each facility, Component, pants of published articles provided to us by the authors. The i system, keyword, and component vendor indexes follow the abstracts relate in one way or another to dose reduction at nu-summanes.. Vendors are those idenhfied by the ' utility when the clear power plants, whether it is through good water chemist y, LER form is initiated; the keywords for the compenent, system.

improvements in nut: ear matenals, better control of corroson, and general keyword indexes are us9gned by the computer robotics, and remote tooling or good operational healm physics.

umng correlation tables from the Sequence Coding and Search The report contains 278 abstracts. Subject and author indices Eystem.

are provided. The subject index covers all previous volumes in

-ttvs senes All informatron in the current volume is also available NUREG/CR*2000 V09 N7: LICENSEE EVENT REPORT. (LER) from the ALARA Center's on4ne sennce, which is accessible by -

COMPILATION For Month Of July 1990.

• Oak Ridge Natonal personal computer with the help of a modem. The preface of Laboratory. August 1990. 101pp. - 9009110143. OHNL/ NSIC-the report explains how the service may be accessed. The on-200. 55194:181.

fine service will be updated as new Infarmation is received.

. See NUREGICR 2000,V09,N06 abstract.

NUREG/CR-4624 V06: RADIONUCUDE RELEASE CALCULA7 NUREG/CR 2000 V00 N8: LICENSEE EVENT REPORT (LER)

TiONS FOR SELECTED SEVERE.

ACCIDENT COMPILATION.For Month Of August 1990

• Oak Ridge Nation-SCENAESuppleuntal Cawawns.

DEW 60 at Laboratory. September 1990, 88pp 9010090032. ORNL/

LEONARD,M.T.; CYBULSK!S,Pa et al. Battelle Memonal Instu NSIC-200 55319.255 See NUREG/CR 2000,V09,N06 abstract, tute, Columbus Laboratones. Auguw 1990.385pp.9009200004 BMb2139 55210:135.

NUREG/CR 2850 V09:. POPULATION DOSE COMMITMENTS The results of source term calculahons are reported. These DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER calculabons were performed in support of the NUREG-1150

- PLANT SITES IN 1987. DAKER,0.A. Battehe Memonal Inshtute, study. Analyses were perfortned for three plants Peach Bottom, Pacific - Northwest - Laboratory. August 1990.

187pp.

a Mark I, biling water reactors Surry, a subatmosphenc contain-9009120104 PNL 4221. 56104:282, ment, pressurued water reactor, and Sequoyah, a subatmos-Population radiabon doso commitments have been estimated phene containtnent, pressurt7ed water reactor. Complete sou<ce from reported radionuclide re%ases from commercia! power re-term tesults are presented for the following sequencesi short actors operat6ng dunng 1907. hfty year dose commitments from term station blackout with failure of the ADS system in the a one-year exposure were calculated ffra both liquid and at-Peach Bottom plant; station blackout with pump seal LOCA in mosphere releases for four populabon groups Ontant, child, the Surry plant; station blackout with a pump seal LOCA rn the teen-ager and adutt) resdng between 2 and 80 km from each Seque/ah plant; and a very small break with loss of ECC and of 70 sites This report tabulates the resUlts of these Calcula-spray recirculation in the Sequoyah plant in adoition, some par-tions, showmg the dose comtmtments br both liquid and air-tial ana!yses were performod which did not require running all of borne pathways for each age group and organ. Also included the modules of the Source Term Code Packaga Thermd-hy-for each of the si49 is a histogram showing the fraction of the draulic calculations were perforrned for tne Surry and Sequoyah total populaton w, thin 2 Po 80 kr. ar%nd each srte receiving plants to eva!uato the effects of alternat've emergency operal-

)

6 Main Citations and Abstracts in0 proceduros involving pnmary and seconda y depressuriza-t, ion rate gas suction and sorosol rnlease were also meds-

- tion. For the Surry plant, calculations woro performed of radio-ured shortly after Zr meta! was added to the melt.

nuchde transport through the pnmary system dunng accident in-i duced failure of steam generator tubes NUREG/CR 4908: ULTRASON!C INSPECTION RELIABILITY J

"^

^"

NUREG/CR-4674 VII: PRECURSORS TO POTENTIAL SEVERE Round Robin Study Of The Effects Of Personnel Proceduros, CORE DAMAGE ACCIDENTS;1989 A STATUS REPORT. Main Equipment, And Crack Charactenstics HEASLER.P,G-;

Report And Appnda A. MINARICK.J Wa CLETCHER.J.W.;

T AYLOR,T.T.; SPANNER.J C.; et al Battelle Memonal Inst:tute, COPINGER,D A_: et at Oak Ridge National Laboratory. August Pacific Northwest Laboratory. July 1930.153pp 900831017D.

1990,177pp.9009130048. ORNL/NOAC 232. 65192:068.

PNL 6196-55043.262 Thirty operational events with conditional probabilities of core A pipe inspection round robin ent! tied " Mini-Round Robin" damago of 1.0 x 10(.6) or higher occurring at commercial hght' was conducted at Pacific Northwest Laboratory hom May 1985 water reactors dunng 1989 are considerod " be procursors to through Octubor 1985. The research was sponsored by the U.S.

potential severo core damage. These a7e oescribed along with Nuclear Regulatory Commission, Office of Nuclear Regulatory associated significance estimates, categorization,. and subse-Research, under a program entitled " Evaluation and im;)rovo.

quent analyses = This study is a continuation of earlier work, which evaluated the 19601981 and 19041088 events. The ment of N,,DE Rehabihty for Inservice inspection of Light Walor g

The Mini Round Robin (MAR) measured the IGSC report discusses (1) the general rationale for this study, t2) the crack detection and string capabilities of inservice inspection selocbon and documentation of ovents as procursors (3) th$

( SI) inspectors that had passed the requirements of IED B3 02 estimabon and use of conditional probabihbes of subsequers and the EPRI srang training courso. The MRR data base was sovere core damage to rank procursor ovents, and (4) tha plant compared with an earlier Prpe inspection Round Robin (PIRR) mor'e!s used in the analysis process that had measured effective detoction prior to 1982. Comparl-HUREG/CR 4674 V12: PRECURSORS TO POTENTIAL SEVERE son of the MAR and PIRR data bases indicatt<t no differenco in CORE DAMAGE ACCIDENTS _1989 A

ST ATUS detection capability was measured for long and shvt crorks in REPORT. Appendices B

And C.

MINARICK.J.W.;

addition to the pipo trispection round robin, a human factors CLETCHERJ W; COPINGER,0.A4 et al Oak Ridge National study was conducted in conjunction with the MRR The most Laboratory August 1990. 516pp 9009130058. ORNL/NOAC-irnportant resutt of the human factors study is that the Relative

-232. 55192:245.-

Orwatin0 Charactenstics (ROC) curves provide a better meth.

See NUREG/CR 4674,V1'.a

-t.

c : fr for describing inspector performance than only POD or NUREQ/CR 4744 V03 N2: LvN>

4 EMBRITTLEW s,# point crack /no crack data.

l CAST DUPLEX STAIM b STEELS N

Lb ri NUREG/CR 5117: STEAM GENERATOR TUDE INTEGRITY PHOGRAM/ STEAM GENERATOR GROUP PROJECTfinal H P A O K.

O,HM on at o Labor o August 1990. 50pp 9009250047, ANL 30/5. 65244 021.

Project Summary Report.

KURTZ,R.J.;

CLARK R.A.;

BRADLEY.E.R4 et al. Battelle Memodai institute, Pacific North-This progress report summarizes work performed by Argonno Nabonal Laboratory on long term embnttloment of cast duplex west Laboratory. May 1090. 210pp. 0008070393, PNL 6446, 548.t6:000 stainless stools in LWR syst.ro riunng the six months from Apnl to September 1988. Characte stics of the pnmary mecha.

The Steam Generator Tubo integnty Program / Steam Genera-tor Group Project was a threo phaso program conducted for the nasrn of aging embnttlement (i.04, spinodal decomposition of for, nte) and synergistic effects of alloying and impunty elements.

U.S. Nucioar Regulatory Commission (NRC) by Pacific North-that influence the kinetics of the pnm ry mechanism are dis, west Laboratory. The main goal of the program was to provce the-NRC with valgiated information on the rchability of nondo cussed. Several secondary metallurval processes of embntile, ment, strongty dependent on the C, f( Ni, Mo, and Si content of

' structive examination techniques to detect -and size flaws -in vanous heats, are identified, information on kinehes and data on steam Denerator tubing and to determino the romaining integnty impact properties are analyzed and correlated with microstruc-of service-degradod tubin0. The program was performed in taa; charactenstics in provxfe a unified mothod of extrapolahng three phases. The first phaso irWolved burst and collapse tests accelerated-anino cinta to reactor operating conditions. Fracture and single-frequency eddy current (EC) examinations of typical toughness data are presented for several heats of cast stain, smam Deerstor tubing with precision machined flaws The goal of Phase I was to develop empirical mode!s of remaining tube less steel aged at temperatures between 320 and 450 degroes C for times up to 10,000 h. MechanicaLproperty data are ana-integnty as a function of flaw type and erzo, and to determino lyzed to develop the procedure anc :orrelations for predicting the capabihty of EC inspection methods to detect and sue tubo

'the kinetics and extent of emurittlement of reactor components degradation. In Phase li, a smaller number of specimens with from known material parameters. The method and examples of the same flaw types were investigated, but tube specimens

..ostamating the impact strength and fracturo toughness of cast were degraded by chemical means rather than ma0hining meth-components dunng reactor servico are described. The lows]r, ods This approach was used to better simulato the irregular ge<

bouM Woos of impact strength and fracture toughness for cast ometry of servico induced degradabert in the final phase of the sit - a

'els at LWR operating temperatures are defined program, the retired 4 tom-service Surry 2A Steam Generator was used as a test bed to investi0 ate the reliabihty of Inservice NURiat? r94: EXPERIMENTAL RESUL1S OF CORE CON-EC inspection equipment, personnel, and procedures, and as a -

CHt.! -,iERACTIONS USING MOLTEN -STEEL WITH ZlR-source of servico degraded tubos for further validating the om.

CONIUM, COPUS.E.R : BLOSE R.E.; BROCKMANN,J.E.; et at pincal equations of remaining tube integrity l_

. Sandia National Laboratones July 1990, 386pp p008070412 l

SAND 86-2630 54849:001, HUREG/CR 5254: DIAS IN PEAK CLAD TEMPERATURE PRE-Four exponments were performed in order to evaluate the ad-DICTIONS DUE TO UNCERTAINTIES IN MODELING OF ECC citional effects of rtreonium makt oxidabon on core debris inter, BYPASS tND DISSOLVED NON CONDENSABLE GAS PHE-lJ actions with limestone concrete using molt 9n stainless steel an NOMENA. ROHATGI,U.Sa NEYMOTIN.L.Y.; JO,J.; et at Grook-the core debns simulant. The OT D. OT E, SURC 3 and SURC-haven National Laboratory. September t 990.

175pp.

3A expenments oroded between 10 and 33 cm of hmestone 90t0090047 BNL NUREG 52108 55322:253.

I concrete during sustained interactions wNch lasted 35 to 120 The U,S Nuclear Regulatory Commission (USNRC), its con-manctes Mett pool temperatures dunng the tests ranged from tractors and consultants have developed a methodology for 1900 K hefore frconium addition to 2100 K dunng the rircorv-ovaluabog Codo Scahng. Applicabihty and Uncetainty (CSAU).

um-steet concrete phase of the tests Largo increases in cro.

The CSAU method has been demonstrated by applyirig it to the i

h Main Citations and Abstracts 7

TRAC-PFI/ MODI, Version 14,3 coda and its analyms of a ground informateon is supphed in the introduction and Appendix Large Orcak Loss of Coolant Accident (LDLOCA) for a Wesbng-A.

NUREG/CR 5373: A DEMONSTRATION EXPER! MENT OF d tc s iv into e ff nt p a yD STEAM-DRIVEN. HIGH. PRESSURE MELT EJECT:ON The down Refill and Reflood. There are two dishnet peak clad tem.

potatures (POT), one en the Dlowdown Phase and one in the HIPS-10S Test. ALLEN.M D; NICHOLS.R T.; PILCH,M. Sandia Reflood Phase. The Refloc Phaso PCT is affected by the phe.

National Laboratonos. July 1990 92pp. 9008310209 SAND 89-113E E41170.

nomena rotated to Emergency Core Cooling System (ECCS) in the downcomer and lowor plenum of the reactor vessel. Thss A steam blowdown test was performed at the Surtsoy Direct report describes a general method for estimating the biases in Heahng Test Facanty to test the steam supply system and burst the Reflood Phaso PCT from systematic errors (biases) assoc 6-aaphragm arrangement that will be used in subsequent Surtsoy aled with the modotting of the ECCS and dissolved nitrogon, Duect Containment Heating (DCH) exportments. Following suc-and the apphcation of this method The bias in the Reflood cessful comptolion of the steam blowdown test, the HIPS-10S Phase PCT due to the uncertainty in the existing code models (High-Prossure Melt Streaming) experimont was conducted to for ECCS related phenomona is 19 degrees K (-34 degrees F).

demonstrato that the technology to perform steam-dnven, hiOb-The bias in the PCT due to the lack of modelling of dissolved pressure mett election (HPME) experrnents had boon success-N(2) in the code is estimated to bo 0 9 degrees K (17.8 degrees fuhy developed in additon, the HIPS 10S exponment was used FL The code prediction for PCT is conservatve if the bias is to assess techn# ques and instrumoniation designed to create riegatsve, and nonconservative if the been is positive The bias D WW #9 d "" D #E NU"8-estimated hvo is based on full scato data from the Uppe' NUREG/CR 5374:

SUMMARY

OF INADEQUATE CORE COOL-Plenum Test facility end is unaftocted by the scale destortions-ING INSTRUMENTATION FOR UNITED STATES NUCLEAR POWER PLANTS.

ANDERSON.J.L; HAGEN,E.W.;

NUREG/CR 5280 V01: AGE RELATED DEGRADATION OF WES, 11NGHOUSE 480NOLT CIRCULI DREAKERS. Aging Assess-MORELOCK,T.C. Oak Ridge National Laboratory. July 1990, 197pp.9008070334. ORNLITM 11200. 54850.027.

mont And Recomrnendaaons For improving Dreaker Rehabildy.

SUBUDHl Ma SHIER,W.; MACDOUGALL.E. Drookhaven Nate This report summarizes a review of inadequate Coro Cochng Instrumentabco-installed in U.S. nuclear power plants in re-al Laboratory. July. 1990, 90pp. 9008070370. DNL NUREO.

sponso to tM reqwernents of WRM737, Qankaton of

$2178 54845:100 An aging assessment of Washnghouse DS-sones low-voltage W Acton Man Roquvements, and related orders The review includes dotcriptions of genonc systems developed by Westing-

- air circuit breakers was performed as part of the Nucioar Plant

- Agin0 Research (NPAR) program. The objectives of this study house and Combustion Engineeny as well as plant specific re-views of each pressurized water reactor installation. Perform-

.aro to characterim ago.colated degradabon wrthin the breaker ance charactonstics are discussed, including feedback from assembly and to identify maintenance practicas to mibgate their effects. Since this study has been promulgated by the failuros piani pws nnd c neemg sta aton, opwauonal apenom of the reactor trip bre6kors at tho McGuire Nuclear Staten in and operator acceptance. An ovaluabon of boiling water reactor July 1987, results relating to tho wolds in tho breaker polo lover s$ ems b ocW welds are also discussed. The design and operahon of DS-206 NUREG/CR 5385:.lNITIAL ASSESSMENT Of THE MECHA.

and DS4il6 breakers wore reviewed. Failure data from various N!SMS AND SIGNIFICANCE OF LOW TEMPERATURE EM-nabonal data bases were analyzed to identfy the predominant BRITTLEMENT OF CAST STAINLESS STEELS IN LWR SYS-

'. failure modes, causes, and mechansoms Additional operat ng TEMS CHOPRA,0.K.; SATHER.A. Argonno Nabonal Laborato-experiences from one nuclear station and two industrial break-ry. August 1990. 252pp. 9000040085. ANL 89/ !7; 55048 043.

ergorvice comparves were obtained to devesop aging trends of This report summanzes work performed by Argonne Nabonal vailous subcomponents. The. responses of the utihbes to the Laborator on longtorm embntilement of cast duplex stainless NRC Bulletin 88-01, which discusses the center pote' lover steels in ' LWR systems. Meallurgical charactenzahon and me-wolds, were analyzed to assess the final resolubon of f ailures of chanical property data from Charpy4mpact, tensile, and J R welds to the reactor inps -

curve tests are presented for several expenmental and commer-cial heats, es well as for reactor agod CF 3 CF 8, and CF.8M NUREG/ChdP97: CLOSEOUT OF IE BULLETIN 83 05 ASME cast stainiosa steeli The offects of matenal vanables on the NUCLEAR CODE PUMPS AND SPARE PARTS MANUFAC-embnttlement of cast stainless stools are evaluated Chemical TURED BY ' THE HAYWARD TYLER PUMP COMPANY, composinco and femte morpnology strongly affect the c* tent FOLEY,W JJ Ot'ANRS4 HENNICK,A. PARAMETER. inc.

ano kinebcs of emonttlement In general, the low-carbon CF 3 August - 1990. 33pp. 0009180017. PARA WTER IE188.

stainless steois are tno most resistant and the molybdenum-55214.290.

centa.ning high-carbon CF 8M sta:nless steels are most suscop.

Documentation is provided in thrs report to close IE Bulietin tible to embrittlement. The microstructural and mechanicabprop-83-05 regarding ASME nuclear code pumps and spare parts orty data are analyrod to estabhsh the mechanisms of embnttle-manufactured by the Hayward Tyler Pump Company (HTPC) ment. The procedure and correlations for prodichng the impact The bulletin was bsuod (t) to alert holders of ooerahng licenses strengtn and fracturo toughness of cast components during re-and construction permits of nuclear power plants that HTPC actor sevice are desenbod The lowet bound values of impact failed to implement effectivoty their quality assurance (OA) pro' strength and fracture toughness for lovetemperature aged cast gram from 19?? to 1081 and (2) to require affected util:ttes to stainless elect are defined.

take acton to resolve the potenbal for failure of the subject pumps and thotr spare parts. Evaluation of uthty responses and NUREG/CR 5395 V11: MULTILOOP INTEGRAL SYSTEM TEST NRC/Rogion inspection reports shows that reliability of the af-(MIST): FINAL REPORT. MIST Phase IV Tests. GEISSLER.G.O.

facted pumps was ensured by means of procedures and por-Dabcock & Wncox Co. August 1990. 528pp. 9009210290, EPRl/

formance tostng of the pumps as required by the bulletin NP-6480. 55237:169.

Based on the evaluabon. in accoroance with sp+cific cntena, The Mulhtocp Integral System Test (MIST) is part of a multe the bulletin is clcsed for 116 (98%) of the 118 facisities to which phase program started in 1983 to address smalbbreak loss-of-it was issued for achon and which were not shut down irdele coolant accidents (S8LOCAs) specific to Babcock and Wilcox nitely or permanently at the time of issuanco of this report. A designed plants. MIST is sponsored by the U S. Nuclear Regu-follow up stem is proposed for the two facihttes with open bulle-laton Commisson, the Babcock & Wdcox Owners Group, the t n status, Based on favorable results. a conclusion is presented Electric Power Research Instituto, and Babcock and Wilcot to indicate that the bulletin comerns havo boon resolved Back-lho unique features of the Babcock arv1 Wdcox destgr..,mcifb

.v n

8 Main Citations and Abstracts i

ca4y the hot leg U bends and steam generators. prevented the NUREG/CR 5451: CR ACK-ARREST BEHAVIOR IN S N WIDE use of costing integrst system data or costing integrai facetica PL AT E S Or LOW. UPPER SHELF BASE METAL TESTED to address the thermal-hydrauhc SBLOCA questions MIST and UNDER NONISOT HERMAL CONDITIONS. WP-2 SERIES two other supporting faelites were specifica!!y designed and NAUS,D J : KEENEY WALKER, BASS B R.; e d Oak Ridge constructed for this provas and an cos5ng fac*ty--the Once Nabonal Laboratory August 1990 299pp 000t * /0076 ORNL.

Throagh integral System (OTIS)~was also used Data from 0504 5520 0163 MIST and the other facihties will be used to benchmark the ade-Six moe-piate cracoanest tests (WP 2 bones) are d$ cussed quacy of system codes, such as RELAP5 and TRAC, for pre-in this repod Each test utAzed either a 1 x 1 x 01 m or a 1 x 1 dicting abrermat plant transients The MIST program is reported x 015-m thick sinte edge notch specimen (alw e 0 2), f abri-in 11 volumel The program is summanzed in Volume 1; Vob cated from a low-upper-shelf base matenal, that was subjected umes 2 through 8 desenbo groups of tests by test type, Volume to a hnear thermal gradient along the plane of crack propaga-9 presents inter group compansom Volume 10 provides com tion The tests were conducted at the National Institute of pansons between the calculations of RELAP5/ MOD 2 and MIST Standards and Technology and were designed to provide frac-observations, and Volumn 11 presents the later Phase 4 tests ture toughness measurements at temperatures approaching of The Volume 11 pertains te M:ST Phase IV tests performed to atove the onset of the Cha'py upper shett regime, in a nsing investigate nsk dominant transients and non-LOCA events toughness region, and with an increasing dnving forr.e Results obtained from these tests have produced crack arrest tough-NURE0/CR-5395 V11 AD: MULTILOOP INTEGRAL SYSTEM ness values well above the limit recognried by the current TEST (M:ST) FIN AL REPORT MIST Phase IV T ests ASME gu*dehnes (220 MPa Vm) with arrests occuenng at up to GEISSLER G O. Babcock & Wilcor Co. August 1990 273pp 102 degrees C above the matenal (DW)NDT (60 degrees C) 9009210229 EPRl/NP-6480 55233.202-The fracture data support- (t) use of fructure mechanics con-The Multiloop Integral System Test (MIST) is part of a mutt" cepts to ana'y2e cleavage run arrest events. (2) treatment of phase program started in 1983 to address small-t:reak loss-of-cleavage and ductile fracture modes as separate events. and coolant accidents (SULOCAs) specific to Babcock and Wilcox (3) fact that cleavage arrest occurs above the ASME fimit designed plants MIST is sponsored by the U S Nuclear Regu-latory Commission, the Dabcoef. & Wilcox Owners Group, the NUREG/CR 5453 V05: BACKGROUND INFORMATION FOR THE Electne Power Research institute, and Dabcock and Wilcox.

DEVELOPMENT OF A LOW. LEVEL WASTE PERFORMANCE The unique features of tne Babcock and Wilcox design. Specih-ASSESSMENT METHODOLOGY. Computer Code implementa cally the hot leg U bends and steam generators, prevented the tion And Assessment.

KOZAK,M W.;

CHU.M.S Y.:

use of existing integral system data or costing integral facWties MATTINGLY,P. A.; et al. Sandia National Laboratones. August to address the thermathydrauhc SBLOCA questions. MIST and 1990.10$pp 9008310184. SAND 89-2509 55044:055.

two other supporting f acsties were specifically designed and This report documents the implementation and assessment of constructed for this program. and an existing facility the Once computer codes for a low level waste performance assessment Through Integral System (OTIS)- was also used Data from metnodology Computer codes and analytical solutions are im-MIST and the other facihties will be used to benchmark the ade-piemented for grounSwater flow and transport analyses, quacy of system codes, such as RELAP5 and TRAC, for pre-source-term analyses, surface water transport analyses, air-dicting abnormal plant transients The MIST program is reported transport analyses, food chain ana!yses, and dosimetry analy-in 11 volumes The program is summan7ed in Volume 1; Vol-Ses The capabikty has been retained to perform either simple umes 2 through 8 desCnbe groups of tests by test type; Volume or more comphcated analyses of the source term and ground-9 presents inter group compansons Vo'ume to prowdes com-water transport asoccts of the performance assessment. The pansons between the calculations of RELAPS/ MOD 2 and MIST s mple approacnes consist of analytical and simpie numoncal observations, and Volume 11 presents tec later Phase 4 tests analyses that are appropriate for relatively simple conceptual Volume 11 addendum portains to MIST natural circulat:on models. For fully muttrdimensional or transient problems, more

~

comphcated numencal solutions are recommended Details are NUREG/CR 5448: AGING EVALUATION OF CLASS 1E BATTER.

given of the recommended analytical methods, together with IES SEISMIC TESTING EDSON,J L EGSG Idaho, Inc. (subs sensitmty analyses that demonstrate important aspects of the of EG&G. Incl August 1990. 233pp 9008310221. EGG-2576.

solutens The implementation processes for the more comph-

$5042,133.

cated computer codes and those problems that arose dunng This report presents the results of a seismic testing program implementat:en are discussed. Finally, a companson is gwen on naturally aged class IE butanos obtained from a nuclear between the simple and comphcated ground-water transport plant The testing program is a Phase il actmty resulung from a analyses for a simple conceptual raodel.

Phase I aging evaluation of class 1E battenes in safety systems NUREG/CR 5461: AG!NG OF CABLES, CONNECTIONS, AND of nuclear power plants, performed previously as a part of th ELECTRICAL FENETRATION ASSEMBLIES USED.N NUCLE.

U.S Nuclear Regulatory Commission's Nuclear Plant Aging Re-search Program and repovted in NUREGrCR 4457. The pomary AR POWER PLANTS JACOBUS.M J. Sandia National Labora-tones July 1990.

81pp 9008080195. SAND 89-2369 purpose of the propam was to evabate the seismic ruggedness of naturally aged battenes to determine if aged battenes could

$4871.328.

have adequate electucal capacity, as determined by tests rec.

This report examines effects of aging on cables, connectoi S, ommended by IEEE Standards, and yet have inadequate seis.

und containment electncal penetration assembhes (EPA.d mic ruggedness to provido needed electnca! power dunng and Agmg is dehned as the cumulative effects that occur to a ccm.

after a safe shutaca n earthquake (SSE) event. A secondary ponent with the passage of time. If unchecked, these ef'ects purpose of th6 program was to evaluate selected advanced sur.

can lead to a loss of function and a potential 'mpa'rment of veillance methods to riotermine if they were hkely to be more plant safety Ms study includes a review of component usNe sensitive to the ayng degradation that reduces seismic rugged-in nuclear power plants: a review of some commonly used som-ness The program used twelve battenes naturally aged to ponents and tneir matenals cf construction; a rewew of the about 14 years of age in a nuclear facihty and temed them at stressors that tne comoonents might be exposed lo in both four defc ont seismic levers representative of the leveu of pos-normal aod accident environments; a compilaton and e<ata-sable earthquakes specAed for nuclear plants in the United tien of industry failure data. a discusson of cornponent f Mure States Seismic test'ng of t^e battenes d.d not cauw any loss trodes and causes and a boel descnetior' of current industry of electncal capacity teshng and maintenance practices

l l

Main Citations and Abstracts 9

NunEG/CR 5515: LIGHT WATER REACTOR PRESSURE ISOLA.

and stress rupture tests were distnbuted to the participating TION VALVE PERFORMANCE TESTING, NEELY,H H :

OECD laboratones Two tna! specimens cut from a plate of A36 JEANMOUGIN,N.M : CORUGEDO J.J. Energy Technology Enoi.

plain-carbon structura! steel by PCI Energy Systems using metal neering Center. July 1990.111pp. 9008070338. ETEC 88 01, disinwgrabon machining (MDM) were examined metallographb MB60:Old celly.

The Li0ht Water Reactor Vatve Performance Testing Program was instated by the NRC to evaluate leakage as an indication of NUREC/CR 5528: AN ASSESSMENT OF BWR MARK 11 CON-valve condition, provide input to Section XI of the ASME Code, TAINMENT CHALLENGES, FAILURE MODES, AND POTEN-evaluate motor signature testing to measure valve operability, TIAL IMnROVEMENTS IN.ERFORMANCE. KELLY.DL; ovaluate acoustc emission monitonng for condition and degra.

JONES,K h : DALLMAN.R.Ja et al EGAG Idaho Inc (subs of dabon and in. service inspection techniques Six typical check EG&G, Inc ) July 1990 317pp 0009040046. EGG-2593 and gate valves were purchased for testing at typical plant con.

55049 270 ditions (550 F at 2250 psg) for en assumed number of cycles This report assesses chaftenges to BWR Mark 11 containment for a 44 year platit hietime. Tests revealed that there were var.

integnty that could potentially arise from severe accedents. Also sances between-the test results and the present statement of assessed are some ptential improvements that could prevent the Code; however, the tesung was not conclusive The lifecycle core damage or contairiment failure, or could natigate the con-tests showed that high tech acoustic emission can be utilized to sequences of such failure by reduc ig the release of fission trend email leaks, that specific motor signature measurement on products to the environment. These challenges and iroprove-gate valves can trend and indicate potential failure, and that in, monts are analyzed via a timed quantitativo nsk/ benefit anaty.

Service inspection techniques for check valves was shown to be sis of a genenc BWR/4 reacter with a Mark 11 containment.

both feasible and an excellent preventive maintenance indice Point estima's frequencies of the dominant core damage se-tor. Lifecycle tesung performance here dd not cause large quences are obtmed and simple containment event trees are valve leakage typical of some plant operahon. Other testing is constructed to evaluate the response of the containment to required to fully understand the implicahon of these results and these severe accident sequences The resulting containraent re-the required program to funy implement them lease modes are then binned into source term release catego.

n 5, whsen provide inputs to the consequence analysis The NUREG/CR 55t9 V01: AGING OF CONTROL AND SERVICE AIR uw c ns e nce ana m us M M cons W an COMPRESSORS AND DRYERS USED IN NUCLEAR POWER overall base case nsk proble_ Potential improven:ents and son-PLANTS. MOYERS,J C Oak Ridge National Laboratory. July "9

1990.129pp 9008070332 ORNL 6607. 54850.224 a gamMMWMhm@M This report was produced under the Octoction nl Defects and sensitivity cases are examined in order to evaluate the impact Degradabon Monitonng of Nuclear Plant Safety Equipment ele.

mont of the Nuclear Plant Aging Research Program. This ele-of phenomenological uncertainties on the final rosults ment includos the identi cation of practical and cost effective NUREG/CR 5532: A PERFORMNCE ASSESSMENT METHOD-fi

- methods for detecting. monitonng and assessing the seventy of OLOGY FOR LOW LEVP WASTE FACiUTIES. KOZAK.M W.;

time dependent degradation (aging) of control and service air CHU,M S Y.: MATTINGiY,p A Sanda National Laboratories.

compressors and dryors in nuclear power plants. These meth-July 1990. 85pp. 9006C 4187. SAND 90-0375 54871.2G ods are to provide capabihties for estabhshing degradation A performance assessment methodology has been developed trends pnot to failure and developing guidance for effective for use by the U.S. Nuclear Regulatory Commission in evaluat-mantonance. The topics of this Phase I assessment report are ing hconse applications for low-level waste disposal facihties.

failure modes and causes resulting from aging. manufacturer.

This report provides a summary of background reports on the recommended maintenance and surveillance practices, and development of the methodology and an overview of the measurable parameters (including lunctional indicators) for use models and codes selected for the methodology The overview in assessing operational readiness, establishing degradation includes discussions of the philosophy and structure of the trends, and detechng incipient fa; lure. The resulta presented are methodology and a sequential orocedure for applymg the meth-based on Informahon derived from operating expenence odology; Discussions are provided of models and associated records, manufacturer supphed information, and input from plant assumptions that are appropriate for each phase of the method-

- operatort For each failure mode, fadure causes are hsted by oiogy. the goals of each phase, data required to implement the sub-component, and parameters potentially useful for detecting-models, signiftcant sour es of g.acertainty associated with each degradation that could toad to failure are identified.

phase, and the computer codes used to implement the appro NUREG/CR-5524 V01: TMi 2 VESSEL INVESTIGATION pnate models. In addition, a sample demonstration of the meth-PROJECT (VIP)

METALLURGICAL - PROGRAM Project odology Is presented for a simple conceptua: Model Report. January September 1989, DIERCKS.D R. Argonne Na-NUREG/CR 5542+ MODELS FOR ESTIMATION OF SERVICE tional Laboratory. March 1990. 43pp. 9008090018. ANL90/2.

LIFE OF CONCRETE DARRIERS IN LOW LEVEL RADtOAC-M872.04 TIVE WASTE DISPOSAL WALTON J Ca PLANSKY, lea This report summan2es the work performed by Argonne Na tional Laboratory on the TMb2 Vessel Investigation Protect (VIP)1 SMITH.R W. EG&G Idaho, Inc. (subs of EG&G inc L Septem-bor t990. 52pp. 9010090060. EGG 2597. 55310.04J.

Metallurgical Program during the nine months from the initiatior' Concrete barriers will be used as intimate parts of systems for of the program in January 1989 through September 1980-isolation of low level radivactive wastes subsequent to disposal.

Durrg the reporting penod, arenive matenal for the program This work reviews mathemahcal models for estimating degrada-was obtained from the lower head of the cancelled Midland nu-tion rate of concrete in typscal service environments. The clear reactor in Midland, Mi, jn the form of four plates -Chemmal models considered cover sulfate attack, reinforcement mro-analyses and hardness measurements were performed on sam' sion. calcium hydronde teaching, carbonatton, freeze / thaw 8"J pies from the four plates, the as received microstructure was cracking Additionally, fluid flow, inass transport, and geocNmr characten&d, and a tentative determination of rolhng direction cal proporties of concrete are bnefly reviewed Example calcuta-was mado. Initial resutts trom heat treatment expenments on tions in91uded illustrate the types of predictions expected of the the archive material indicate that those regions of the tmh 2 models.

matenal where the maximum temperature exceeded 727 de-grees C should be readily ideNifiable on the basis of micros-NUREG/CR 5552: AN OVERVIEW OF THE LOW UPFER SHELF a

tructural observations A senes of round-robin mechanical tests TOUGHNESS SAFETY MARGIN ISSUE MERKl E.J G. Oak and microstructural studes on the as-rece-vW archive matenai Rdge National Laboratory August 1990 62pp. 900904003).

was developed, and specimens and spevn <t' Nanks for tensile ORNL/ TM411314 55052:260.

10 Main Citations and Abstracts j

The low upper shelf toughness issue has a long history, be-are largely based on oxisting information obtained from the nu-ginning with the choice of matenals for tne submerged arc weld-clear industry and the NRC's severe accident research pro-

- eng process, but also potentially involving the use of A302 D grams. Additional analyses related to operator actions were per-piate. Cntene for vessels contarning low upper shelf matenals formed and are presented in the append 4ces have usualiy been expressed in terms of the Charpy upper shelf impact energy. Although these critena have had several differ.

NUREG/CR 5568 V01: INDUSTRY BASED PERFORMANCE IN.

ent bases, the range of limit:ng values ()r wal! thicknesses ap-DiCATORS FOR NUCLEAR PONER PLANTS Phase 1 Report.

prohching ryne inches has remained between 40 and 50 ft.lbs June 1989 February 1990. CONNELLY,E.M ; VAN HEMEL,S 8.

Values for msels with thinnor walls and/or only circumferential Communications Technology spphcations. Inc. HAAS.P.M. Con, low upper shelf wolds could be less A decision on critena to be cord Associates, Inc. Jutf 1990 99pp. 9008090024. CTA incorporated into the ASME Code is approaching Choices to be 900215 025. 54B7c094.

made concern the method for estimating the decrease in upper This report presents the resuus of the first phase of a two-shelf impact energy, flaw geome"y for circumferential welds, phase study, performed with the goal of developing indirect statistical significance of toughnest values, the choice between (leading) indicators of nuclear power plant safety, using other in.

J(D) and J(M) reference pressure, safety factors, and the inclu.

dustnes as a model it was hypothesized that other industnes sion of instabihty pressure calculations by rneans of R curve ex-with similnr pubhc safety concerns could,.erve as analogs to trapotabon. This report presents a comprehenstve overvew of the nuclear power industry Many process !.1dustnes have many the issue, including history and recommendations for expediting more years of oporating exponence, and many more plants than ris resolut# ort the nuclear power industry, and thus should have accumulated mu sa y a o

a sch NUREG/CR 5554: RECOMMENDATIONS FOR THE SHALLOW.

a vanety of potential industry analogs and chose a chemical /

CRACK FRACTURE TOUGHNESS TESTING TASK WITHIN petrochemical manufactunng industry as the primary analog for THE HSST PROGRAM. THE!SS.T.J. OA Ndge National Late furtMr study. Information was gathered on safety programs and ratory September 1990 55pp 9010090068. ORNL/TM.t l509 indicators tai the chemical industry, as well n in the nuclear 55318:34 "

power industry. Frameworks were selected for the development Recommendations for the Heavy Sochon St'el Technology of indicators which could be transferred from the chomica; to Program) investgation into the influence of crack depth on the the nuclJar power environment, and candidate sets of direct fracture Lughness of a stent under conditions prototypic of and indirect safety indicators were developed. Estimates were those in a reactor pressure vessel are included in this report-made of the+ avadability and quailty of data in the chemical in-The pnmary goal of the shallow-crack protect is to invesiigate dustry, and plans were developed for further investigating and the influence of crack depth on fracture toughness under condi-testing it7se candidate indicators against safety data in both tions prototypic of a reactor vessel, A timited data base of frac ~

the chemical and nuclear power industries in Phase 2, ture-toughness values will be assembled using a beam speci-men with a depth of 100 mm (4 in.) using prototypic reactor NUREG/CR-5572: AN EVALUATION OF THE EFFECTS OF -

vessel niatenal Results of the investigation are expected to im-LOCAL CONTROL STATION DESGIN CONFIGURATIONS ON prove the understanding of SMllow-flaw behavior in pressure HUMAN PERFORMANCE AND NUCLEAR POWER PLANT vossols, thereby providing more reakstic information for app 4ca-RISK O'HAR A,J ; RUGER.Ca HIGGINS.J.: et al. Brookhaven bon to the pressun2nd thermal shock issues-National Laboratory. September 1990. 71pp. 9009250057. BNL-NUREG/CR-5556: REVIEW OF CURRENT LITERATURE RELAT-NUREG.52236. 55N3 312.

ED TO GENERIC SAFETY ISSUE 15 LIPINSKl R E.:

A human facurs analysis was performed to assess how iden-GARNER R.W. EG&G Idaho, Inc. (subs. of EG&G. Inc4 July tified upgrades te local control stations (LCSS) in nuclear power -

1990. 20pp 9008080197. EGG 2598. 54881:320 plants affect both human performance and plant nsk. Upgrades Recent evaluahons of surveiliance samples in the High Flux in the design of individual control panels and overall improve-Isotope Reactor at the Oak Rdge Natonal Laboratory led to ment of functional centrahration were considered The analysis the conclusion that the embattlement rates of several reactor rrethodology was accomphshed in four stages 'First, a list of pressure vessel (RPV) steels may be greater (Mn onginally an.

LCS human engineenng design deficiencies was developed t!cipated, in June 1987, the Adsisory Commit'ee on Reactor usang data collected from a vanety of sources including visits to Safoguards requested that the U.S Nuclear Regulatory Com.

nuclear power plants, From these data, a set of potential up-mission investigate the consequences of embrittlement of RPV grades were defined to correct the dnficiencies. Second, the ef.

supports This report summan2es the current hterature related lects of the upgrades on humen error probabihties (HEPs) were to these studies, evaluates their ceabution toward resolving determined using a computer basad methodofogy for soliciting Genenc Safety issue 15 concoming matenal embnttlement, and expert judgement. Third, the HEPs were nropagated through a recommends any further action considered appropnate. This plant probabikstic nsk assessment (PRA), and new core melt review also contains a short discussion of the uses of structural frequencies were estabhshed A preliminarv, scoping value-mechantes and tracture mechanics to analyze embnttlement.

impact assessment was performed to evaluate the regu!atory need for further review rJ possible action to improve the human NUREG/CR 556h PWR DRY CONTAINMENT ISSUE CHARAC-f actors engineenng aspects of local control stations. The results TER12ATION. Y ANG.J,W. Brookhaven Natiora! Laboratory-indicated that implementation of both types of upgrades would August 1990 204po 9009040028 BNL-NUREG-52234.

irnprove human performance and lower risk, but tr at r

'ho v

55040.311.

panel design 'mprovements would be cost beneficial.

Sevore accident issues have been characterived for pressur-12ed water roactors with largo dry containment

• A descript on of NUREG/CR 5575: QUANTITATIVE ANALYSIS OF POTENTIAL PWR dry containment performance under severe *cident coro PERFORMANCE IMPROVEMENTS FOR THE DRY PWR CON.

ditions rs provided Reviews and escussions of esty contain.

TAINMENT KEL Y.D L : PAFFORD.D.J.; SCHROEDER,J A.; et mont fmfure due to direct containment heahng (DCHL in-vessel al EG&G Idaho. Inc. (subs. of EGaG, Inc.) August 1990 steam explosions, hydrogen burns and steam spikes, late con-163pp 9009200008 EGG-2602. 55232.035.

' tainment falute durs to Gradual overpressun2ation and basomat This report calculates the nsk beneht associated with poton-melt-through, and containmerit bypass (interfacing evstem9 taal rartormance improvements for the large dry pressurized LOCA) events are included An assessment of potente im-water reactot (PWR) containment. The anafysis is based on the provements such as RCS depressunzabon, reactor caWy is June 1989 draft NUREG 1150 results for the Zrn commercial flooding. hydrogen coraroi, contanment ve ring and accident nuclear reactor. Simphfied containment event trees and the management strategy a presented The tr wew and discumon large acodent progressen event trees from draft NUREG.t 150 l

E

~-

~

~. - -

Main Citations and Abstracts 11 are used to evaluate the effects of potential improvements on Module of CARES and reprewnts the Us.r's Manual. Volume 1 the response of the 200 Containment to dominant severe acci-concentrates on the theorebcal bes of the system and pre-dent sequences Source terms are generated parametncally sents modeling assumptior.s and hmitabons as well as sotation using the ZlSOR code and offsite consequences are calculated schemes and algonthms of CARES Solutions and results from with the MELCO9 Accident Conseque%c Code Sys. tem a set of sample problems are published as Volume 3 of the (MACCS). These results give point estimates of the risk redoc-CARES ilocumentation tion assocated with each containment improvement 6dentified by Brookhaven Nabonal Laboratory in their draft issues Charac-NUREG/C+5588 V03: CARES (COMPUTER ANALYSIS FOR tenzation Report RAPID Ei/ALUATION OF STRUCTURES) VERSION 1.0.Seit.mic NUREQ/CR 5583: PREDICTION OF CHECK VALVE PERFORM.

Module.S smple Problems.

XV,J.;

PHILIPPACOPOULO; ANCE AND DEGRADATION IN NUCLEAR POWER PLANT MILLERL A.; et al. Brookhaven National Laborator, July 1990.

SYSTEMS WEAR AND IMPACT TESTS Final 14 %.9008070359. DNL NUREG 52241. 54848.215 Report. September 1988 Apnl 1990. KALSI.M S; HORST,C.L.;

Dunng FY's 1988 and 1989, Brookhaven National Laboratory WANG.J K.; et al. Kalsi Engineering. Inc. August 1990.11Ppp, (ONL) developed the CARES system (Computer Anahsis for 9009070007. KEl 1656 55070:010.

Rapid Evaluation of Structures) for the U.S. Nuclear Regulatory Check vane failures in nuclear power pg4 ha e led to Commission (NRC) CARES is a PC software system which has safety concerns as well as extensive damage ano ioas of plant been designed to perform structural respotise computabons availabit'ty in recent yests Swing check valve 6nternan may es, similar to those encountered in heensing rev;aws of nuclear perience premature degradation (! the disc is not firmly held power plant structures. The documentation of the Seismr open against its stop and significant flow disturbances are Module of CARES consists of shree volumes. Thit report repre-present upstream w;tNn 10 pipe diameters. The objective of the sents Volume 3 of the three volume documentation of the Seis-current Phase 11 research was to develop and expenmentally mic Module of CARES It presents three samole problems type-venty a quantitatrve methodology for predictmg swing check cally encountered in the Soil Structure Interaction analyses. The valve performance and the degradation of internals caused by theoretical bases, modehng assumptions and hmitations as well hinge pin wear or disc stud irnpact. Phase I research had fo.

as solution schemes and,algot4hms of the Seismic Mdule o' cussed on investigating.the stabihty of the swir:0 check vane CARES are prven in Volume 1. The Users Manual is pubiched disc at different flow velocities for a wide vanety of upstream as Volume 2.

flow disturbances located within 10 pipe diame'ers of the check NUREG/CR 5589: ASSESSMENT OF ICE CONDENSER CON-vaNo Vane performance predictions based on methodology developed as a result of Phase I and ll research correlate well TAINMENT PERFORMANCE ISSUES. NOURDAKHSH.HP.

with actual vane operating history at plants. The conservahve Brookhaven National Laboratory. July 1990. 57pp 9008070396.

p*1ebnes provided by this methodology, tempered and refined BNL NUREG 52242. 54844:259.

ctual portormance history and int > grated with preventive Vulnerabilities of an ice-condencer containment to challenges s

itenanct aCliVilles, have the potential for $$Crdficantly im-that Could anse from sevefe accidents have been assessed.

F puing the overall reliabihty of check vaives in nuclear power The phenomenological issues associated with containment plants.

challenges have buen evaluated. A number of containtnent im-pr vements which have the potential lc -tigate severe acci-NUREG/CR 55b8 Vol: CARES (COMPUTER ANALYSIS FOR dent challenges have been evaluated. Thm report is intended to RAPID EVALUATION OF STRUCTURES) VERSION 1,0 Seismic pr vide a comprehensive statement of the relevant issues that Module.Theoret cal Manual.

XU,J - PHILIPPACOPOULO.

MILLER CA: 4.i at Drookhaven Naborbl Laboratory. July 1990; can be used in the NRC staff s evaluahon process and by the utihties dunng their individual plant examinations (IPEst 80pp.9008070356. DNL NUREG 52241. 54644:316.

Dunng FY's 1908 and 1989 Brookhaven Nabonal LaboratoW NUREG/CR 5591 V01 N1: HEAW-SECTION STEEL IRRADIA-(DNL) developed the CARES system (Computer Analysis for TION PROGRAM. Semiannual Progress Report For October Rapid Evaluat,on ni Structures) for the U.S. Nuclear Regulatory 1989 - March 1990. CORWIN,W.R. Oak Radge National Labora-Commission (NRC). CARES is a PC software system which has tory. August 1990 44pp. 9008310217. ORNL/TM-11568.

been designed to pc'iorm stractural response computations 55043:011, similar to those encounn.ed irt licensing reviews of nuclear The primary goal of the Heavy Section Steel irradiation Pro-power plant structures. The documentation of the Seismic gram is to provide a thorough, quanutatNe assessment of the Module of CARES consists of three volumes. This report repre~

effects of neutron irradiation on the material behavior (particu-sents Volume 1 of the three volume documentation of the Seis-larly the fracture toughness properties) of typical pressure-raic Module of CARES. It concentrates on the theorebcal baeis vessel steels as they relate to hght. water reactor pressure-of the system and presents modehng assumptions and limita-vessel integrity. The program includes direct continuabon of irra-tons as well as solution schemed and algonthms of CARES.

diaton studies previously conducted by the Heavy Section The User s Manual is published as Volume 2 while solutions Steel Technology Program augmented by enhanced examina-and results from a set of sample problems are published as tions of the accompanying microstructural charges. Effects of Volume 3 of the CARES documentation.

specimen size; matenal chemistry; product form and microstruc-NUREG/CR 558? Vr$2: CARES (COMPUTER ANALYSIS FOR tsre; irradiat:on fluence, flux, temperature, and spectrum; and RAPID EVALUATION JF STRUCTURES) VERSION 1.0. Seismic postirradiation annealing are examined on a wide range of frac-Module User's Manual XU,J.;

PHILIPPACOPOULO.

ture properties. Detailed statistical analyses of the fracture data Mit.LER.C.A.; et at Brookhaven Nationai Laboratory July 1990.

on K(ic) shift of high-copper welds were performed Analysis of 110pp.9006070352 DNL NUREG 52241. 54848.105.

the first phase o' irradiated crack arrest testing on high copper Dunng FY's 1988 and 1989, Brookhaven National Laboratory welds was comp;eted. Final analysis and pubhcabon of the re.

(BNL) developed the CARES system (Computer Analysis for suits of the second phase of the irradiation studies on stainless Rapid Evaluation of Structures) for the U S. Nuclear Regulatory steel weld-overlay cladding were completed. Determinations Commission (NRC) CARES is s PC software system which has were made of the vanations in chemistry and unirradiated been oosigned to perform Structural resporme cumputahons RT(NDT) of Ow upner shelf weld metal from the Midland reac-similar to those encountered in ficensing reviews of nuclear tor. Final anafyses were performed on the Charpy impact and power plant structures The documenta;.on of the Seismic tensile data from the Second and Third Irra iahon senes on low J

Module of CARES consets of three volumes. This report is upper 6helf welds, and the report on the senes was drafted. A Volume 2 of the three volume documentation of the Seismic detailed survey of exishrig data on microstructural models and 2

12 Maln Citations and Abstracts data bases of irradiation damage was performed, and irvtial de-related challenges to safety systems by edentifying and catego-velopment of a :eactiordrate based model was completed nzing such everAs; 2) to prepare a computerued data base of BOP related reactor inp events and use the data base to identi-NULEQ/CR 5596: UNSATURATED FRACTURED ROCK CHAR.

fy trends and patterns in the population of these events,3) to ACTERt2ATION METHODS AND DATA SETS AT THE innstigato the na imphcatons of BOP events that challenge APACHE LEAP TUFF SITE, RASMUSSEN,T.Ca EVANS.D O.

saMy systems and 4 to provide recommendations on how to SiiEETS.P.J.; et at An or.a. Univ. of Tucson, AZ. August 1990 address BOP-related concerns in a regulatory context 146pp 9009110t22. 551/3.350.

r erformance assessment of high-level nuclear waste contain' NUREG/CR 5640 OVERVIEW AND COMPARISON OF U S.

E me)nt feasibuity requires representative values of parameters as COMMERCIAL NUCLEAR POWER PLANTS Nuclear Power input, including parameter moments, distnbutional charactens-Plant System Sourcebook LOBNER.P.; DONAHOE.Ca tics, and covanance structures between parameters To meet CAVALLIN.C. Science Appbcations Internationd Corp, (formerly this need characten2ation methods and data sets for interst!1;al' Science Apphcetions, incJ September 1990. 600pp bydraultc pneumatic and thermal parameters for a shghtly 9010090058 SAIC 89/1541. 55320 212, welded fractured tuff at the Apache leap Tuff Site situated in

.This report is the intrDdJctory volume to the Nuclear Power centrat Anzona are reported in this document. The data sets in-Plant Sourcebook Senes and is intended as a source of current clude the influence of matric suction on measured parameters summary and comparative information on U,S comme,ciai hgnt Spatial vanability is investiga'ed t;y samphng along nine bore-water reactors (LWRs) The summary a id comparative informa-holes at regular distances Laboratory parameter estimates for tion is organaed into the following four parts; (a) general U S.

10$ core segments are provded, as well as field estimates con' LWRs, (b) pressunzed water reactors (PV 'As), (c) t>oihng water tered on the intervals where the core 6egments we o coliocted reactors (BWRs). and (d) bibliographies of genera! PWR and Measurement uncertainty is estimated by repetitively testing BWR references, plant-specific references, system specific ref.

control samples erences, and component-specific references This report is sup-NUREG/CR 560h FLOW AND TRANSPORT AT THE LAS piemened by a sot of Sourcebooks that provides more Ontailed CRUCES TRENCH SITE.Expenments 1 And 2. WlERENGA.P.Ja Mormation on specific U S. LWR plants.

HUDSON,0 B, Anzona. Univ. of, Tucson, A2. HILLS.R G ; et at NUREG/lA 0033: ASSESSMENT OF RELAPS/ MOD 2 CYCLE New Mexico S' ate Univ., las Cruces, NM. August 1990 42fipp 36 04 AGAINST LOFT SMALL BREAK EXPERIMENT L3-6 0009040036. 55051:200, ERIKSSON.J. Sweden. Govt of.

July 1990.

103pp Two water flow and solute transport expenments were per.

0008140510 STUDSVlkNP87128. 54926 326.

formed as part of a compmhensive field trench study near Las The LOFT small break expmiment L3-6 has been analyzed as Cruces. New Mexico. Thwu expenments were designed to pro.

vide data to test deterministo and stochastic models of vadose part of Sweden s contnbution to the International Thermal +

draulic Code Assessment and Apphcations Program (ICAP).

zone flow and transpurt. In Expenment 1, a 4 m by 9 m area Th'ee calculations, of which twc vere sensitivity studies, were was imgated for 10 days mth water conta:ning tntium, Thereaf-ter, water w;is apphed without tntium for an additional 76 days.

carred out. The following quaif s were vaned. (1) the content of secondary side fluid and r feed water valve closure, and Simple one-dimensional uniform and layered soit deterministic modeis for infdtration adequately predeted the overall move.

(2) the two-phase characteri u of the main pumps. All three predictions agreed reasonably well with most of the measured ment of tho wetting front dunng infiltratton, but poorly pred.cted data The se~titivity calculations resulted only in marginal im-

oint values for water content due to spatial vanabihty Use of the layered soil model, rather than the uniform soil model, dKt provennts.

,e predicted and measured data are compared on,ots and ther differences are quantified over intervals in not consistently improve prediction awurecy for this particular t031 l'me field apphcatiori in Expenment 2, a 122 m by 12 m area was 6rngated for 11.5 days with water containing tatium and brornide' NUREG/lA 0034: ASSESSMENT STUDY U RELAPS/ MOD 2 TP

• gr, water was applied wtbout tracers for an additional CYCLE 36 04 BASED ON PRESSURIZER SAFETY AND 6 m Water and bromide moved fairly uniformly during infil-REttEF VALVE TESTS. STUBBE.E.Ja VANHOENACKER,L

tra, whereas high concentrations of tntium developed on TRACTEDEL. July 1990. 86pp. 0008080178. 54871:157.

one s& of the Irngated area Dur iJ redistnbution, tritium This report presents a code assessment study based on full moved it tio, whereas bromide displayed significant rnovc.aent size rehel and assisted safety valve (called SEBtM) tests per.

both dounward and to one side. A two dimensional determinis-formeo on the CUMULUS valve test og operated by Electncite tic mod i for water flow showed quahtauve, but not quantitative, de France (EDF). The increased awareness that the pressurizer agreer ent with observations A two-dimensional determinsstic safety and rehef valves are not rehable under water blowdown s

mor' A for solute transport poorly descnbed tntium and brormde and installation of so conditions, ha*, led to the design, testing'he SEBIM (TM) vatves

...ovement dunng redintnbution caued assisted safety vanes o' which t NUREG/CR 5822: ANALYSIS OF REACTOR TRIPS ORIGINAT-are an example. These va'ves, used in tandem, are gradually re-ING IN SALANCE OF PLANT SYSTEMS STETSON.F.Ta placing the safety and tehof valves on presaurizers in some Eu-GALLAGHER,0 Wa LE,P.Ta et at Science Applications intema-ropean PWR's Before installation at the plant, the Belgian tional Corp, (formerty Science Apphcatrono, Inc.), September safety authorities requested a thorough full scale testing of 1990 200pp 9010000026 SAIC-89/1148. 55323.064 these valves on a test ng (CUMULUS) equipped with sufficient This report documents the results of an analys:s of balance-diagnostics to measure the charactenstics of the valv2 The of piant (DOP) related reactor tnpa ut commercia! U S. nuclear Beigian architect engineenng firm TRACTEDEL was called upon power plants over a 5 year panod, frorn January 1, 1984, to specify. order and test these valves for installation at the through December 31,19M The study was performed for the DOEu 1 and DOEL 2 power plants These tests do not provide Plant Systems Branen, Office of Nuclear Reactor Regulation, sufficient data of high Quality to justify an assessment study of U S Nuclear Regulatory Commission. The objectives of the the code RELAP 5 MOD-2 CYCLE 36 in the ICAP frameworli study were 1) to improve the level of understanding of 00P-which is the subiect of this report, i

h

/

O

4 Secondary Report Number Index This index lista, in alphabetical order, the performing organization issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross.

referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY REPORT NUMBER REPORT NUMBER SLCONDARY REPORT NUMBER REPORT NUMBER ANL-89 /17 NUREGICR 5365 E PRi*P448C N'JRE G/CR 5395 V t t ANL 90!?

NLREG/CR 5524 VOI E iEC en-01 NURE_G/CR 5515 ANb90/22 NUREG/CP 0112 V01

(('

Oh ANL 00/22 NUREG/CP 0112 VO2 ANU90/5 NUNEG/CR 4 744 V03 N2 ORNL--6%4 NU4t'gG/CR 5451 ORNL4607 NURE G/CR 5519 V01 BAWam7 NUREG/CR 5395 V11 pqNL / NO AC-232 NUREG/CR 4674 V11 BAW 2?M NUREG/CR 5395 Vt1 AD OR NL / NOAC-232 NUREG/CR-4674 Vt2 DMh2139 NUREG/CIL4624 V06 ORNL/NSIC 200 NUREG/CR 2000 V09 Nb (INL-NUREG 516fr) in 'Rt G/CR 3444 VO7 ORNL/NSIC-200 NURE G/CR-2 coo Vo9 N7 BNL-NUREG 51706 NUMEG/CR-3469 V05 ORNL/NSlC 200 NUREGICA 2000 VO9 N8 DNL NUREG 52168 NUREG/CH-5254 ORNL/ T M-11200 NUREG/CR4374 DNL.NUHEG 52178 NUREG/CR 5280 V01

$pffh(4 Ohh BNL-NUREG $2234 NUREG/CR 5%7

)

BNL-NUREG 52/36 NUREG/CH-5572 OHNLMM 115r6 NURE C/CH-5591 VOI N1 PARAME TER hi188 NUREG/CR 5297 DNL NUREG $224i NUREG/CR 5588 V02 PNL 4221 NUREG/CR 2R50 V00 BNL NUREG $2241 NUREG/CR5588 V01 PNL4196 NURE G/CR 4908 BNL NUHEG-52241 NUREG/CR 5588 V03 PNL 4446 NUHE G!CR-511'/

HNbNUREG 52242 NURE G 'OR-5589 SA!C 69/114B NUREG/CR 5622 CT A w00215-025 NUREG/CR 5566 VOi SAIC-89/1541 NURE G /CR-5640 EGG 2576 NUREG/CR-5448 y

$3[3 "h',

3 EGG-2593 NUREG/CR 5528 g

EGG 2597 NUMEG/CR 5542 SANDM 2369 NUREG/CR 5461 EGG 2596 NUREG/CR-5556 SAND 80-2509 NUREG/CO-5453 VOS SANo900375 NURf G/CH S532 EGG 2602 NUREG/CR 5575 S AND90-03 75 NJREG/CR 5453 V05 EPRl/NP 6480 NUREGluR5395 Vil AD STUDSVANPe7128 k.URE GllA-0033 l

l l

13

1 b

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 turther information is needed, refer to the main cita-tion by the NUREG number.

ALEX ANDER.D J.

C AV ALLIN.C.

NUREGICR 5451 CRACK ARREST HEHAVIOR IN SEN WOE PL ATES NUREGICR 5640 OVERMA AND COMPAR SON Or o S COMMER-OF LOW-UPPER SHELF BASE MET AL TESTED UNDER NON!SOTH-CIAL NUCLEAR POWER PLANTS Nuclear power F%r System Sour.

ERMAL CONDITIONS. WP 2 SERIES chA ALLEN,U D.

CHOPR A,0.K, NUREG/CR 5373 A DEMONSTRATION E XPERIMENT OF ST E A M-NUREG/CR 4T44 VD3 N2 LONG-TERM EMBRITTLEMENT OF CAST DR!VEN, HIGH PRESSURE MELT EJECTION The HIPS-10S fest DUPLEY STA!NLESS STEELS IN LWR SYSTEMS Semeannual Report Apnl September 1986 ALLE NSP ACH.F-NUREG/CR 5385 INtTIAL ASSESSVENT OF THE MECHANISMS AND NURLG 1214 R06 H!STORICAL DAs A

SUMMARY

Or THE SYSTEMAT.

SIGNIFICANCE OF LOW TEMPERATURE EMBRITTLEMENT OF (C ASSES 5 MENT OF LICENSEE PERFORMANCE CAST ST AINLESS STEELS IN LWR SYSTEMS ALLICON.D P.

CHU.M.S.Y.

NUREG-1409 BACAFITriNG GUCELINES NUREG/CR-5453 V05 BACMROUND INFORMATION FOR THE DE-VtLOPMENT OF A LOW. LEVEL WASTE PERFORMANCE ASSESS-NU EC/

374

SUMMARY

OF INADEOVAR CORE COOLING IN-S TRUMENT A TION FOH UNITED STATES NUCLEAR POWER NUREG/CR 5532 A PERFORMANCE ASSESSMENT METHODOLOGY PLANTS FOR LOW-LEVEL W ASTE FACluTIES APOSTOLAKIS.G.

egggg,g y NUREG 1420 SPECIAL COMMitTE' REVIEW OF THE NUCLEAR REG ^

NUREG/CR 4744 V03 N2 LONG-TERM EMBRITTLEMENT OF CAST LATORY COMWSS10N'S SEVERE ACCOENT RISKS REPORT DUPLEX STAINLESS STEELS IN LWR SYSTEMS S<..wannual Report Apnl Septembst 1988 D A K E R,0. A.

C ARgg GpCR Sit? STEAM GENERATOR Tb8E INTEGRITY PROGRAM /

R NUREG!CR-2850 V00 POPULATON DOSE COMMITMENTS DUE TO RA CTIVE RELE ASES FROM NUCLEAR POWER PLANT SITES STEAbt GENERATOR GROUP PROJECT Fral Proiect Summary Report.

DAS?DR.

C LE TCHE R.J.W.

NUREG rCR-5451 CRACK ARREST BEHAVIOR IN SEN WOE PLAllS NUREG/CRJ674 V11 PRECURSORS TO POTENTIAL SEVERE CORE OF LOW-UPPER SHELF BASE MET AL TE STED UNDER NONISOTH.

DAMAGE ACCIDENTS 1989 A STATUS REPORT Main Report And Ap-ERMAL CONDITIONS WP 2 SCRIES penda A BAUMJW.

NURFG/CR-4674 V12; PRECURSORS TO POTENTIAL GEVERE CORE NUREG/CR-3469 V05 OCCUPATIONat DOSE REDUCTK)N AT NU.

DAMAGE ACCIDENTS 1989 A STATUS REPORT. Appendices B Arid CLEAR POWER PLANTS ANNOTATED O!BUOGRAPHY OF SELECT.

C ED READINGS iN RADIATION PROTECTION AND ALARA DIR K HOF E R,E,H.

NUREG-t 425. W ELD!NG AND NONDESTRUCTIVE EXAM! NATION NUREG-1420 SPECIAL COMM!TTEE REVIEW OF THE NUCLEAR REG.

ISSUES AT SEABROOK NUCLEAR STATION An independent Review ULATORY COMWSSION'S SEVERE ACCIDENT RISKS REPORT Team Report (NUREG-1150)

CONNE LLY.E.M.

DLANFORD.J.H.

NUREG/CR 5568 V0t. INDUSTRY BASED PERFORMANCE INDICA.

NUREG/CR 5596 UNSATURATED FRACTURED ROCK CHARACTER.

TORS FOR NUCLEAR DOWER PLANTS Phase 1 Report June 1989 -

IZATION METHODS AND DATA SETS AT THE APACHE LEAP TUFF Febrwy 1990-SI T E.

CONRAN4H.

DLOSE,R.E.

NUREG 1409 BACAFITTING GUOELINES NUREG/CR 4794 EXPEniMENT AL RESULTS OF COAE CONCRETE INTE R ACTIONS USING MOLTEN STEEL WiiH Z1RCONIUM, COPINGER 0,A.

NUREG/CR 4674 Vit PRECURSORS TO POTENTIAL SEVERE CORE BOWEN,W.M[

DAMAGE ACCIDENTS 1989 A STATUS REPORT Main Report And Ap.

NUREC/CR-5117 STEAM GENERATOR TUBE INTEGRITY PROGRAMi penda A.

STEAM GENERATOR GROUP PROJECT Final Praect Summary NUREG/CR-4674 V12 PRECURSORS TO POTENTIAL SEVERE CORE Report DAMAGE ACCIDENT &1969 A STATUS REPORT. Append <es B And C.

DRADLEY,EA NUREG/CR 5117. STEAM GENERATOR TUDE INTEGRITY PROGRAMr COPUS,EA STEAM GENER ATOR GROUP PROJECT Final Prmect Sum.wy NUREG!CH 4794 EXPE R f MENT Al, RESULTS OF CORE-CONCRETE Report INTERACTIONS USiNG MOLTEN STEEL W1f H 2tRCONIUM.

BROC K M ANN,J.E.

CORUGEDO.J.J.

NURE GICR4794 EXPERIMENT AL RESULTS OF CORE CONCRETE PUREG/CR 5515 LIGHT WATER REACTOR PRESSURE ISOLAtlON INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM VALVE PERFORMANCE TESTING 15

16 Personal i athor hidex i

CORWIN,wA DOCTOR,P.G.

NUREG/06 M91 m MAVY SECTON STEEL iRRADtATION NUREG/CR 5117 STEAM GE NE RA10H TUDE INTEGRITY PROGRAMe PWJGRAM Seru saa! Progress Repcst F or OctoNr 1989 MaNh S TE AM GE NER ATOR GROUP PROFCi Final Protect Summary 1990 Report COST ANTINO.C.

DOCTOR S.R NOREG/C45586 VO1 CARES (COMPUTER ANALYSIS FOR RAPID NUREG/CR 4908 MTRASONIC INSPECTON HillAblLITY FOR IN T EORANULAR STRESS CORROSON CRACKS A Round Rotun M

e Ttw <etwa Manua St4y Of The Eff*+ cts CH Personnel Proccuses. E qapment. And Crace NUREG/CR %M V02. CARES (COMPUTER ANALYSIS FOR RAPtD EV ALU ATION OF STRUCTLIRES)

VERSON 10Seemc Cha actenstics Module UWs Manual NUREG/CR 5548 VO3 CARES (COMPUTER ANALYS!S FOR RAPO DOLAN.B.W.

EV ALUAT ON OF STRUCTURES)

VERSION 1 D Semm e NUREG/CR4674 Vil-PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS 1969 A ST ATUS RE PORI Ma,n Report AN Ap.

MMule Sample Prot 9ema perds A COTTER,D P.

NUREG/CR 46?4 V12 PRECURSORS TO POTENTIAL SEVERE CORE NVREG 1363 V02 ATOMIC SATETY AND LICENSING 00ARD F ANEL DAMAGE ACCIDENTS 1969 A STATUS REPORT Appendices B And ANNUAL REPORT FISCAL YE AR 1989 c

CROUCH.D.

DONAHOE.C NUREG!CF %to OVERVIEW AND COMPARISCN OF U S COMMER-C TF OL.TATIO 4 D N

W CU TO S C i MA 4 CIAL NUCLEAR POWER PLANTS Nuclear Power Plant System Sour-f OPMANCE AND NUCLEAR POWER PLANT RISK cebook CROWLEY,W.

NUREG 1425 WELDING AND NONDE STRUCTIVE EX AM;N AT ON E DE RT,M.W.

ISSUES AT SE ADROOK NUCLEAR STATION An IndepeNent Reven NUREG/CH 5622 ANALYSIS OF REACTOR TR1PS ORIGINATING !N Team Report.

BALANCE Of PLANT SYSTEMS CULLE N.W.H.

EDSONJ L NUREG/CP.0112 Vot. PROCEEDtHOS OF THE THIRD INTERNATON-NUREG/CR 5448 AGING EVALUATION OF CLASS 1E DATTERTS AL ATOMIC ENERGY AGENCY SPECIALISTS' MEETING ON SUB-SEISMIC TESilNG CRITICAL CRACK GROWTH Opening Session And Technical Seneon iHeld Al Moscow. USSR.May 14 17 1990 EMRITA NUREG/CP 0112 V02 PROGLEDIN8S OF THE THIRD INTERNATON-NUREG-0933 Sti: A PRIORITIZATION OF GENERIC SAFETY ISSUES AL ATOMIC ENERGY AGENCY SFECIALISTS' MEETING ON SUB CRITICAL CRACK GROWTH Techncal Sessons it. lil And IV And ERIKSSON,J.

Recomnwndahons And Conclusions Sesmon V Held At NUN!G/tA-003) ASSESSMENT OF RELAP5/ MOO 2 CYCLE 36 04 Moscow.USSA.May 14 17,1990 AGAtNST LOFT SMALL BREAr; EXPERIMENT L3-6 CURTIS.LA.

E V ANS,0.D.

HUREG/CR4624 V06 RADIONUCLIOE RELEASE CALCULATONS NUREG/CH 5596 UNSATURATED FRACTURED ROCK CHARACTER-FOR SELECTED SDERE ACCOENT SCENAntOS Surpiemontal Ca'-

12ATION METHOUS AND DATA SETS AT THE APACHE LE AP TUFF cwations.

SITE CYDULS t.S.P.

NUREWR4624 V06 RADtONUCL10E RELEASE CALCULA TONS FERRISAH.

FOR belt.u tu dEVERE ACCIDEN T SCENARIOS Supptomental Cat.

NUREG/CR 5117. STEAM GENERATOR TUDE INTEGRITY PROGRAM /

culations STEAM GENERATOR GROUP PRCUE^T Fmt Proiect Summary DALLMANAJ.

NUREG/CH 55?B. AN ASSESSMENT OF DWR MARK ll CONTAINMENT FIELDSAJ.

CHALLENGES. FAILURE MOnES AND POTENTIAL IMPROVEMENTS NUREG/CR 5451 CRACK. ARREST BEHAVOR IN SEN WOE PLATES IN PERFORMANCE OF LOW. UPPER-SHELF BASE METAL TESTED UNDER NONISOTH-ERMAL CONDIflONS WP-2 SER!ES DE AN,R S.

NUREG/CH SM1. CLOSEOUT OF lE DULLETIN 03 05 ASVE NUCLEAR NU R-529?. CLOSEOUT OF IE DULLETIN 83-05 ASME NUCLEAR WARD T ER MPC A Y' CODE PUMPS AND SPARE PARTS MANUFACTURED DY THE HAY-w ARD TYLER PUMP COMPANY.

DEF FENBAUGH.J NUREGICR4000 ULTRASON:C INSPECYlON REllADILITY FOR IN-TERGRANULAR STREcs CO9AOslON CRACKS A Round Rcben GALLAGHER,0,W.

Study Of The Effects Of Personnel, Procedures, Equipment And Crack NUREGICR 5622: ANALYSIS OF REACTOR TRIPS OROINATING IN DALANCE OF PLANT SYSTEMS Chwactenstes DE NNINGAS.

C AR NE R.R.W.

NUREG/CR 4624 V06 RADIONUCLOE RELEASE CALCULATIONS NUREG/CR-5556 REVIEW OF CURRENT LITERATURE RELATED TO FOR SELECTED SEVERE ACCOENT SCENAROS Supplemental Cab GENERIC SAFETY ISSUE 15 culakons GEISSLER,0.0, DEWTTA NUREGICA-5395 VII-MULTILOOP INTEGRAL SYST EM TEST NUREG!CR.5451 CRACK ARRJST BEHAYlOn IN SEN wt PLATES (M;ST) FINAL REPORT YlST Phase IV Tests Of LOW. UPPER SHELF B ASE METAL YESTED UNDER NON60TH~

NUREG/CR 5305 VII AD MULTILOOP IN TEGR AL SYSTEM TEST ERMAL CONDtTICNS WP 2 SER!ES (MIST) FINAL REPORT MIST Phase IV Tests DIERCKS DA GO M E Z,R.D.

NUREGAR 5524 V01 TMI-2 VESSEL INVESTIGATION PROJECT (VIP)

NUREGICR 4 ?94 EXPERIMENTAL RESULTS OF CORE. CONCRETE ME T ALLURGICAL PROGRAM Prort Repot. January.Septemtae, INTERACTIONS USING MOLTEN STEEL WITH ZIRCONIUM.

1969 OtONNE.0J.

H AAS.P.M.

NUREG/CR 3M VOS OCCUPATIONAL DOSE REDUCTON AT NU-NUREG/CR 5560 V01 (NDUSTRY DASED PERFORMANCE INDtCA-C' E AR POWE R PLAN 15 ANNOT ATED Bt0LIOGRAPHY OF SELECG TORS FOR NUCLEAR POWER PLANTS Phase 1 Report June 1980 -

ED RE ADINGS IN RADIATION PROTECTION AND ALARA.

Fettuary 1990

(

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

4 Personal Author index 17 HACE N.E.W.

JONE S.K.R.

NUREG/CR 53/4 SUMMAFly OF INADEOUATE CORE COOLING IN.

NJREG/CR4528 AN ASSE iMENT OF DWR VARK la CONTAINMENT STRUMLNTATION FOR UNITED STATES NUCLEAR POWER CHALLENGES. FAILURE MODES, AND POTENTIAL IMPROVEMENTS PLANT $

IN PERFORMANCE NUREG/CR 5575 OUANili AflVE ANALYSIS OF POTENTIAL PE H.

N G

0 V14 NO3 LICENSED OPEPATING RE ACTORS STATUS

SUMMARY

REPoni Data As Of Fotvuary 28.1990.(Gray Ekok 0 JORDAN H, NUREG/CR-4624 V06: RADIONUCLIDE NELE ASE CALCULATIONS gggg g pg NUftLG/CR-4MB ULTRASONIC INSPECfCN RELIABILITY FOR IN-b TERGRANULAR STRE SS CORROSION CHACKS A Round Rotun S cty Of The E flucts Of Pennonnul. Prrredgres. Equipment. And Crack K ALsEM 3, CLra;tanstics NURLG/CR 5583 PREDICTION OF CHECK VALVE PERFORM / JCE HENNICK.A.

AND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS NUREG/CR 5297: CLOSEOUT OF IE DULLETIN 8109 ASME NUCLEAR WEAR AND IMPACT T[ STS Fina: Reportseptember 1988 April 1990 CODE PUMPS AND SPARE PARTS MANUFACTURED DY THE HAv.

US M DERG E WARD TYLER PUMP COMPANY' NURLQ 1420 SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-HIGGINS.J.

ULATORY COMM:SSON S SEVERE ACCIDENT RISKS REPORT NUREG/CR 5572 AN FVALUATON OF THE EFFECTS OF LOCAL (NUREG-1150)

CONTROL STATION DE$ GIN CONFIGURATONS ON HUMAN PER' KEENEY WALKER FORMANCE AND NUCLE AR POWER PLANT HISK NUREGiCR 5450 CRACK. ARREST DEHAVIOR !N SEN ' WIDE PLATES HILLE.L OF LOW. UPPER SHELF DASE METAL TFSTED UNDER NONICOTH-NUREG-1377 F101: NRC RESEARCH PROGRAM ON PLANT AGING CRMAn. CONDITIONS WP-2 SERIES.

LIS INGS AND SUMMARIES OF REPORTS ISSUED THROUGH MAY KELL Y.D.L.

NUREG/CR-5528 AN ASAES5 VENT OF DWR MARK ll CONTAINMENT HILLS R O CHALLENGES, FAILURE MODES, AND POTENTIAL IMPROVEMENTS NUREG/CR 5607, FLOW AND TRANSPORf AT THE LAS CRUCES IN PERFORMANCE TRENCH StTE Experitrwnts 1 And 2 NUREG/CR 5575: OUAN11TATIVE ANALYSIS OF POTENTIAL PER-FORMANCE IMPROVEMENTS FOR THE DRf PWR CONTAINMENT.

HOEQUERG,LQ.

t NUREG 1420: SPECIAL COMMiiTEC REVIEW OF THE NUCLEAR REG-KELLYAF.

I-ULATORY COMMISSION'S SEVE RE ACODENT RISKS REPORT NUF.EG/CR 4624 V06-RADONUCLOC RELEASE CALCULATIONS (NUREG-11W FOR SELECTED SEVERE ACCOENT SCENARIOS Suppiamenta! Cal-culabons HORST,C.L NUREGICR-5581 PREDICflON Or CHECK VALVE PERFORMANCE KHAN,T.A.

AND DEGRADATION IN NUCLE. AR POWER PLANT SYSTEMS NUREG/CR 3469 V05 OCCUPATONAL DOSE REDUCTION AT NU-WEAR AND IMPACT TESTS Final Report, September 1908 Aptd 1000.

CLEAR POWER PLANTS ANNOTATED BlDLOGRAPHY OF SELECT-ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR 5607 FL.OW ANJ TRANSPORT AT THE LAS CRUCES KIRKLAND,MA TRENCH SITE Espenments t And 2.

NUREGICA.5607 FLOW AND TRANSPORT AT THE LAS CRUCES ISKANDER,S L NUREG/CR 5451: CRACK ARREST DEHAVOR IN SEN WIDE PLATES KONDIC N.N1 OF LOW UPPER-SHELF DASE METAL TESTED UNDER NONISOTH' NUREG 1377 R01: NRC RESEARCH PROGRAM ON PLANT AGING ERMAL CONDITIONS. WP4 SERIES LISTINGS AND SUMMARIES OF REPORTS ISSUED THROUGH MAY JACODUS,M.J.

20 NUREG/CR 5461-AGING OF CADLES, CONNECTONS. AND ELECTRI-KOUTS H.J C CAL PENETRATION ASSEMDLif S USED IN NUCLEAR POWER NUREG-1420: SPEC AL COMMITTEE REVIEW OF THE NUCLE AR REG-PLANTS.

ULATORY COMMISSION'S SEVERE ACCIDENT RISKS REPORT JEANMOUQlN,N M.

(NUREG I1501-NUREG/CR 5515 LIGHT WATE'1 REACTOR PRESSURE ISOL ATION K DZ A K,M.W VALVE PERFORMANCE TLSTING-NUREG/Cint53 V05: DACKGROUND INFORMATON FOR THE DE.

JO,J. -

VFLOPMNT OF A LOW-LEVEL W6STE PERFORMANCE ASSESS-NUREG/CR 5?54 DIAS IN PEAK CLAO TEMPERATURE PRED;CTIONS

- MENT METHODOLOGYaomputer Code impicmentation And Assess-DUE TO UNCERTAINTIES IN MODELING OF ECC DYPASS AND DIS-

- N"i

'rOLVED t4014CONDENSADLE. GAS PHENOMENA.

NUREGiCR-553? A PERFORMANCE ASSESSMENT METHOOOLOGY FOR LOW LEVEL WASTE FACILITIES

' JOH ANSSON10.

NUREG/CR-5451: CRACK ARREST DEHAVOR IN SEN WIDE PLATES KURTZ,R.J.

OF LOW UPPER-SHELF DASE METAL TESTED UNDER NONISOTH.

NUREG/CR-Sit 7. STEAM GENERATOR TUDE INTEGRITY PROGRAM /

ERMAL CONDITIONS WP-2 SERIES

-STEAM GENERATOR GROUP PROJECT Final Protect Summary Pwnt JOHNSON.J.D.

NUREG!CR 5453 V05 DACKGROUND INFORMATION FOR THE DC-LE M VELOPMENT OF A LOW-LEVil WASTE' PERFORMANCE ASSGS.

N'.N G/CRS622: ANALYSIS OF REACTOR TR!PS ORIGINATING IN KNT METHOOOLOGY. Computer Code implementation And Assess.

t:ALANCE OF PLANT SYSTEMS-L E E,K.W. '

JOHNSONAE.

NUREG/CR-4624 vos RADIONUCLIDE RELEASE CALCULATIONS NURFG 1339 RESot.UTION OF GENERIC SAFETY ISSUE 20 BOLTING FOR SELECTED SEVERE ACCOENT SCENAROS Supplemental Ca' DEGRADATION OR FAILURE IN NUCLE AR POWER PLANTS --

colations JONES.C.CL LEONARD.M.T.

NUREG 1396 ENVIRONMEUTAL ASSESSMENT OF THE THERMAL NUREG/CR 4624 VLW RADIONUCLIDE RELEACE CALCUL A TIONS NEUTT40N ACTIVITATON EXPLOslVE DETECTION SYSTEM FOR FOR SELECTED SEVERE ACCIDENT SCENARtOS Supemental Cai-CONCOURSE USE AT llS AtRPORTS culations

18 Personal Author Inden LE 8 AGE.LG.

MOVERS) C.

NUREG.1420 SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-NURE?s/CR 5519 V01 AGtNG OF CONTROL AND SERVICE AIR COM.

ULATORY COMMIS$ON'S SEVERE ACCOENT RISKS REPORT PRESSORS AND DRYERS USED IN NUCLEAR POWER PLANTS (NURE G-I150)

NAUS.DA LIPINSKl.R E.

NUREG/CR 5C1 CRACK. ARREST BEHAVOR IN SEN WOE PLATES NURE G/CR 5556 REVIEW OF CURRENT LITERATURE RELATED TO OF LOW. UPPER-SHELF RASE METAL TESTED UNDER NONISOTH-GENERIC SAFETY 1%UE 15 ERMAL CONDITIONS WP-2 SERIES LOONER.P.

gg gty,g,g, NUREGICR 5640 OVEHVIEW AND COMPAR: SON OF U S COMMER-NUREG/CR 5515-LIGHT WATER REACTOR PRESSURE ISOLATON CIAL NUCLEAR POWER PLANTS Nuclear Power Ptent System Sour-VALVE PERFORMANCE TESTING cebook NEYMOTIN.LY.

NUREGTHW MS W W GAD WWW NON N Ed/CR 5451. CRACK-ARREST BEHAVIOR IN SEN WIDE PLATES

^

b bb OF LOW-UPPER-SHELF BASE METAL TESTED UNDER NON!SOTH-SOLVED NON-CONDENSABLE GAS PHENOMENA.

ERMAL CONDITONS WP-2 SERES N!CHOLS R.T.

LUCERO D.A NUREG/CR-5373 A DEMONSTRATION EXPERIMENT OF STEAM-NUREd/CR 4794 EXPLRIMENI AL RESUtTS Or CORE CONCRETE DRIVEN. HIGH-PRESSURE MELT EJECT ON The HIPS-10S Test.

INTERACTONS USING MOLTEN STEEL WITH 71RCONIUM.

NOURDAKHSH,HA LUCKAS.W.

NUREG/CH 5572 AN EVALUATON OF THE EFFECTS OF LOCAL NUREGIC45589 ASSESSMENT OF ICEOONDENSER CON 1 AINMENT CONTROL ST ATON DESGIN CONF 4GURATONS ON HUMAN PER.

PERFORMANCE ISSUES.

FORMANCE AND NUCLEAR POWER FLANT RISK.

, gaga.

MACDOUGALLE.

NUREGICA-5572 AN EVALUATON OF THE EFFECTS OF LOCAL NUREG/CR 5280 V01' AGE.RELATED DEGRADATION OF WESTING.

CONTROL STATION DESGIN CONFIGURATONS ON HUMAN PER.

HOUSE 480-VOLT CIRCUIT BREAKERS Agn0 Assessment And Roc.

FORMANCE AND NUCLEAR POWER PLANT RISK.

ommendehons For impfowng Dreaker Rellatahty MATTINGLY,P.A.

NUREGICR-5575: OVANTIT ATIVE ANALYSIS OF POTENTIAL PER.

NUREG/CR 5453 V05: BACKGROUND INFORMATION FOR THE DE-FORMANCE IVPROVEMENTS FOR THE DRY PWR CONTAINMENT VELOPMENT OF A LOW-LEVEL WASTE PERFORMANCE ASSESS-MENT METHODOLOGY Computer Code implementanon And Assess.

PHILIPPACOPOULO ment NUREa CR 5588 Vol: CARES (COMPUTER ANALYSIS FOR RAPID NUREG/CR 5532: A rERFORMANCE ASSESSMENT METHODOLOGY EVALUATION OF STRUCTURES)

VERSON 10 Seismic FOR LOW LEVEL WASTE FACILITIES.

Meule Theorehcal Manuai NURE0/CR-5588 V02: CARES (COMPUTER ANALYSIS FOR RAPID MCCOROJ.T.

EVALUATION OF STRUCTURES)

VERSION 10 Seemic NUREG'CR-5453 V05 BACKGROUND INFORMATION FOR THE DE-MoMe User's Manual VELOPMENT OF A LOW-LEVEL WASTE PERFORMANCE ASSESS-NUREU/CR 5588 V03 CARES (COMPUTER ANALYSIS FOR RAPO MENT METHODOLOGY. Computer Code implementahon And AAsess-EVALUATION OF STRUCTURES)

VERSION 1.0 Seismic ment ~

Module Sample Problems.

MCNAMARA N-PILCH,M.

NUREG-0837 V10 NO2 NRC TLD OtRECT RADIATON MONITORING NUREG /CR-5373 A DEMONSTRATION EXPERIMENT OF STEAM-NETWORK Progress Report Apral-June 1990.

DRWEN, HtGH PRESSURE MELT EJECTION The HIPS tos Test MERKLE.J.G.

PITTMANJ.

NUREG/CR 5552. AN OVERVIEW OF THE LOW UPPER SHELF NUREG-0933 S11, A PRIORIT12ATION OF GENERIC SAFETY ISSUES TOUGHNESS SAFETY MARGIN ISSUE.

PLANSKY LE.

MILIAN.LW^

NUREG/CR-5542. MODELS FOR ESTIMATON OF SERVICE LIFE OF NVREG/CR.3444 V07: THE IMPACT OF LWR DECONTAMINATONS

• ##N ON SOLO 4FICATION. WASTE OtSPOSAL AND ASSOCIATED OCCU-PO M PATONAL EXPOSURE, PORRO,L MILLER C.A.

NUREG/CR460/ FLOW' AND TRANSPORT AT THE LAS CRUCES NUREG/CR 5588 V01: CARES (COMPUTER ANALYSIS FOR RAPiO TRENCH SITE Expo,monts 1 And 2-EVALVATION OF STRUCTURES)

VERSION 10 Sammic MoMe Theoretcat Manual NUREG 42 S'PECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-EVA AI TRU TURE VERSIO Ss ULA10RY COMMISSION'S SEVERE ACCIDENT R!SKS REPORT Module user's Manua, NUREG/CR 5588 V03. CARES (COMPUTER ANALYSIS FOR RAPIO (NUREG-1150).

EVALUATION OF STRUCTURES)

VERSON 1.0 Seismic RA MU SEN, Module Sample Problems MILSTEAD,W.

IZATION METHODS AND DATA SETS AT THE APACHE LEAP TUFF NUREG-0933 S11-A PRIORITIZATION OF GENERIC SAT ETY ISSUES SITE MINARICKJ.W.

RIGGSA NUREGICA.4574 Vll PRECURSORS TO POTENTIAL SEVERE CORE NUREG 0933 S11 A PRORiT1ZATION OF GENERIC SAFETY ISSUES DAMAGE ACCOENTS 1989 A ST ATUS REPORT Main Report And Ap-pe,wu A.

ROBINSON,0.C.

NUREG!CR 4674 V12 PRECURSORS TO POTENTIAL SEVERE CORE NUREG!CR-5451: CRACK ARREST BEHAVIOR IN SEN WIDE PLATES DAMAGE ACCIDENTS 1989 A STATUS REPORT. Append;ces B And OF LOW. UPPER. SHELF BASE METAL TESTED UNDER NONISOTH-C.

ERMAL CONDITIONS WP 2 SERIES MORE LOC K.T.C.

ROHATGI,U.S.

N') REG /CR 5374

SUMMARY

OF INADEQUATE COHE COOLING tN-NUREG/CH-5254 BIAS IN PE AK CLAD *.EMPERATURE PREDICTIONS ST RUVENT ATON FOR UN'T E D STATES NUCLEAR POWER DUE TO UNCERTAINTIES IN MODELING OF ECC SYPASS ANO DIS-PLANTS.

SOLVED NON CGNDENSABLE GAS PHENOMENA

Personal Author index 19 RUGE R,C.

T AYiOR.J.J.

NUREG/CR 5572-AN EVALUATON OF THE EFFECTS OF LOCAL NUREG-1420 SPECIAL COMurTTEE REVIEW OF THE NUCLE AR REG-CONTROL ST ATON DESGIN CONOGURATIOWS ON HUMAN PER-ULATORY COMMISSION'S SEVERE ACCIDENT RISKS REPORT FORMANCE AND NUCl EAA POWER PLANT RISK.

(NUREG-1:50)

SATHERA.

T A Y LOR,T,T.

NUREG/CR 5385 tNITIAL ASSESSMENT OF THE MECHANISMS AND NUREG/CR4908. ULTRASONIC INSPECTION REllADIUTY FOR IN-SONIFICANCE OF LOW TEMPERATURE EMBRITTLEMENT OF TERGRANULAR STRESS CORROSION CRACKS A Round Hotun CAST STAINLESS STEELS IN LWR SYSTEMS Study Of The Effects Of Personnei, Procedures. Er.ppment. And Crack SCHROE DE R.J.A.

NUREG/CR 5575. QUANTITATIVE ANALYSIS OF POTENTIAL PER-TEAGUE.H.J.

FORMANCE IMPROVEMENTS FOR THE ORY PWR CONT AINMENT.

NUREG 1420- SPFCIAL COMMITTEE REVIEW OF THE NUCLEAR REG.

ULATORY COMMISSON'S SEVERE ACCIDENT RISKS REPORT SCHUM ACHE RP.M.

NUREG/CR-4624 V06: RADIONUCLIDE RELEASE CALCULATONS (NUREG-1150L FOR SELECTED SEVERE ACCIDENT SCENAROS Supplemental Cab THEISS,T.J.

cutawno-HUREG/CR4554 RECOMMENDATIONS FOR THE SHALLOW. CRACK SCHW ARTZ,C.W.

FRACTURE TOUGHNESS TESTING TASK WITHIN THE HSST PRO-NUREG/CR 5451: CRACK ARREST BEHAVOR IN SEN WIDE PLATES GRAM.

OF LOW UPPER SHELF BASE MET AL TESTED UNDEH NONISOTH.

TR E

ERMAL CONDITONS WP-2 SERIES.

g B CKFITTING GUIDELINES SHARM A V.

NUREG/CR 5583 PREDICTON OF CHECK VALVE PERFORMA%E VAN HEMEL,S.B.

AND DEGRADATON IN NUCLEAR POWER PLANT ScSir,MS NUREG/CR 5568 V01. INDUSTRY BASED PERFORMANCE INDICA.

WEAR AND IMPACT TESTS Finai Report,Septemter 1988. ord 1990.

TORS FOR NUCLEAR POWER PLANTS Phase 1 Report June 1989 Fetxuary 1990.

SHE ETC,P.J.

NUREGICR4596 UNSATURATED FRACTURED ROCK CHARACTER.

VANHOENACKERL 17Ai!ON METHODS AND DATA SETS AT THE APACHE LEAP TUFF NUREG/lA 0034 ASSESSMENT STUDY OF RELAP5/ MOD 2 CYCLE SIT E.

36.04 BASED ON PRESSURIZER SAFFTY AND RELIEF VALVE TESTS.

SHIER W.

NUREG/CR 5280 VOI. AGE-RELATED DEGRADATON OF WESTING-VINSON.J.

HOUSE 480 VOLT CIRCUIT BREAKERS Aging Assessment And Rec.

NUREG/CR4607. FLOW AND TRANSPORT AT THE LAS CRUCES ommendatsons For Improving Breaker Rehatnhty TRENCH SITE.Erpentnents 1 And 2 SIMONEN,F.A.

W AGNER K.C.

NURf.G/CR 5117: STEAM GENERATOR TUBE INTEGRITY PROGRAM /

NUREG/CR.5528 AN ASSESSMENT OF BWR MARK ll CONTAINMENT STEAM GENERATOR GROUP PROJECT Final Project Summary CHALLENGES. FAILURE MODES, AND POTENTIAL IMPROVEMENTS Report IN PERrCAMANCE.

SMITH.RW.

WALTON,G.

NUREGICR 5542: MODELS FOR ESTIMATION OF SERVICE UFE OF NUREG-1425: WELDING AND NONDESTRUCTIVE EXAMINALON COWCRETE BARRIERS IN LOW. LEVEL RADIOACTIVE WASTE DIS-ISSUES AT SEABROOK NUCLEAR STATION An independent Reymw POSAL Team Report.

SOO.P.

W ALTON,J.C.

NUREG/CH-3444 V07; THE IMPACT OF LWR DECONTAMINATIONS NOREG/CR 5542" MODELS FOR ESTIMATON OF SERVtCE LIFE OF ON SOLIDIFICATON. WASTE DISPOSAL AND ASSOCIATED OCCV-rONCRETE BARRIERS IN LOW. LEVEL RADCACTivE WASTE DIS-PATONAL EXPOSURE.

,oSAL SPA NNE R,J.C.

WANG.J K.

NUREG/CR4908. ULTRASONIC INSPECTON RELIABILITY FOR IN~

NUREG/CR5583. PREDtCTION OF CHECK VALVE PERFORMANCE TFRGRANUL AR STRESS CORROSON CRACKS.A Round Robin AND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS Study Of The Effects Of Personnel, Proceoures, Equipment. And Crack WE AR AND IMPACT TESTS Final Report September 19e8 Apnl 1990 Charac'enstKs WHARTON,R.

SJESSARD,RL NUREG-1214 R06 HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

dVREG 1425: WELDING AND NONDESTRUCTIVE EXAMINATION IC ASSESSMENT OF LICENSEE PERFORMANCE ISSUES AT SEABROOK NUCLEAR S*ATION An indenendent Review N#9#

WlERENGA,P.J.

NUREG/CR 5607. FLOW AND TRANSPORT AT THE LAS CRUCES STETSOhAT.

TRENCH SITE.Expenments 1 And 2.

NUREG/C6 (622 ANALYSIS OF REACTOR TRIPS ORIGINATING IN

= BALANCE OF PLANT SYSTEMS' WULFF,W.

NUREG/CR-5254. BIAS IN PEAK CLAD TEMPERATURE PREDICTIONS STRUCKMEYER,R DUE TO UNCERT AINTIES IN MODELING OF ECC BYPASS AND DIS-NUREG 0037 V10 NO2 NRC TLD DIRECT RADIATON MONITORING SOLVED NON-CONDENSABLE GAS PHENOMENA NETWORK Progress Report Apnl-June 1990 STUBBE E.J.

X U,J.

NUREG/lA-0034 ASSESSMENT STUDY OF RELAPS/ MOD 2 CYCtE NUREG/CR5588 vol: CALES (COMPUTER ANALYSIS FOR RAPO

,J 36 04 BASED ON PRESSUR12ER SAFETY AND PEllEF VALVE EVALUATION OF STRUCTURESI VERSION 10 Seismic TESTS Module. Theoretical Manual NUREGrCR5508 V02-CARES (COMPtffER ANALYSIS FOR RAPID SUGUDHI,M.

EVALUATION OF STRUCTURES)

VERSION 10 Seismic NUREG/CR 5280 V01: AGE RELATED DEGRf 0ATION OF WESTING-Moduw User's Manual HOUSE 480-VOLT CIRCULI BREAKERS Agmg Assessment And Rec.

NUPEG/CR 5589 V03 CARES (COMPUTER ANALYSIS FOR RAPO ommendations For Improvmg Breaker Rehatslity EVALUATION OF STRUCTURES)

VERSION LO be smic Module Sample Preuems NUREG/CR3469 VOS. OCCUPATONAL DOSE REDUCTON AT NU.

Y ANG.J.W.

CLEAR POWER PLANTS ANNOTATED B!BLIOGRAPHY OF SELECT-NUREG/CR5567: PWR ORY CONTAINMENT ISSUE CHARACTER 12A<

CD READINGS IN RADIATION PROTEC? ION AND ALARA.

TON

m i

e iumimmmmmmmes.

-'v=-

s

Subject Index This index was developed from keywords and word strings in tities 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.

AEOD DWR NUREG.12 72 V04 N31 OFFICE FOR ANAL YSIS AND Et ALUATION OF NUREG/CR452B AN ASSESSMCNT OF BWR MARK lt CONT AINMENT OPERATIONAL DAT A 198L' ANNUAL REPORT Power Reactors CHALLE NGE S.F AILURE MODES. AND POTENTIAL IMPROVEMENTS NUREG 1212 Yod NO2 OFFICE FOR ANAL YS!S AND EVALUATION OF IN PERFORMANCE OPI RATIONAL DAf A 1909 ANNUAL REPORT Nonreactors Backfitting Guldeline ALARA NUREG 1409 BACKFIT f1NG GUIDELINES NUREGICR 3463 V05 OCCUPATIONAL DOSE REDUCTION AT NU-CLEAR POWER PLANTS ANNOT ATED B40!!OGRAPHY OF SELE I.

Datance Of Plant ED READINGS IN RADtATION PROTECTION AND Al ARA NUREG/CR 5622 ANALYSIS OF REACTOR TRIPS ORIGINAflNG IN BALANCE OF PLANT SYSTEMS Abrermal Occurr ence NUREG 0090 Vl3 Not REPORT TO CONGRESS ON ADNORMAL Dolfing Water Reactor NUREG'CR 5528 AN ASSESSMMT OF BWR MARK 11 CONT AINMENT OCCURRENCESJanuary March 1990 NUREG 1272 V04 NO2 OFFICE FOR ANALYSIS AND EV ALUATION Or CHALLENGESJ ALLURE MODES. AND POTENTIAL IMPROVEMENTS OPERATtONAL DAT A 1989 ANNUAL REPORT Nonreactors IN PERFORMANCE.

Accident Sequeme ilotting NUREG-1339 RESOLUTON OF GENERIC SAFETY (SSUE 29 OOLTING NUREGeCR-4674 Vit' PRECURSORS TO POTENTIAL SEVERE CORE DEGR ADATION OR F AILURE IN NUCLEAR POWER PLANTS OAMAGE ACCIDE NTS 1989 A STATUS REPORT Main Repoel And Ap.

poruim A.

C WUREG'CR-4674 V12-PRECURSORS TO POTENTIAL SEVERE CORE R

SK PUT E R AN Ali SIS FOR R APIO DAMAGE ACCIDENTb 1900 A ST ATUS REPORT Appendices O And EVALUATICN OF STRUC TURES)

VERSION 10 Seismic Maduo Theo<etical Manua!

NURcG'CR45BB V02 CARES (COMPUTER ANALYSIS FOR RAPID gging EN ALUATION OF S TRUCTURE S)

VERSION 1.0 Seismic NUREG/CR 5280 Vot, AGE.RELATED DECRADA f TON OF WESilNG.

HOUSE 400 VOLT CIRCU T BRE A1ERS Aging Assessment And Rec-N CARES (CCMPUTER ANALYSIS FOR RAPID EV ALU A TION OF STRUCTURES)

VE RSION 1.0 $cismic NL E C 8 A E AL AT N F LASS 1E BATTER #ES Moctule Sarriple Probtems SEISMIC TE SilNG NUREGICR 546t' AGING OF CABLES, CONNECTIONS. AND ELECTRi' Cable CAL PENE f R ATION ASSEMBUES JSED IN NUCLEAR POWE R NURLO/CR 5461. AGING OF CABLES CONNECTIONS. AND ELECTRi-ENET RA TION ASSEMBLIES USED IN NUCLE AR POWER N

C CR5510 V01: AGING OF CONTROL AND SERVICE AIR COM.

PRESSORS AND DRYERS USED IN NUCLEAR POWER PLANTS NUREG/CR 5583. PREDICTION OF CHECK VALVE PERFORMANCE Check Valve AND DFGRADATION !N NUCLEAR POWER PLANT S YSTE MS NURE G 'P45583 PREDtCTION OF CHECA VALVE PERFORMANCE WE AR ANO IMPACT T EST S final Report Ser.umter 1968 - Apol 1090 AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS b b"*'

Ag ng WWgat6on NUREG 1311 ROI: NRC RESEARCH PROGRAM ON PL ANT AGING Chemical lodustry LISTINGS AND SUMMART S OF REPORTS ISSUED THROUGH MAY NUREGICR $56d V01 INDUSTRY DASED PERFORbNCE INDICA-1990 TORS FOR NUCLE AR POWER PLANTS Phase 1 Report Jane 1M0 >

a7 M Air Compressor NUREG1CR5519 V01 AGlNG OF CONTROL AND SERVICE AtR COM Circuit Dreaker PRESSORS AND DRYERS USED IN NUCLEAR POWER PLANTS NUREG1CR-5260 vot: AGE.RELATED DEGRADATION OF WESTING-HOUSf 480-VOLT CIRCUti BRE AAERS Aging Assessment Arvi Rec-U EG 45 V06 U.S NUCLE AR REGULATORY COMMtSSON IM9 ANNUAL REPORT.

Class 1E Battery NUREG 1363 VO2. ATOMIC SAFET Y AND LICENSING BOARD PANEL NUREGICR $448 AG:NG EVALUATION OF CLASS iE BATTERIES ANNU AL REPORT FtSCAL YE AR 1989 SEISMIC TESTING Apache Leap Tuff Closeout NUREG!CR45% UNSATURATED FRACTURED ROCK CHARACTER NUREG!C45297, CLOSEQUT OF lE OULLETIN 83 05 ASME NUCLEAR IZATION METHOOS AND DATA SETS At THE APACHE LEA? TUFF CODE PUMPS AND SPARE PARTS MANtJF ACTURED BY THE HAY.

SIT E..

W ARD TYLER PUMP COMPANY-Atmospheric Release Concrete Darrier NUREG/CFt 2850 V00 POPULATON DOSE COMV;TMENTS D'JE TO NUREGrCR 5542 MODELS FOn ESTIMATION OF SERWCE LtFE OF RACICACTIVE RFLE ASES FROM NUCLEAR POWER PLANT SffES CONCRETE BARA:ERS IN LOW. LEVEL n ADtOACTIVE WASTE DIS-IN 1D81 POSAL g

Atomc Safety And Licensing Doard Panei Contamment NUREG 13tu V02 ATOM C SAFET r AND LICENSING BOARD PANEL NUREG'CR 5%1: PM DRY CONT AINMENT ISSUE CHARACTER:ZA ANNUAL REPOR' F8 SCAL YE AR IN T!ON

'f 21

22 Subject index NUREG/C84 5575 OUANfif ATIVE ANALYSIS Or POTENTIAL PER-NUREG tW DRFT FC ENVIRONMENTAL ASSESSMENT FOR PRO-FORMANCE IMPROVIMENTS FOR THE DRY PWR CON! AINME NT.

POSED RUC ON NUCLE AR POWER PL ANT UCENSE Containment Heating NUREG/CR 5373 A DE MONST R ATON EXPEniMENT OF STE AM-Esport System DfilVEN, HIGH-FRESSURE MELT t JLCf ON The HIPS 10S Test NL; REG /CP 592 / N EVAL UA TON OF THC EFFECTS OF LDCAL CONTRot ST ATK N DESGIN CONrIGURATONS ON HUMAN PER Containment Integrity F:ORMANCE AND l'UCLE AR POWER PLANT RISK.

NUREG/CR 55?8 AN ASSESSMENT OF DWH MARK 11 CONT AINVENT CHALLENGES FAILURE MOD [S, AND POTENTIAL IMPRGvf MEtCS Erplosive Detector IN PERFORMANCE NUREG 1396 ENVIRON 4 ENTAL ASSESSMENT OF THE THERMAL Control Station Mirrrw AmlTNN EXPLOSIVE DETECTION SYSTEM FOR NUREG/CR4572 AN EVALUATION OF THE EFFECTS OF LOCAL CONCCORSE USE AT U S AIRPORTS CONTROL ST ATION DESGIN CONrlGURATIONS ON HUMAN PER FORMANCE AND NUCLEAR POWER PLANT HISk E sternal E vent NUREG 1407 DRFT FC. PROCEDURAL AND SUBMITTAL GUIDANCE Core Damage FOR INDIVIOUAL PLANT EXAMINATION OF EXTERNAL EVENTS NUREG/GR 4074 Vit: PRECURSORS TO POTENilAL SEVERE CORE (IPEEE) FOR SEVERE ACCIDENT VULNERABillTIES Draft Rooor1 For DAMAGE ACCOENTS 1909 A ST ATUS qi PORT. Main Report And Ap-Comment pendm A NUREG/CR-4674 Vt2 PRECURJORH C POTENTIAL SEVERE CORE Failure Mode DAMAGE ACCIDENTS IfW.* t TJS REPORT Appendces D And NUREG/CR-5528 AN ASSESSMENT OF BWR MARK ll CONTAINMENT C.

CHALLENGES. FAILURE MODES AND POTENTIAL IMPROVEMENTS IN PERFORMANCE Core Concrete NURE G/UR.4794 EXPERIMENT AL RESULTS OF CORE-CONCRETE Fracture Mechan 6ce INTERACTONS USING MOL1EN STEEL WITH ZlRCONIUM NUREG 1239 RESOttff CN OF GENERIC SAFETY ISSUE 29 00LTING Crack Growth DEGnADATON OR FAILURL IN NUCLEAR POWER PLANTS NUREG/CP4112 V01: PROCEEDtNGS OF THE THIRD INTERNATION.

NUREGICR 5451. CRACK-ARREST BEHAVIOR IN SEN WOE PLATES AL ATOMIC ENERGY ADE NCY SPECIALISTS' MEETING ON SUD.

OF LOW UPPER SHELF DASE METAL TESTED UNDER NON!SOTH-CRITICAL CRACK GHOWTH Operung Session And Technica! Session ERMAL CONDITIONS WP 2 SERIES I Hold Al Moscow, USSR May 14 17,1990 NUREG/CR-5554 RECOMMENDATIONS FOR THE SHALLOW-CRACK NUREGICP4112 V02, PROCLEDINGS OF THE THIRD INTERNATION-FRACTURE TOUGHNESS TESilNG T ASK WITHIN THE HSST PRO-AL ATOMIC ENERGY AGENCY SPECIALISTS' MEETING ON EUB-GRAM CRITICAL CRACK GROWTH.Techrucal Sessions 11. til. And IV And NUREG/CR 5596 V01 N1: HEAVY SECTIT4 STEEL IRRADIATON Recommendations And Conclusions Sess6on V. Held At PROGRAM Semiannual Progress Report For Octot;or 1989 March Moscow. USSR.May 14 17,1990.

1990 Crack Arrect liacture TougMess NUREG/CR 5451 CRACK-ARREST DEHAVIOR IN SEN WIDE MTES NUREG/CR 4744 V03 N2. LONG TERM EMBRITTLEMENT OF CAST OF LOW UPPER SHELF BASE METAL TESTED UNDER NON!SOTH-DLIPLEX ST AINLE SS STEELS IN LWR SYSTEMS Semiannual ERM AL CONDITIONS-WP 2 SERIES Report Aoni Septemtaer Hs98 NUREG/CR-5305^ INITLAL ASSESSMENT OF THE MECHANISMS AND EG I 444 V07. THE IMPACT Of t WR DECONT AMIN ATONS CAS LE65 TEEL IN L F S ST MS ON SOLIDIFICATION. WASTE DISPOSAL AND ASSOCIATED OCO NUREG!CR 5554 RECOMMENDATIONS FOR THE SHAll,0W CRACK PATIONAL EXPOSURE FRACTURE TOUGHNESS TESTING TASK WITHIN THE HSST PRO-GRAM Degradat6on NUREG-1339 RESOLUTION OF GENERIC SAFETY ISSUE 29 BMTING DEGRADATION OR F AILURE IN NUCLEAR POWER PLANTS NVREGrCR 5200 vot; AGE RELATED DEGRADATON OF WESTING.

WREG/CR 5254 DIAS IN PEAK CLAD TEMPERATURE PREDICTIONS HOUSE 480 VOLT CIFCUti BREAKERS. Aging Assessmont And Rec,

' 4!E TO UNCERTAINTIES IN MODEL:NG OF ECC DYPASS AND dis-ommmtauons For improvino Dreaker Ruliatality WLVED NON-CONDENSABLE GAS PHENOMENA NUREG/CR 5583 PREDICTidN OF CHECK VALVE PERFORMANCE AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMS Generic Communication WEAR AND IMPACT TESTS Final Report.Septemtsr 1988 Apnl 1990 NUREG-t409 BACAFit flNG GUIDELINES.

Dryer Ceneric Safety issue NUREG/CR 5519 V01: AGING OF CONTROL AND SERVICE AIR COM NUREG-0933 Si1: A PRIOR!T12ATION OF GENERIC SAFETY ISSUES FRESSORS AND DRYERS USED IN NUCLEAR POMR PLANTS Generic Safety lesue 15 Electrical Penetration NUREG/CR 5556. REVIEW OF CURRENT LITERATURE RELATED TO NUREG/CR 5461. AGING OF CABLES, CONNECTIONS. AND ELECTRI' GENERIC SAFETY ISSUE 15 CAL PENETRATION ASSEMBLIES USED IN NUCLEAR POWER PLANTS Generic Safety issue 29 NUREG-1339 RESOLUTION OF GENERIC SAFETY !SSUE 29 BOLTING DEGRADATION OR F AILURE IN NUCLEAR POWER PLANTS U E F 4744 V03 N2: LONG-TERM EMBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS Sermannual HIPS 10S test NUREG/CR $373 A DE AtONSTRATION EXPERIMENT OF STEAM-NU C

5 N L ASSESSMENT OF THE MECHANISMS AND DRIVEN. HIGH-PRESSURE MELT EJECTION The HIPS-10S Test.

SIGNIFICANCY OF LOW-TEMPERATURE i MBRITTLE ME NT OF CAST STAINLESS STEELS IN LWR SYSTEMS HSST Program Enforcement Actions NUREG/CR 5%4 RECOMMENDATIONS FOR THE SMAuGW CRACK NUREG'0940 V09 NO2. ENFORCEMENT ACTIONS SIGNIFICANT AC-FRACTURE TOUGHNESS TESTING TASK WITHIN THE HSST PQO TIONS RESOLVED Ouarterty Progress Report.Apnldune 1990 GRAV Environmental Assessment Heavy-Section Steelirradlation Program NUREO-1396 ENViRONMENI AL ASSESSMENT OF THE THERMAL NUR E G /CR-5591 V91 N1 HE AVY-SECTION STEEL 1RRADIATION NEUTRON ACTIVITATICN EXPLOSIVE DiTECTION SYSTEM FOR PROGRAM Serrmannual Progress Report For October 1989. March CONCOURSE USE AT U S. AIRPORTS 1990

\\

i Subject index 23 High+ressure Mett Streaming =

NUREG/CR4451: CRACK ARREST BEHAVIOR IN SEN WOE LATES

= NUREG/CR.5373 A DEMONSTRATON ' EXPERIMENT OF STEAM-OF LOW UPPER SHELF BASE METAL TESTED UNDER NONtSOTH.

DRIVEN. HIGH-PRESSURE MELT EJECTION.The HIPS 10$ TesL' LRMAL CONDITIONS WP 2 SERIES.

NUREG/CR-5515: UGHT WATER REACTOR PRESSURE ISOLATION VALVE PERFORMANCE TESTING.

p EGl 7 AN EVALUATON OF THE EFFt: CTS OF LOCAL CONTROL STATION DESGIN CONFIGURATONS ON HUMAN PER-Las Cruces Trench Stte FC* NANCE AND NUCLEAR POWER PLANT RISK-NUREGICR4607. FLOW AND TRANSPORT AT THE LAS CRUCES lAEA-TRENCH SITE.Expenments 1 And f NUREG/CP 0112 V01: PROCEEDINGS OF THE THIRD INTERNATION.

NUR G V31 101: INDEXES TO NUCLEAR REGULATORY COM C Tl K O H s

T a Ses MISSON ISSUANCES January-March 1990.

i Heid At Mosenw. USSR Me 14-17 1990.

NUREG/CP-0112 V02: PFiOCkEDINdS OF THE THIPO rdTERNATION-NUREG 0750 V31 N05: NUCLEAR REGULATORY COMMISSION iS-AL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUB.

3UANCES FOR MAY 1990 Pages 371491.

NUREG-0750 V31 N06 NUCLEAR REGULATGRY COMMICSION IS-CRITICAL CRACK GROWTH. Technical Seasons li, m, And IV And Recommerdatens And Cenetusions Sesson V. Held At SUANCES FOR JUNE 1990 Pages 483-604.

NUREG4750 V32 N01: NUCLEAR hEGULATORY COMMISSON di-Moscow,VSSR,May 14-17,1990.

SUANCES FOR JULY 1990 Pages 155.

IE Bulletin 83 05 NVREG/CR 5297; CLOSEOUT OF IE But.LETIN 83 05:ASME NUCLEAR Ucense Renewal

- CODE PUMPS AND SPARE PARTS MANUFACTURED BY THE HAY, NUREG 1362 DAF FC ER. Errata to "Re9ulatory Analysis for Proposed WARD TYLER PUMP COMPANY, Rule on Nuclear Power Plant utense Renewal, Draft Rept for Com-ment," revising Section 7.2 on Page 7-3 to read as hsted.

' ice-Condenser Containment NUREG 1398 DRFT FC: ENVIRONMENTAL ASSESSMENT FOR PRO-NUREG3CR 5589. ASSESSMENT OF ICE CONDENSER CONTAINMEM POSED RULE ON NUCLEAR POWER PLANT LICENSE PERFORMANCE ISSUES.

RENEWALDraft Report For Comment NUREG 1411 RESPONSE TO PUBLIC COMME VTS RESULTING FROM

/C 7

YO NA EQUATE CORE COOUNG IN-R NE STRUMENTATON FOR. UNITED STATES NUCLEAR POWER NUREG-1412 DRFT FC: FOUNDATION FOR THE ADEOUACY OF THE ELAME LICENSIN'l BASES A Supp6ement to The Statement Of consider-Cons For The Pn) posed Rule On Nuclear Power Piant Ucense Re-

~ IndivEl Plant Esamination NUREG-1407 ORFT FC: PROCEDURAL AND SUBM!TTAL CUlOANCE newal(10 CFR Part 54). Draft Report For Comment FOR INDIV" AL PLANT EXAMnNATION OF EXTERNAL EVENTS UC

~

(

e IERE ACCIDENT VULNERABluTIES Draft Report For NUREG NO3 ENSSD OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of February 28,1990(Gray Book I)

Inservice inepection -

NUREGICR-5117; STEAM GENERATOR TUBE INTEGRITY PROGRAM /

Ucensee Event Report STEAM GENERATOR GROUP DROJECT Final Project Summary NUREG/CR-2000 V09 N6. UCENSEE EVENT REPORT (LER)

Report COMPILATON For Month Of June 1990.

NUREG/CR-2000 V09 N7: UCENSEE EVENT REPORT (LER)

Intergranuter Stress Corrosion Crock -

COMPILATON For Month Of July 1990.

NUREG!CR4008. ULTRASONIC INSPECTON REUABluTY FOR IN-NUREG/CR-2000 V09 N8.

LICENSEE EVENT REPORT (LER)

TERGRANULAR. STRESS CORROSON CRACKS.A Round Rotan COMPILATION For Month Of August 1990.

- Study Of 1he Effects Of Personnel, Procedures, Equipment, And Crack Charactenttics 00ht Water Reactor NUREG-080017.3 ROO STANDARD REVIEW PLAN FOli THE REVIEW J R Cum OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER NUREG/CR-5551 ' AN OVsRVTW OF THE LOW UPPER SHELF FLANTS LWR EditeortRevison 0 To SAP Secten 17.3, "Qualty Assur-

. TOUGHNESS SAFETY MAN:,4 (SSUE. -

ance Program Desenption?

NUREG/Cm3J44 V07; THE IMPACT OF LWR DECON!AMINATIONS LER-ON SOUDiFICATON, WASTE DISPOSAL AND ASSOCIATED OCCU-

- NUREG/CR 2000 V09 N6: - UCENSEE. EVENT. REPORT kER)

PATONAL EXPOSURE.

. COMPILATION For Monm Of Joe 1990

~ N' VREG/CR 2000 V09 N7:. UCENSEE EVENT REPORT (LER)

NUREG/CR-4674 V11: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS.1989 A STATUS REPORT. Main Repost And Ap-COMPILATION For Monm Of Juy 1990.

' NUREG/CR-2000 V09 NB: Lt..ENSEE EVENT REPORT (LER) pendm Ac 1 COMPILATION Fer Month Of % p 1990, NUREG/CR 4674 V12. PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS:1989 A STATUS REPORT Appendees B Ar.d LOFT C.

NUREG/lA-0033 ASSESSMENT OF 1RELAP5/ MOD 2-CYCLE 36.04 NUREG/CR 4744 V03 N2: LONG-TERM EMBRITTLEMENT OF CAST AGAINST LOFT SMALL BREAK EXPERIMENT L3 6.

DUPLEX STAINLESS STEELS IN LWR SYSTEMS Somiannual Report.Apni-September 1988 L*N NUREG/CR 5385 INITIAL ASSESSMENT OF THE MECHANISMS AND NUREG-080017.3 ROO STANDARD REVIEW PLAN FOR THE REVIEW SIGNIFICANCli OF LOW TEMPERATURE EMBRITTLEMENT OF

. OF SAFETY - ANALYSIS REPORTS FOR NUCLEAR PCWER CAST STAINLESS $1 EELS IN LWR SYSTEMS PLANTS. LWR Edition.Revison 0 To SRP Section 17.3, "Quahty Assur' NUREG/CR-5451: CRACK ARREST BEHAVIOR IN SEN WIDE PLATES

NI N 44 V07 OE IMPACT OF LWR DECONTAMINATIONS OF LOW UPPER-SHELF BASE METAL TESTED UNDER NONtSOTH-E M^L SW SC"

M FICA WASTE DtSPOSAL AND ASSOCIATED OCCU-NUREG/

ER ACTOR PRESSURE ISOLATION

- NUREG/CR.4674 V11-PRECURSORS TO POTENTIAL SEVERE CORE VALVE PERFOHMANCE TESTLNG.

' DAMAGE ACCIDENTS:1989 A STATUS REPORT.Mac Report And Ap-W CN NUREG/CR 4874 V12: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-525A: BIAS IN PEAK RLAG TEMPERATURE P9EDICTIONS DAMAGE ACCIDENTS:1989 A 13TATUS REPORTAppendices B And DUE TO UNCERTAINTIES IN MODEUNG OF ECC BYPASS AND DIS-C.

SOLVED NON-CONDENSABLE GAS PHENOMENA.

'NUREG/CR 4744 'V03 N2; LONG-TERM EMBRrTTLEMENT OF CAST

. DUPLEX STAINLESS STEELS IN LWR SYSTEMS. Semiannual Loss Ct Coolant Accident Report. April September 1988 NUREG/CR-5395 V11: MULTtLOOP INTEGRAL S'r STEM TEST NVREG/CH-5385: INmAL ASSESSMENT OF THE MECHANSMS AND (MIST) FINAL REPORT. MIST Phase IV Tests SIGNIFICANCE OF LOW-TEMPEHATURE EMBRITTLEMENT OF NUREGICR-539$ VU AD: MULTILOOP INTEGRAL SYSTEM TEST CAST STAINLESS STEELS IN LWR SYSTEMS.

(MIST) FINAL REPOR T. MIST Phase IV Tests.

l

24 Subject index Low Level Radioactive Wasle NURf G'CR $519 VM AG;NG OF CONTROL AND SERVICE AIR GOM NUREG/CR %42 MODELS FOR ESTIMATION Or St NICE LIF E OF PRE SSORS AND DR YE RS USE D IN NUCL E AR POWER PL ANTS CONCRETE DARRiERS IN LOW LEVEL RADIOACTIVE W ASTE D!S-POSAL Operational E vent NURE G'CR 4f ?4 Vi t PRE CURSORS TO POTENTIAL SE VERE CORE Low lev 34 Weste DAM AGE ACCIDE NTS 1%9 A ST ATUS REPORT Mem Reort And An NUREG'CR 5453 V05 BACk GROUND INFORMATION FOR THJ Of-pendix A VROPMENT OF A LOW LEVEL W ASTE PERFORMANCE ASSESS-NURE G'CR 4E ?4 V1 ? PRE CURSOR 5 TO POTE NHAL SEVE RE CORE MENT METHODOLOGY Computer Code implemer" anon And Assess-DAM AGE ACCIDENTS tm A SI ATUS REPORT Appendces b And rNnt C-Low level Weste Disposal Orgata%n Chart NUREG/CR 5532 A PERFORVANCE ASSESSMENT urTHO90tOGy FOR LOW LEVEL WASTE F ACILinES NUREG 03" E a U S NUCLE AR REGULATORv Covv!SStON FUND TION % ORGANi2ATION CH ARTS Ap 15 %0 MIST NUPEG'CR 5395 V11 U. LT! LOOP INTEGR AL SYSTEM TEST PRA (M!ST) FINAL REPORT M s r Pnase IV Tests IJUREG W SPECIAL COMM.TTE E RE CEW OF THE NUCL E AR RE G-NUREG'CR53H V11 C MutitLOOP IN T E GR AL SYSTEM TEST ULATOM COMM!SSION S SEkERE ACCf DE N T R:SKS REPORT (MlST) FINAL REPORT M:sT Phase tv Tests (NUi.Eh t n N Mechanical Property PWR NUREC/CR-5524 VOI TM4 VESSEL INVESTIGATION PROJF CT (V9 NUhEG/CRd5El PWR DRY CONT AINMENT ISSUF CHAR ACit H2A.

MET ALLURG CAL PROGRAM Prqect Report. January.SWtembef TION 1989 NURE G/CR 5575 QU ANTl' ATIVE AN ALYSIS OF POTENilAL PER-FORM AN(.E IMPROVEMENT S FOR THE DRY PWR CONT AiNME NT Metallurgical Program NUREG/CR 5589 ASSESSMENT OF ICE -CONDENhER CONTA!NMENT NUREG/CR 5524 V00 TMb2 VE*SEL INVESitG ATION PROJE CT (vip) pgarORMANCE k,5U'E S ME T ALL URGICA'.

PROGR AM Praiect Report.Jinvary Sephember N

Peak Clad Temperature Molten Core HE G'CR 5254 W AS IN PE AK CLAD TEMPE R ATURE F REDICTIONS NUREO'CR4 % E XPE RIMENT Ai RESULTS CF CORECONCRET E DUE TO UNCERT AiNTIE S IN MODELING Or ECC BY PASS AND D?S-INTERACTIONS USING MOLTEN STEEL WITH ZIRCONIUM SOLNED NON CONDENSABLE GAS PHE NOMENA Multiloop Integral System Test Perft rmance Assessment NUREGICR 5395 V 1 1.

MJLTILOOP lNT EOR AL SYSTEM TEST NUREG'CR 5453 V05 UACKGROUND IM ORM A TION FOR THE DE-(M'ST) FIN AL REPORT VIS e Phase IV Terts VELOPMENT OF A LOW LEVEL n ASTE PE RFORMANCE ASSESS NUREG/CR 5395 V11 AD MULilLOOP lN TEGR AL SYSTEM TEST MEN T METHODOLOGY Computw Code impementation And Aswss-(MIST) FINAL REFORT M:ST Phase IV Tests ment NURE G 'CR-5532 A PERFORM ANCE ASSESSMENT METHODOLOGY Nondestructive Etamination FOR LOW LEVE L W ASTE F ACILIT!E S NURE G-1425 WELDING AND NONDESTRUCTIVE E X AMtN A90N ISSUES AT SE ABROOK NUCLE AR STATION Aq Independent Reww Performance Ristory Team RnM NUREG l' 14 A06 HISTORtCAL DAT A SUMM ARY OF THE SYSTEMAT-IC ASSESSMENT OF LICENSEE PERFORMANCE Nondestructive Tesung NUREG/ CR-4 )08, ULTRAGONIC INSPECTION RELIABILITY FOH IN Performance indicator TERGRANULA STRESS CORROS60N CRACES A Round Roun NUREG 'CR 5568 VD INDUSTRY BASED PERFORM ANCE IND CA-Studv Of The i ts Of Personnel. Procedures, Eqwpment And Cra" TORS FOR NUCLE AR POWER PLANTS PNse t Report Jene 1989 -

Chattenstics Nonreactor NUREG-1272 V04 N02-OFFICE FOR ANALYSIS AND EV ALUATION JF

' U "' '

• • d "9

OPERATIONAL DFA 1989 ANNUAL REPORT Nonreactors NUR E G-0936 VC9 NC2 NRC REu_uLATORY AGENDAOumtem Report AprSJurv 1990 Nuclear Power NUREGICR-5568 V01 INDUSTRY DASED PERFORMANCE INDICA Plant Aomg TORS FOR NUCLEAR POWER PLANTS Phase 1 Reped June 19fi9 NURIO 13N Rot NRC RESE ARCH PROGLAM ON PL ANT AG!NG February 1990 LISTINGS AND SUMMARIES OF REPORTS ISSUED THHOUGH MAY 1990 Nuclear Power Plant NUREG-1362 DhF FC ER Errata to ' Regulatory Anaiysm for Pf 0 posed Plant System Ode on Nuclear Power Plant License Renewa!.Dra't Rept for Com-NUREG'CR$622 AN AL VE'S OF REACTOR TRPS ORtGlNATING IN rnent." reesing Section 7 2 on Page 7-3 to read as hsted BALA.4CE OF P1 ANT SYSTEMS NUREG-13M DHFT FC. ENV:RONVENTAL ASSESSMENT FOR PRO-POSED RULE ON NUCLEAR POWER PLAN T LICENSE Population Dose RENEWALDra't R> port Fr Cumment NUREG sCR 2850 VW POPULATION DOSE COMMITMENTS DUE TO NUREG-1411. RESPONSE TO PUBLIC CCMMENTS RESULTING FROU RADIOACTIVE RELE ASF S FROM NJCLE AR POWE R PLANT SITE S THE PUBLIC WORKSHOP ON NUCL EAR POWER PLANT LICENSE W 1987 RENEW AL NUREG 1412 DAFT FC FOUNDATION EOR THE ADEOUACY OF THE Practice And Procedure Digest LICEWING BASES A Septement to The Statement Of Cons e NUREG 0386 D05 h07 UN'TED ST ATES NUCLE AR REGULATORY atans F The P7 posed Rule On Nxicar Power Plant Lcense Re' CCV WSSION STAFF PR AC TICE AND PROCEDURE newal O c CFR Part $4) D aq Report For Comrner t OlGEST Comss on-Acroai Baard And Licenwg Board NUREG tA 50-(0- OVERv:EW AND COMPAR: SON Cr U S COMMER.

CIAL NUCLEAR POWER Pt. ANTS Notia Power Piant System Sour

" JW "N2 ' "d" "DO#

Pressure isolatbn Valve Occupational Dose Reduction NUREG'CH 5515 LIGHT W ATER RE ACTOR PRESSURE ISDLA fiON NL'ilEGICR-3469 V05 OCCyr ArlONAL DOSE REDUCDON AT NV.

VALVE PERFORMANCE TESRNG CLEAR POWER PLANTS ANNOT ATED WBLIOGRAPHY Or SELECT-ED RE AD1NGS IN RADiAitON PROTECTION AND ALARA Pressure Vessel NUREG'CP 0112 VT FROCEEDINGS OF THE THiHD INTERNATlON Operatmg Espe 6ence AL ATOM:C E NERG r LGENCy SPE Ci ALlS TS MEEilNG ON SUB NUREG-1272 V04 NGO OFFICE FOR AN ALY SIS AND EV A;U ATION CF cru 0C AL Cn ACb GROWTH Openq 9swn AN Tachnical Sess.on OPER ATIONAL DA T A 1W3 ANNU AL REPORT Power Reamm I mW M Mestow USSR Mm 1417.'9 K

-_____s

Subject Index 25 Reactor Safety AGE REcATED DE GRADATON or WE ST'NG NUREG/CP-0)1/ V02 PROCEEDINGS OF THE THIRD INTERNATION-NUREG/CR 5280 V01 AL ATOMIC ENERGY AGENCY SPECIAUSTS' MErhNG ON SUEL HOUSE 480 VOLT CIRCUff DRE AFERS Agmg Assess <twnt And Rec SesMons it ill And IV And umer+ndations I or impong B eaker Rabatery CRtitCAL CRACK GROWTH TKhntCal Recommercations And Concluvens Seswon V Held At 14 17. 1990 Reactor Trip ANALYS;S OF RE ACTOR T8005 OniGINA%G IN Mascow USSRMai CRACK-AhRE ST DEHAVIOR IN SEN WIDE PLATES NUREG'CR 5622 NURE G!CR $451 OF LOW UPPL7 SHELF BASE MET AL TESTED UNDER NONGOTH-BALANCE or PL ANT SYSTEMS ERMAf CONDITIONS WF2 SERtEb NUREGiCR459) V01 N1 HEAVY SECTION STEEL IRRADI ATION Reactor Veneet Or INAPEOJATE CORE CODUNG ;N-Progress Repoq For Ocuer 1969 Manh NUREG/CR 5374 $UMMARY PROGR AM Eewannsat 19M ST RUMENT AllON FOR UN'TE D STATES NUCLEAR POWER PLANTS Pressurtzed Water ReactorPWR DRY CONT AINMENT ISSUE CHARACTER 12A-NUREG/CR 5567 Regulatory Agenda OUANTIT AitvE ANALYSIS Or POTENnAL PER NURf G 0936 V90 N% NRC REGJL ATDAY AGEND A Quartody flON NUREG!CR 5575 FORMANCE IMPROVEME NTS FOR THE DRY PWR CONTAINMEN T Report. Apni June 1990 NUREG/CR4589 AMESSMENT OF (CE-CONDENSER CONI AINMENT PERFORM ANCE ISSUES Reguletory Arietysla NUREG 14J9 BACPJtTTi% UJ1Di. int E Pressurtter Safety And Relief ValveSTUDY OF RELAP5/ MOD 2 CYCLE Report To Congress REPORT TO CONGRESS ON ABNORMAL NUREG1tA 0034 ASSESSMENT 36 04 BASED ON PRESSURi2:_R SAFETY AND RELIEr VALVE NUREG-0090 V13 NDt OCCURRENCES January-March i990 TESTS NUREG.1362 DAF FC ( R En8'a to "Reguiatory Anatygm for Propo ed NUREG-0933 St 1 A PRIOR T12 ATl0N OF GENERIC SATE h !SSU Risk Rule on Nuclear Power Plant Ocense DenewatDrah Rept for Com-rent." reveng f ection 7 2 on Pap 7-3 to red as ImtM NUREG-1412 DRFT FC FOUNDA RON FOR T HE ADEQUACY Or THE Alah Assessment NUREGICR 5572 AN EVALUATION OF THE EFFECTS OF LOCAL UCENSING BASES A Supplement To The (tatement Of Cormier' CONTROL STATION DESGtN CONrlGURATIONS ON HUMAN PER ations For The Propowd Rule On Nucsear Power Piant Leense Re-FORMANCE AND NUCLE AR FOWER PLANT R:SK newal (10 CFR Pa't 54) Draft Report f or Commem Ouality Assurance ROO ST ANDARD REVIEW PLAN FOR THE REVIEVW JREG-0930 V09 N0' NRC REGJ( ATORY AGENDA Owtety NUREG 060017 3 OF SAFETY AN AL YSIS REPORTS FOR NUCLEAR POWER Report.Apnl. June 1990 DLANTS LWR 6dihon Revmon 0 To SRP Section 17.3. "Quakt, Assun Rules Ot Practice ATORY ance Program Desenption" t4UREG-0386 DOS R07. UN:TED ST ATES NUCL E AR REGULPRDC COMMISSION STAFF PRACTWE AND DiGE S t.Commismon, Apper Ro.

Ar.d Lxer%

Bean.)

RELAP5/ MOO 2 NUREG11A-0033 ASSESSMENT OF RE LAPS / MOD 2 CYCLE 36 0 t AGAINST LOFT SMALL BRE AK E1PERIMENT L3 6 Decisons Juh 19 72 Mau t' 1990 NUREGnA-0034 ASSESSMENT STUDY OF RELAPS? MOD 2 CrCLE 36 04 BASED ON PRESSUR!?ER SAFETY AND REUEF V ALVE NUREG 1214 R06 H!STORfCAL DAT A SUMM ARY OF THE SYS GALP TT STS IC ASSESE4ENT OF UCENSEE PER&ORM ANCE Radiation Protection OCCUPATIONAL DOSE REDvCTION Al NU-Sateguarcis Suminary Event List NUREGCR 3469 VOS CLE AR POWER PLANTS ANNOTATED DIOUOGRAPHY OF SELECT-NUREG 0525 R16 SAF FGUARDS

SUMMARY

EVENT UST (SSEL)

ED RE ADINGS IN RADIATION PROTECTION AND ALARA NUREGICR $532 A PERFORMANCE ASSESSMENT METHODOLOGY NUREG 'CR 5552 AN OVEnviEW OF THE LOW UPPER SHELF Sauty Margin Radioactive Weste Disposat TOUGHNESS SAFETY MARGIN ISSUE FOR LOW LEVEL WASTE F AC!UTIES Seistmc Module CARES (COMPtfTER ANALYS b FOR RAPID Rad 6ography WELD!NG AND NONDESTRUCTIVE E XAMIN ATION NUREG!CR 5588 V01 ISSUES AT SE ABROOA NUCLEAR ST ATION An independent Rovw EV A LU ATION OF STRUC'URES VERSION 10 Semmic NUREG-t 425 Moduie Theoretica! ManuW NUREGICR 5588 V02 CARES (COMPUTER ANALYSIS FOR RA Team Report EVALUATION OF STRUCTURES)

VERSION t 0 kruc Radlonuclide Release NUREG/CR4850 V09 POPULAf TON DOSE COMMITMENTS DUE TO Moduo user's Manut CARES tCOMPUTER ANALYS$ FOR RAPtD RADIOACTIVE RELE ASES FROM NUCLEAR POWER PLANT SITES NUREG/CR 5588 V03 NUREG/CR 4624 VC6 RAD 60NUCUDC RELEASE CALCULATICNS EV ALU ATIC54 OF ST RUCTURE S)

VERS!ON 10 Seismic IN 1$67 Module Sampte Probioms FOR SELECTED SEVERE ACCIDENT SCENARh0C Scementaf Cal-CulahOns Se<4rnic Techng ggqga cm44i3 43ING EV ALU A TION OF CL ASS 1E BATTER:E5 Reactor Acetdent B3AS IN PE AK CLAD TEMPERATURE PREDICTIONS SEtSMIC TESTING NUREGtCA 5254 DUE TO UNCERT AlNTIES IN MODELING OF ECC BYPASS ANC DS Service Life SOLVED NON-CONDENSABLE GAS PHENOMENA NUREG/CR 5542 MODELS FOR ESTtMATION OF SERVICE UF NUREG/CR M61 PWR DRY CONT AINMENT ISSUE CHARACTERf 2A-ERS W WWM R@CW WM N E /CR-5589 ASSESSMENT OF ICE CONDENSFR CONT AINMENT

" ^"

N PERFORMANCE ISSUES Severe Acetdent NUREG t 07 DOFT FC PROCEDURAL AND SUUM;FT AL GJiDAME FOR INOMDUAL PLANT EXAMiNAltON OC [ YTERN AL EVr T Reactor Coolant SUVMARY OF INADEOUATE CORE COOUNG IN.

FEEE) FOR SEVERE ACCIDFMT VULNERABluTIES Dra't Report F cc NUREG/CR4374 M RUVENT ATION FOH UN'T E D ST A TE S NUCLE AR POWE n NUWG Lir SPECIAL COMM!TTEE REvlEW OF NE NUCLE AR R Commet.

PLANTS NUREG'CR 5552 AN OVERVTW OF THE LOW UPPER SHELF ULATOR< COMM,SSf0N S SEVERE ACCIDENT M 4S DEPORT Reactor Pressure Vessel (NUM G 11501 TOUGHNESS SAFETY M ARGtN ISSUE

26 Subject index NUREG/CR 4t24 VDG RADIONUCLIDE RELEASE CALCUL ATIONS TLD FOR SEELCTED SEVERE ACCIDENT SCENARIORSupplementa! Cal-NUREG 0837 V10 NO2 NRC TLD DmECT RAD ATION MONITORING culations NETWORK Progress Report Apnl#ne 1990 NUREGICR 557! OUANTff ATIVE AN Aiv SIS OF *OTENTIAL PE R-FORMANCE IMPROVEMENTS FOR THE DRY PWR CONTAINMENT =

Thermal Neutron Activation NUREG 1396 ENv;RONMENTAL ASSC.SMENT OF THE THERM AL Shallow Flaw NEUTRON ACTIVP ATION EXPLOSivt DETECTION SYSTEM FOR NUREG <CR 5554 RECOMMENDATIONS FOR THE SHALLOW CRACK CONCOURSE USE AT U S. A!RPORTS FRACTURE TOUGrMSS TESTING TASK WITHIN THE HSST PRO GRAM.

Thermoluminescen' Dosimeter NUREGoe37 V10 NO2 NGC TLD DIRECT R?DIATION MONITORING Shelf Toughnest NE TWO% Progress Report ApobJune 1990 NURE G /CR-5552 AN OVEnVIE W OF THE LOW UPPE R SHELF 100GHNESS SAF[TY MARGtN lSSJE Title List NUhEr 0540 V12 NM TITLE UST Of DOCUMENTS MADE PUBUCLY Small Dreak Au ULABL E.Ma':n 1 4 1.1990 NUREG 4A.003) ASSESSMENT OF RE AP',! MODE CYCLE 30 0t NiUEG 0540 V12 Noa TITLE LIST OF DOCUMENTS MADE PUOUCLY AGAINS' LOFT SMALL DRE AA EXPERIMENT L3 C AV AILABLE APul 1 30.1000 NUREG-0540 V12 N05 TITLE UST OF DOCUMENTS M ADE PUBUCLY SolLWater Rotention AV A! LADLE May 1 31.1990 NURE G/CR-$607 FLOW AND TRANSPORT AT THE LAS CRUCES NUREG 0540 V12 N06 TITLE UST OF DOCUMENTS MADE PUBUCt.Y TRENCH STTE Ev#nments 1 And g AVAILABLE Jane 1 30.1990 NUREG-0540 Vt2 N07 TITLE UST Or DOCUMENTS MADE PUBUCLY Sourcebook AVAILABLE July 131.1990 NUREG/CR $NO OVERWEW AND COMPARISON OF U S COMWR-Tu int i L NUCLEAR POWER PLANTS Nadear Power Plant Sys;em Sca,,

STE AM GENERATOR GROUP PROJECT.Firw Praiect Summay Stainless Steel Report NUREG/CR 4744 V03 N2 LONG TERM EMDR TTLEMENT OF CAST JRE R 49 JLTR ASONIC INSPECTION REUADlJTY FOR IN-t pr r 108 NUREG/CR 5385 IN!TiAL ASSESSMENT OF THE MECHANISMS AND TERGRANULAR StHESS CORROSION CRACKS A Round Rotun StA Of The ENects Of Per onner. Procedures. Equen+nt. And Crack SIGNIRCAN'E OF LOW-TEMPERATURE EMBR!TTLEMENT OF s

CAST STAINLESS STEELS IN LWR SYSTEMS Characlenstics Unsaturated Fractured Rwk NJREG

?

00- ST ANDARD REV EW PLAN FOn THE REVIEW NUREG/CR-5596 UNSATURATED FRACTURED ROCK CHARACTER-OF SAFETY mNALYSIS REPORTS FOP NUCLEAR POWEA ATION CH@S AW DATA SETS AT M EM N W PLAN'S LWR Ed tion Revisa.in 0 To SRP Secton 17 3. "Quahty Assur-ante Progarn Desmpton?

Unsaturated Zone NUREG/OR 5607. FLOW AND TR ANSPORT AT THE LAS CRUCES N iEG C 617 STE AM GENERATOR TUDE INTEGRf TY PROGRAM /

TRENCH SITE Expenmen's 1 And 2 STEAM GENERATOR GROUP FAOJECT Final Protect Summa 7 Valve Leakage Report.

NUREG/CA-55 5 UGHT WATER REACTOR PRESSURE tSOLATION WUREG/CR 5395 V11 MJLTILOOP IN TEGR AL SYC f E M TEST VALVE PERFORMANCE TEST!NG (MIST) FINAL HEPORT MIST Ptmse IV Tests NUREGICR-5]95 V11 AO. MULTILOOP INTEGRAL SYSTEhr UST Vendor inspection (M ST) FINAL REPORT. Mis t Phase ly Tests NUREG 0040 V14 Not: UCENSEE CONTL ACTOR AND VENDOR IN.

^

Stress Correvon Cracidng NUREGICP4)112 Vot: PROCEED!NGS OF THE THIRD INTERNA! TON Wear And impact AL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUS-NUREGICR 5583. PREDICTION OF CHECK VALVE PEnrORMANCE CR!TICAL CRACK GROWTH Oper9ng Sess:on And Techtwat Sess.on AND DEGRADATION iN NUCLEAR POWER PLANT SYSTEMS i Hold At Moscow. USSR.May 14 17.1990 WE AR ANC MPACT TESTfi Final Report Septemt2er 1983 Apnl 1990.

NUREGICP-0112 V02 PROCEEDINGS OF THE THIRD INTERNATION-AL ATOMIC ENERGY AGENCY SPECIAUSTS MEETi4G ON SUB-Welding CTTICAL CRACK C90WTH Technica! Sasrans Il 111. And IV And NUR E G-1425 WELDING AND NONDESTRUCTIVE EXAMINATION Recommendations - And Conclusions Sessen V Heid At ISSUES Af SEABROOK NUCLEAR STATION An Independent Fieview Moscow. USSR.May 14 17, 1990.

Ted'n Report.

Syr.tamatic Assessment Cf Ucensee Performance Zirconium NUREG-1214 RD6 HISTOntCAL DATA

SUMMARY

OF THE SYSTEMAT-NUREG/CR-4794 EXPERIMENTAL RESULTS Or CONE CONCRETE IC A$aESSMENT OF UCENSEE PERFOAMANCE INTERACTIONS USING mot. TEN STEEL WlTH ZIRCONIUM

=_= _ _ _ _ _

NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by ma or NRC organizations (e.g., program officos) and then by sub-sections of these (e.g., divis!ons, 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.

ATOM!C SAFETY DOARD(S) & PANEL (S)

EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFLGUARDS ATOMIC 5AFETY AND UCENSING BOARD PANEL DNISON OF SAFEGUARDS & TRANSPORTATION (POST 670413)

NUREG 1363 V02 A TOMiC SAFETY AND LICENSING DOARD NUREG-0525 R16. GAFEGUARDS

SUMMARY

EVENT LIST (SGEL)

PANEL ANNUAL REPORT FISCAL YEAR 1989 DIVISION OF INDUS T RIAL & MEDICAL NUCLE AR GAF ETY (POST 870729)

OFFICE OF EXECUTIVE DIRECTOR FOR OPERATONS (EOO)

NUREG-tD96 ENVIRONMENTAL ASSESSMEffT OF THE THERMAL OFC OF THE EXECUTIVE DIRECTOR F OR OPERATIONS NEUTRON ACTIVIT ATION EXPLOStVE DETECTION SYSTEM FOR NUREG-1425 WELDING AND NONDESTRUCTIVE EXAM! NATION CONCOURSE USE AT U S AIRPORTS ISSUES AT SEABROOK NUCLEAR STATIOr. An independent Acve* Team Report U.S NUCLE AR REGULATORY COMMISSION REGION 1 (POST 820201)

OFFICE Of THE GENERAL COUNSEL (POST 860701)

NUREG-0637 V10 N01 NRC TLD D; RECT RAD (ATON MONITORING NUREC-0386 005 R07. UNITED Sl ATES NUCLE AR REGULATORY NETWORK Progress Report Apni, June Ipa COVM SSION STAFF PRACTICE AND PROCEDURE OFC OF ENFORCEMENT (POST 870a13)

OtGE S T. Commission. Appeal Board And bconsing Nant NUREG-0943 V09 NO2 ENFORCEMENT ACTION u SiGNiFICANT AC-Decis,cns Joty 1972 Marct.1990 flONS RESOLVED Ouarterty Progress Report.Ap LJune 1990 OFC OF PERSONNEL (POST 8704131 EDO OFFICE OF NUCLE AR REGULATORY RESEARCH (POST 820405)

NUREG 0325 R14 U. S NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLE AR REGULATORY RESEARCH (PORT B60720)

FUNCTION AL ORGANIZATION CHA.RTS AuguM 15.1990 NUR E Gd 411-RESPONSE TO PUBUC COMMENTS RESULTING FROM THE PUBUC WORKSHOP ON NUCLE AR POWER PLANT U-EDO OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)

CENSE RENEYW AL OF FICE OF ADM NtSTRATON (POST 690205)

NUREG 1420 SPECIAL COMM:TTEE REVIEW OF THE NUCLEAR NUREG-1145 V06-U.S N'JCLEAR REGULATORY CCMM:SSION REGULATORY COMMISSION'S SEVERE ACCOENT R:SKS 1989 ANNUAL REPORT.

RE PORT (NUREG.t 150)

DIVISION OF FREEDOM OF INFORMATION & PUBUCATIONS SERV-DtVISION OF ENGINEERING (POST 870413)

ICES (POST B90205 NUREG-1377 ROI NRC RESEARCH PROGRAM ON PLANT AG!NG NUREG-0540 V12 NO3-TITLE UST OF DOCUMENTS MADE PUBUC-USTINGS AND SUMMARIES OF RF' PORTS ISSUED THROUGH LY AVAILABi,E March 1,3t,1990 M AY 1930.

NUREG 0540 V12 N04 TITLE UST OF DOCUMENTS MADE PUBUC-OlviSIGN OF REGULATORY APPLICATIONS (POST 870413)

LY AVAILABLE Apnl l 30 1990 NUREG 0933 Sit A PRtORIT12ATION OF GENERIC SAFETY NUREG-0540 V12 N05 TITLE UST OF DOCUMENTS MADE PUDUC-ISSUES LY AVA!LABLE Me 1-31.1990 DIVISION OF SAFETY ISSUE RESOLUTION (POST 880717)

NUREG-0540 V12 N06 TITLE UST OF DOCUMENTS MADE PUBUC.

NUREG-1339 RESOLUTION OF GENERIC SAFETY ISSUE 29 BOLT.

LY AVAILABLE. June 1 30. 1990 ING DEGRADATON OR FAILURE IN NUCLEAR POWER PLANTS NUREG 0540 V12 N07 TITLE UST OF DOCUMENTS MADE PUBUC.

NUREw1362 DRFT FC. REGULATORY ANALYSIS FOR PROPOSED LY AVAILABLE July 1 31,1990.

RULE ON NUCLEAR POWER PLANT UCENSE RENEWAL.Dra t r

NUREG 0750 V31101: INDEXES TO NUCLEA"! REGULATORY COM.

Report for Comment MtSS'ON ISSU ANCES JanuanpMarch 1990.

NURLG-1390 DRFT rC. ENVIRONMENT AL ASSESSMENT FOR PRO-NUREG-0750 V31 NOS NUCLEAR REGULATORY MMM!SSiON IS_

POSED RULE ON NUCLEAR POWER PLANT UCENSE RENEW ALDra t Report For Comment r

SUANCES FOR MAY 1990 Pages 371481 NUREG M50 V31 N06 NUCLE AR REGULATORY COMMISSION IS.

NUREG4407 DRF1 FC PROCEDURAL AND SUBMITTAL GUIDANCE SU ANCES FOR JUNE 1990 Page3 483 604 FOR tNDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS NUREG 0750 V32 NGt NUCLEAR REGULATORY COMM:SSON IS-OPEEE) FOR SEVERE ACCIDENT VULNERABlUTIES Draft Report SUANCES FOR JULY 1990 Pages 155.

For Comment NUREG-0936 V09 NO2 NRC REGULATORY AGENDA.Quartarty RepostApnLJune 1990.

EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80)T OntCE OF NUCLEAR REACTOR REGULATtON. DIRECTOR (POS EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATION AL B70411)

DATA NUREG 1412 DAFT FC. FOUNDATION FOR THE ADEOUACY OF OFFICE FOR ANALYS S & EVALUATION OF WERATIONAL DATA. Di.

THE UCENSING BASES A Supplement To The Statement Of Con-RECTOR sidorahons For The Proposed Rule On Nuclear Power Plant Ucense NUREG.0090 V13 Not. REPORT TO CONGnESS ON ABNORM AL Renews (10 CFR Part 54) Draft Report For Comment OCCURRENCESJanuary-March 1990 DIVISION OF REACTOR INSPECTION & SAFEGUARDS (POST NUREG-1272 V04 N01. OFF4CE FOR ANALYSIS AND EVALLATION 8704111 Or OPERATIONAL DATA 1989 ANNUAL REPORT Power Reactort NUREG-0040 V14 Not. UCENSEE CONTRACTOR AND VENDOR IN-NUREG4272 V04 N02. OFFICE FOR ANALYS!S AND EVALUATION SPECTION STATUS REPORT. Quarterly Report.Januay March OF OPERATION At DAT A 1989 ANNUAL REPORT Nenreactors.

1990 NURtG 1404 BACKFITTING GUIDEUNES DIVISION OF UCENSEE PERFORMANCE & OUAUTY EVALUATION (POST B70411)

EDO OFFICE OF INFORMATION RESOUHCES M ANAGEMENT & ARM NUREG 0800 17 3 ROO STANDARD REVIEW Pt AN FOR THE (POST 861109)

REVIEW OF SAFETY ANALYS!S REPORTS FOR NUCLE AR DIVISION OF COMPUTE R & TELECOMMUNICATONS SE RVICES POWER PLANTS LWR Edition nemon 0 To SRP Section 17 3, (POST 890205)

"Quattty Assurance Prmgram Descretion" NUREG 0020 Via NO3 UCENSED OPERAirNG RE ACTORS STATUS NUREG 1214 R36. H!STORICAL DAT A

SUMMARY

OF THE SYSTEM.

SUMMARf REPORT Data As of FeLruary 281990 (Gray Book !)

ATIC ASSESSMENT OF LICENSEE PERFORMANCE 27

m l

O 4

NRC Originating Organization index (International Agreements)

This index lists those NRC organizations that have published international agreement to-ports. The index is arranged alphabetically by major NRC organizations program of-fices) and then by subsections of these (e.g., divisions, branches) where a;, cpriate. 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.

E!4 - OFF6CE OF NUCLE AR REGULATORY RESEARCH (POST 820405)

Olvt90N OF SY STE MS Fit SE ARCH "OST 880717) 06 FiCE OF NUCLt.AH REGut ATORY RESEARCH (POST 9607?cn NURE G 1A-0034 ASSESSMENT Sf UDY Or HELAPS/ MOD 2 CYCLE NUREG/iA4033 ASSESSMENT OF HE LAP 5/ MOO 2 CYCLE 36 04 36 04 BASED ON PRF,SSUR;IER SAFETY AND RELIEF V ALVE AGAiNST LOF1 SMALL BAF A*. EXPER! MEN' L3 6 TESTS i

29

u NRC Contract Sponsor index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) prepared by that organi-zation. Il further information is needed, refer to the main citation by the NUREG/CR number, s

EDO. OFFICE FOR ANALYS 3 & EVALUATION OF OPERAtlONAL NUREGICR-5519 V01. ADNG CF CONTRDL AND SERVICE AIR 1-DATA COMPRESSORS AND DRVERS USED W NUCLEAR POWER OFFICE FOR ANALYSIS & EVALUATION OF OPERATONAL DATA, Db PLANTS RECTOR NUREG/CR 5524 VOI TM4 VESSFL INVESUGATION PROJE CT NUREG /CR 2000 V09 N6. UCENSEE EVENT Ar* ORT (LER)

(V1P) MET ALLURGICAL PROGR AM. Protect hwcNenusy-Septem COMP!LATION For Month Of June 1990 dert999 NUREG /C42000 V09 N7: UCENSEE EVENT REPORT (LE R)

NUREG/CR 5542 MODELS FOR EST!MATION OF SERvtCE UFE OF COMPILATION For Month Of Juty 1990 CONCRETE BARRIERS IN LOW LEVEL RADIOACTIVE W ASTE NUREG/CR-2000 V09 Ne LICE NSEE EVENT REPORT (LE R)

O!SpOSAL COMPIL ATION For Month of August 1990 NUREGICR 5552-AN OVERVIEW OF THE LOW UDPER SHE(F DMSiON OF SAFETY PROGRAMS (POST 870413)

TOUGHNESS SAFETY MARG!N ISSUE NURE G /CR-4674 V11-PRECURSORS TO POTENTIAL SEVERE NUREGICR>5554 RECOMMENDATIONS FOR THE SHALLOW.

CORE DAMAGE ACCIDEN TS 1989 A STATUS REPORT Main CHACK FRAOTURE TOUGHNESS TESTING TASK WITHIN THE Report And Appendu A HSST PROGRAM NUREG!CR 4674 V12 T'RECURSORS TO POTENTIAL SEVERE NUREG!CR-5583 PREDICTION OF CHECK VALVE PERFORMANCE CORE DAMAGE ACCICENTS 1989 A St ATUS REPORT Appeneces AND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS D And C WEAR AND IMPACT TESTS Final ReporLSeptember 1988 Apnl EDO. OFFICE OF HFORM A90N RESOURCES MANAGEMENT & ARM NUFt G/CR-5588 VOI CARES (COMPUTER ANALYSIS FOR nApp EVALUATION OF ST RUCTURES) VE RSION 1.0 Seismic Dtv i i

OMPUTER & TELECOMMUNICATIONS SERVICES Modate Theotexal Manum NUREG/CR 5508 V02. CARES (COMPUTER ANALYSIS FOR RAPC N

/C 25 V09 PODULATION DOSE COMMITMENTS DUE TO RADIOACTIVE RELEASES FROM NUCl. EAR POWER PLANT SITES EVAL.UATION OF STRUCTURES) VERS!ON 10 Seismic

• N0 7' Module User s Manua:

NUREG'CR 5588 V03 CARES (COMPUTER ANALYSIS FOR RAPID EDO OFFICE OF NUCLEAR MATER AL SAFETY & SAFEQUARDS EVALUATON OF STRUCTURES) VERSION 1.0 Seismic DMSON OF HIGH-LEVEL WASTE MANAGEMENT (POST B70413)

Module Sample Probtems NUREG'CR 5453 VOS BACKGROUND INFOROTION FOR THE DE-NUREGrCR 5591 V01 N1 HEAVY SECTON STEEL IRHADIATION VELOPMENT OF A LOW LEVEL W ASTE PERFOW ANCE ASSESS.

PROGRAM Semiannuat Progress Report For October 1969 March MENT METHODOLOGY Computer Code implementa,.m And As 1990 sessment.

NUREG /CR-5500 UNSATURATED FRACTURED ROCK CHARAC.

DMS!ON OF LOW 4EVEL WASTE MANAGEMENT & DECOMM!Sb '3N, TER12ATION METHODS AND DATA SETS AT THE APACHE LE AP ING IPOST 870413:

TUFF StTE NURES/CR-5532. A PERFORMANCE ASSESSMEN T METHODOtt -

NUREGICR 5607. FLOW AND TRANSPORT of THE LAS CRUCES Of FOR LOW-LEVEL W ASTE FACluTIES TRENCH SITE Enpenments 1 And 2 DMSION OF REGULATORY APPUCATIONS (POS' B104131 EDO OFFICE OF % CLEAR REGULATORY RESEARCH (POST 30405)

NUREG/CA-3469 V06 OCCUPATONAt DOSE F EDUCTION AT NU-DMSON OF ENGINEERING (POST 870413)

CLE AR POWER PLANTS ANNOTATED 0:DLhX1RAPHY OF SE.

NUREGICR 3444 V07 THE IMPACT OF LWR DECONTAM: NATIONS LECTED READENGS IN RADIATION PROTECTION AND ALARA ON SOLOlFICATION. WASTE DISPOSAL AND AS5OCIATED OC-DMSION OF SAFETY ISSUE RESOLUTON (POST 8807171 CUPATONAL EXPOSURE.

NUREG/CR-5529 AN ASSESSMENT OF BWR MARK 11 CONTAIN-NUREGICR 4744 V03 N2 LONG-TERM EMBRITTLEMENT OF CAST MENT CHALLENGE S.F AILURE MODES, AND PO TE NTIAL IM-DUPLEX STAl%ESS STEELS IN LWR SYSTEMS Semiannual PROVEMENTS IN PERFORMANCE Report Apni Septemtw 1988 NUREG/CR 5556-REVIEW OF CURRENT LITERATURE RELATED Nb8EG/CR 4908 ULTRASONIC INSPECTlON REUABluTY FOR IN-TO GENERIC SAFETY ISSUE 15 TERGRANULAR STRESS CORROSON CRACKS A Round RM NUREG /CR 5567: PWR DRY CONTAINMENT ISSUE CHARACTER-Study Of The Effects Of Perscnnet Procedures, Equipment, And 12A TION Crack Charrtenst.cs NUREG/CH-5575 OUANTITATIVE ANALYSIS OF POTENTIAL PER-NUREG rCR 5117c STEAM GENERATOR TUDE INTEGR!TY PRO-FORM ANCE IMPROVEMENTS FOR THE DRY PWR CONTAIN-GRAM'STE AM GENERATOR GROUP PROJECT Fra! Progt Sum-MENT mary Report NUREGICH5581 ASSESSMENT Or ICE CONCENSER CONTAIN-i NUREG/CR 5280 V01 AGE-RELATED DEGRADATION Or WES-MENT PERF OPMANCE ISSUES TINGHOUSE 480-VOLT CIRCUlf BREAKERS Aging Assessment DMSION 3r SYRTEMS RESEARCH (POST 880717)

And Recommendahons For Impfwry Breaker Rehabihty NUREG/CR424 V06 RADONUCUDE REtrASE CALCULATIONS NUREG/CR4385 LNITIAL ASSES %fENT OF THE MECHANtSMS FOR SELECTED SEVERE ACCCENT SCENAntOS Supelemental AND SIGNIFICANCE OF LOW TEMPERATURE EMDRITTLEMENT Caeutatons OF CAST STAINLESS STEELS IN LWR SYSTEMS NUREG/CR 4W EXPERMNT AL RESULTS Or CORE CONCRETE NUREGiCR 5448 AGING EVALUATION OF CLASS 1E BATTER'E5 INTERACTONS USING MOLTEN STEEL WITH 21RCONIUM SEISMIC TESRNG NUREG&R $254 BLAS IN PE AK CLAD TEMPERAiURE OREDIC-NUREG/CR 5451. CRACK ARREST BEHAVOR IN SEN WOE TIONS DUE TO UNCERT AINUES IN MODEUNG OF ECC BYPASS PLATES OF LOW UPPER SHELF BASE METAL TESTED UNDER AND DISSOLVED NON-CONOENSABLE GAS PHENOMENA NON!SOTHFRVAL CONDrTIONS WP-2 SER4ES NUREG /C453 /3 A DEMONSTRATION EXPER: MENT Of STE AM-NUREG'CR 5461 AG:NG OF CABLES CONNECTONS. AND ELEC-DRIVEN HIGnPRESSURL MELT EXCTION The M!PS 10S Test TROAL PENETRATION ASSEM9UES USED IN NUCLEAR POWE R NUAEGrCR 5396 Vit MULTILOOP INT EGR AL SYSTEM TEST PLANTS (M!ST) FINAL REFORT M;S T PNse IV Tess NUREG'CR 5515 UGHT W ATER REACTOR PRESSURE iSOLAT;ON NUREG CR-5395 Vi t AO MJLilLOOP INTEGRAL SNSTEM TEST VALVE PERIOF MANCE TESTING (MiSTp ONAL REPOR T MtST Phaso IV Tests 31

32 NRC Contract Sponsor Index NUREGICR 5568 vol. INDUSTRY BASED PERFORMANCE INDICA-DMSiON OF SYSTEMS TEDtNOLOGY (POST 69062h TORS FOR NUCLE AR POWER PLANTS Phase 1 Repert June 1989 NUREG!CR 5374

SUMMARY

OF INADEOuATE CORE COOLING IN Fetswy 1990 S TRUME NT A tlON FOR UN11E D STATES NUCLE Af4 POWER HUREGICR 5572 AN EVALUA110N Or THE Ef FECTS OF LOCAL PL ANT S CONTROL ST ATeON DESGIN CONFIGURAf TONS ON HUMAN NUREG/CR 5622 ANALYSIS OF RE ACTOR TRIPS ORIGINATING IN PERFORMANCE AND NUCLEAR POWER PLANT R1SK BALANCE OF PL ANT SYSTEMS NUREG/CR 5MO OVERVIEW AND COVDATMON OF L' S COM EDO OFFICE OF NUCEEAR REACTOR REGULATION (POST 4/26/80)

ME RCIAL NUCLF AR POWER PL ANTS Nacient Power Piant System O! VISION OF OPERATIONAL EVENTS ASSESSMENT FOST 670411) bO "

NUREG/CR 5297. CLOSEOOT OF IE BULLETIN tG05 ASME NUCLE -

AR CODE PUMPS AND SF-ARE F ARTS MANUF ACTURED BY THE HAYWARD TYLER PUMP COMPANY 1

i

(

)

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

ARGONNE NATIONAL LABORATORY NUREG'CR 5%e Vat' CARES (COMPUTER ANALYSIS FOR R4PO NUREGICP 0112 V01 PROCEEDINGS OF THE THIRD INTERNATnON=

EV ALU AT ON OF S T RUCTURE S)

VE RSION 10 Setsenic AL ATOMtC ENERGY AGENJY SPECIAUSTS M(ETING ON SUB-Macute Theorehear Manual CRITIC %L CRACA GROWTH Opemng Seswon ed Technea! Sesson NUREG/CR 55H8 V02 CARES (COMPUTER ANALYSIS FOR RAPO I Held At Moscow. USSR May 14 17,1990.

EVALUATION OF STRUCTURES)

VERSON t 0 Seismc NUREG/CFt0112 VD2 PROCEEDINGS Or THE THIRD INTERNATON' Maiute Users Manual AL ATOMIC ENERGY AGENCY SPECIALIST $' MEETING ON SUD-NUREG/CR 5586 V03 CARES (COMPLTTER ANALYSIS FOR RAPO CTTICAL CRACA GROWTH Technica: Sesvons it, l!L And IV And EVALUATON OF S T RUCTURES)

VE RSON 10 $eisn r Recommendaws And Conctumons Seuon VHeld At Madote Sampie Petuems Mos:ca USSR May 14-17.1M0 NUREG/CR 5589 ASSESSMENT OF ICE-CONDENSER CONTAINMENI NUREG'CR444 VQJ N7 LONG TERM EMORiTTLE UENT OF CAST PERFORMANCE ISSUES DUPLE x STAINLESS STEELS IN LWR SYSTEMS Smannua!

Re[wt Apni Septamtier IM6 COMMUNIC ATIONS TECHNOLOGY APPLICATlONS,INC.

NURtG!CH $385 INITIAL ASSESSMENT OF THE MECHANISMS AND NUREGICR 5%B V01 INDUSTRY BASED PERCORMANCE INDICA StGN$10ANCE OF LOW.TE MPER ATURE EMBRITTLEMENT OF TORS FOR N JCLE AR POWER PLANTS hate 1 Report June 1989 CAST ST AINLE SS STE ELS IN t.WR SYSTEMS February 1990 NUREG/CR 5024 V01 TML2 VESSEL INVESitG ATION PROJECT MP)

ME T ALLURGIC AL PROGRAM Propict ReporLJanuary Septemtier CONCORD ASSOCIATES,INC.

N9 NUREG'CR 5SM Vot-' INDUSTRY DASED PERFORMANCE INDICA.

RS R NU AR WR WS Maw 1 Repm kne N -

ARI2ONA, UNIY. OF, TUCSON, AZ NUREG/CR 5796 UNSATURATED FRACTURED ROCK CHARACTER.

W IZATON METHODS AND DAT A SETS AT THE APACHE LEAP TUFF EG40 IDAHO, INC. (SUBS. OF EC&G. INC.)

N EG/CR-560L FLOW AND TRANSPORT AT THE LAS CRUCE3 NUREG/CR $440 AGING EVALUATON OF CLASS 1E DATTERIES TRENCH SITC Egenments 1 And 2 ES ESTING DABCOCK & WILCOX CO.

CHALLENGESJ ALLURE MODES, AND POTENTIAL IMPROVEMENTS NUREG/CR 5305 V11' MutitLOOP INTEGRAL SYSTEM TEST IN PERFORMANCE.

(MIST)flNAL REPORT MIST Phase IV Tests NUREG/CR 5542 MODELS FOR ESTIMATION OF SERVICE UFE Of NUREG/CR-5N5 V11 AD MUL11 LOOP INTEGRAL SYSTEM TEST CONCRETE DARRIERS IN LOW LEVEL RADCACTIVE WASTE DIS-(MIST) FINAL REPORT MIST Phase IV Tests POSAL NUREG/CR 5%6 REVIEW Or CURRENT UTERATURE RELATED TO BATTELLE MEMORIAL INSTITUTE COLUMBUS LARORATORIES GENERIC SAFETY ISSUE 15 NUR E GICA-4624 V06 RADIONUCLOE RELEASE CALCULATONS NUREG/CR 5575 OUANTITATIVE ANALYSIS OF PO1ENTIAL PER-FOR SELECTED SEVERE ACCIDENT SCENARIOS Suppiementat CaF FORVANCE IMPROVEMENTS FOR THE DRY PWR CONTAINMENT.

Cutahons BATTELLE MEMORIAL INSTITUTE' PACtFIC NORTHWEST NUREG'CR 55 i5 LIGHT WATER REACTOR PRESSURE ISOLATION

^

NU EG C 650 V09 POPULATON DOSE COMYlTMENTS DUE TO RADIOAOTIVE RELCASES FROM NUCLE AR POWER PL ANT SITES K ALSI ENGINEERING, INC.

N E R-4906 ULTRASONIC INSPECTION REUADILOV FOR IN-

^

T ERGR ANULAR STRESS CORROSON GRACAS A Round Rotun

'^

Stmty Of The ENcts Of Personnel Procedures. Equipment. And Crack

.NU E 5 E STEAM GENERATOR TUDE INTEGRITY PROGRAV/

STEAM GENERATOR GROUP PROJECT Final Project Summary AL ATOMIC ENERG' Y AGENCY SPECIAUSTS MEETING ON SUB-ggg CHITICAL CHACA GROWTH.Openrng Susion And Techncai Sossion

. BROOKHAVEN NATIONAL LADORATORY I Hext At Moscow USSRMay 14 17,1090.

NUREG/CRJ401 V07: THE IMPACT Of LWR DECONTAMiNATIONS NUREG/CP.0112 V02 PROCEEDINGS OF NE THIRD INTERNATON-

-ON SOUDtFICATION. WASTE DISPOSAL AND ASSOCIA TED OCCU-AL ATOMtC ENERGY AGENCY SPEC %USTS' MEETING ON SUD-PATIONAL EXPOSURE.

CRITICAL CRACK GROWTH Technica Sessions it. IR And TV And NUREG/CR4t60 V05. OCCUPATIONAL DOSE REDUCTON AT NU.

Recommendations And Conclusions Sesson V Hewt At CLEAR POWER PLANIS' ANNOTATED BIBLIOGRAPHY OF SELECT.

Moscow. USSR,May 14 17,1990 ED READINGS IN RADIATON PROTECTION AND ALARA NUREGICR 5254. BIAS IN PE AA CLAD TEVPERATURE PREDICTIONS NEW MEXICO STATE UNIV., LAS CRUCES. NM DUE TO UNCERTAINTIES IN MODEUNG OF ECC BYPASS AND dis-NUREG'CR 5607 FLOW AND TRANSPORT AT THE LAS CRUCES SOLVED NON CONDENSA0LE GAS PHENOMENA.

TRENCH SITE E penments 1 And 2.

NUREGICR-5280 Vol AGE RELATED DEGRADATION Or WESTING HOUSE 4BSVOLT CIRCUIT BRE AKERS Agmg Assessment And Rec.

OAK RIDGE NATION AL LABORATORY ommendahens Fce improvmg '3reper Rehability NUREG/CR 2000 V09 N6 UCENSEE - EVENT REPORT (LE R)

NUREGICR 5667. PWR DRY CONT AINMENT ISSUE CHARACTER 12A-COMPtLATON For Month Of June IMO TION.

NUREG/CR 2000 VC0 N7 LICENSEE EVENT REPORT (LER)

NURE G/CR-%72 -AN EVALUATION Of THE EFFECTS OF LOCAL COMPILATION For Month Ot Juh 1990 CON' POL ST ATION DESGJN CONFOURATONS ON HUMAN PER-NUREG/CR 2000 V09 N8 UCENSEE EVENT REPORT tLER)

FORM ANCE AND NUCLEAR POWER PLANT RISK COMPILATON For Month Of August 1990 33

I 1

34 Contractor Index NUREG/CR 4674 V11 PRECURSORS TO POTENTIAL SEVERE CORE SANDtA H ATIONAL EADORATORIES DAMAGE ACCIDENTS 1980 A ST ATUS AEPORT Ma>n Report And AP-NUREG/CR.4794 EXPER: MENT AL RESULTS OF CORE-CONCRE T E IN ERANNS USM MON N WMH NONW N 4

'CR4674 V12 PRECURSORS TO FOTENTIAL SEVEhE CORE NUREG/CR 5373 A DEMONS T R ATION EXPERIMENT OF S TE AM DAMAGE ACCIDE NTS 1989 A ST ATUS REPORT Apperdces D And DRIVEN HIGH PRESSURE MELT FJECTION The HIPS 105 Test i

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NUREG/CR 5374

SUMMARY

Or INADEQUATE CORE COOttNG IN NUREG/CR 5453 VOS BACFOROUND INFORMATION FOR THE DE-ST RUME NT A TION FOR UNITED STAIES NUCLEAR POWER VELOPMENT OF A LOW-LEVEL W ASTE PERF ORMANCE ASSE SS-PLANTS MENT METHODOLOGY Computer Corte impiementation And Aness NUREG/GR S451 CRACh-APREST DEHAv1OR IN SEN WIDE PLATES ment OF LOW-UPPER SHELF BASE ME T AL TESTED UNDER NONLSOTH-NUREG'CR5461 AGING OF CADLES CONNECTIONS AND ELECTRb ERMAL CONDiilONS WP,2 SERIE S NUREG/CR 5519 v01 AGING OF CONTROL AND SERV 1CE AIR COM.

CAL PENETRATION ASSEMBLIES USED IN NUCLE AR POWER PRESSORS AND DRYERS USED IN NUCLE AR POWER PLANTS PLANTS NUREG/CR 5552 AN OVERVIEW OF THE LOW UPPE R SHELF NUREGICA 5532 A PERF ORMANCE ASSE SSMENT ME'THODOLOGY TOUGHNESS SAFETY MARGIN ISSUE FOR LOW LEVEL W ASTE F ACILITIES NURE G'CR 5554 RECOMMENDATIONS FOR THE SHALLOW CRACK FRACTURE TOUGHNESS TESTING T ASA WITHIN THE HSST PRO' SCIENCE APPLICATIONS INTERNATIONAL CORP,(FORMERLY SCIENCE APPLICATIONS, NU E G'CR 5591 VO) N1 HE AVY.SE CTION STEEL IRR ADI ATION NUREG'CR 5622 AN%YSIS OF RE ACTOR TRIPS ORIGINATING IN PROyhAM Semtennual Progess Report For Octotier 1989 Ma ;n BALANCE OF PLANT SYSTEMS 19 %

NURTG!CR %40 OVERVIEW AND COMPARISON OF U S COMMER-

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

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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 proceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

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Vol, 15, No.-3 7, il1LE AND SUbflikt Regulatory and Technical Reports (Abstract Index Journal) 3 DAlt REPORT PUBLISHE D Compilction for l --

December 1990

- Third Quarter 1990 Ju'ly - September

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. 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.

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