ML20095A802

Regulatory and Technical Reports (Abstract Index Journal). Annual Compilation for 1991

ML20095A802
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Issue date:	03/31/1992
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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NUREG-0304, NUREG-0304-V16-N04, NUREG-304, NUREG-304-V16-N4, NUDOCS 9204210071
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NUREG-0304 Vol.16, No. 4 A

Regulatory and Technical Reports

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l Available from Superintendent of Documents U.S. Government Printing Office Post Of' ice Box 37082 Washington, D.C. 20013-7082

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NUREG-0304 Vol.16, No. 4 -

Regulatory and Technical Reports (Abstract Index Journal)

Annual Compilation for 1991 Date Puolished: March 1992 Regulatory Publications Ilranch Division of Freedom ofInformation and Publications Scryices OIYice of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 9,

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CONTENTS Preface.,

........ y Index Tab-Main Citations and Abstracts 1

• Statt Reports

• Conference Proceedings

• Contractor Reports e international Agreement Reports Secondary Report Number index...

,,............,.... 2 Personal Authorindex 3

Subject index.....,

4 NRC Originating Oiganization index (Staff Reports)..

S s.

NRC Originating Organization Index (International Agreements),

.............. 6 NRC Contract Sponsor Index sContractor Reports).,

7 Contractor index...,

8 International Organization Index.

9 Licensed Facility Index,

........ 10-iii l

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

Technical Publications Section Regulatory Publications Branch Division of Freedom of Information and Publicat ons Services i

P 223 U.S. Nuclear Regulatory Commission Washington, D.C, 20555 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG XXXX, NUREG/CP-XXXX, NUREG/CR XXXX, and NUREG/lA XXXX. These precede the following indexes:

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

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor Index (Contractor Reports)

Contractor index International Organization index Licensed Facility Index A detailed explanation of the entries precedes each iddex, The bibliographic eleme of the main citations are the following:

. Staff Report NUREG-0808: MARK 11 CONTAINMEMT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.

ANDERSON. C.J. Division of Safety Technology. August 1981, 90 pp. 8109140048. 09570:200, Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of '

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

Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABil.lTY ENGINEERING IN NUCLEAR REGULATION, JANERP, J.S. Argonne National Laboratory, May 1981,141 pp. 8105280299. ANL-81-3, 08632:070, Where the entries are (1) report ni.mber, (2) report title (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report (7) the NRC Docu-ment Control System accession number, (8) the report number of the originating organization;(9) the microfiche address (for NRC internal use).

Contractor Report -

H NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P,R.

Sandia Laboratories, -May 1981,100 pp,~ 8107010449 SAND 80-0929. 08912:242.

~

Where the entries are (1) report nur'nber, (2) report title, (3) report authors,' (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control Sytem accession number, (8) the report number of the originating organization (if.

given), and (9) the microfiche address (for NRC internal use).

v

Intnrnational Agreement Report NUREG/lA 0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENT AL DAT A. NEUMANN, U. Kraftwerk Union. August 1986. 223 pp. 8608270424. 37659:138 Whose the entries are (1) report number (2) report title, (3) report author, (4) organizational unit of authar, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accesnion number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use).

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

ADD

-addendum APP

- appendix DRFT - draf t ERR errata N

number R - revision S

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

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

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

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

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

O vi

- =

Main Citations and Abstracts The report listings in this cornpilation are arranged by report number, where NUREG XXXX is an NRC staff-originated report, NUREG/CP-XXXX is an NRU-sponsored conference report, NUREG/CR XXXX is an NRC contractor-prepared report, and NUREG/lA XXXX is an inter-national agreement re3 ort. The bibliographic inforrnation (see Preface for details) is followed by a briof abstract of tais report.

NUREG 0020 V16: LICENSED OPERATING RE ACTORS STATUS to the inspected organization dunng the penod from July 1991

SUMMARY

REPORT Data As Of December 31, 1990 (Gray through September 1991 Book l} HARTrlELD,R A Division of Computer & Telecommuni-NUREG 0090 V13 NO3: REPORT TO CONGRESS ON ADNOR.

^ "'

MAL OCCURRENCES July-September 1990.

• Offyce for Analy.

9 0 030 0 87 sis & Evaluation of Operational Data, Director. January 1991, The Nuclear Ra story Commission's annual summa y of li-consed nuclear.

er reactor data is based pnmarily on the 35pp. 9102250192. 56789 010.

report of operatiri.,ata submitted by licensees for each unit for Section 208 of the Energy Reorganization Act of 1974 identi-f>es an abnormal occurrence as an unscheduled incident or the rnonth of December because that report contains data for the month of December, the year to date (in this case calendar event which the Nuclear Regulatory Commisson determines to 1990) and cumulative data, usually froin the date of commercial be significant from the standpoint of public health and safety operation, The data is not independently venfied, but vanous and requires a quarterly report of such events to be made to computer checks are made. The report is d:vided into two sec-Congmss. This report covers the period July 1 through Septem-bor 30,1990. The report discusses six abnormal occurrences, tions The first contains summary highlights and the second contains data on each individual unit in commercial operation.

none of which involved a nuclear power plant. There were five abnormal occurrences at NRC-licensed facilities: one involved a Section 1 capacity and availability factors are simple anthmetic averages. Section 2 Items in the cumulative column are general.

medical therapy misadministration; three involved medical diag-ly as reported by the licensee and notes as to the use of nostic misadministrations; and one involved a significant break-weighted averagos and starting dates other than commercial down in management and procedural controls at a medical facil-operation are provided 4 The sixth abnormal occurrence was reported by an Agree-ment State (Anzona); the ovent involved a medical therapy mis-NURFG-0040 V14 N04: LICENSEE CONTRACTOR AND administration.

VENDOR INSPECTION STATUS REPORT Cuarterfy Report, October December 1990,(White Book) ' D[ vision of Re-NUREG-0090 V13 N04: REPORT TO CONGRESS ON A8NOR.

MAL OCCURRENCESOctober December 1000.

• Office for actor inspection & Safeguards (Post 870411), February 1991.

274pp 9103200057,57062.125.

Analysis & Evaluation of Operational Data, Director. March This periodical covers the results of inspectior;s performed by N 2Qp. 9NMBL SW22.

the NRC's Vendor inspect on Branch that have been distributed Section 208 of the Energy Reorganization Act of 1974 identi-fies en abnormal occurrence as an unscheduled incident or to the inspected organizationb dunng the period from October 1P90 hrough December 1990, event which the Nuclear Regulatory Commission determines to be significant from ;he standpoint of public health and safety NUREG 0040 V15 N01: LICENSEE CONTRACTOR AND and requires a quarterly roport of such events to be made to VENDOR INSPECTION STATUS REPORT. Quarterly Congress. This repoit covers the period October 1 through De-Report. January March 1991.(White Book)

• Division of Reactor cember 31, 1990. The report discusses five abnormal occur-Inspection & Safeguseds (Post 870411). May 1991. 105pp.

rences, none of which involved a nucloar power plant. Two in-(

9105300232. 57863156.

volved sianificant overexposures to the hands of two radio-This periodical covers the resuP.s of inspections performed by graphers, two involved medical therapy misadministrations, and t

the NRC's Vendor inspection Branch that have been d.stributed ono involved a medical diagnostic misadministration. No abnor-to the inspected organization dunng the penod from January mal occurrences were reported by the Agieement States. The 1991 through March 1991, report a:ao contains information that updates a pwviously re-ported abnonnal occurrence, NUREG 0040 V15 N02: LICENSEE CONTRACTOR AND l

VENDOR INSPECTION STATUS REPORT. Quarterly NUREG-0090 V14 Not: REPORT TO CONCRESS ON ABNOR-l Report,Apnt-June 1991.(White Book)

• Division of Reactor In.

MAL OCCURRENCES. January-March 1991.

• Office for Analy-spect$on & Safeguards (Post 870411). September 1991,292pp.

sis & Evaluation of Operational Data, Director. June 1991.21pp, 9110080408. 59310.28 t, 9107220285. 58489:273.

This penodical covers the results of inspections performed by Section 200 of the Enorgy Reorganization Act of 1974 ldenti-the NRC's Vendor Inspection Branch that have been distributed fies an abnormal occurrence as an unscheduled incident or to the inspected organization dunng the penod from April event that the Nuclear Regulatory Commission determines to be through June 1991, significant from the standpoint of public hechh and safety and requires a quarterty report of such events to be mado to Con-HUREG-0040 V15 NO3: LICENSEE CONTRACTOR AND gress. This report covers th penod January thrcugh March VENDOR INSPECTION STATUS REPORT. Quarterly 1991, The report discusses six abr.ormal occurrences, none of Report, July September 1991.(White Book)

• Division of Reactor which involved a nuclear power plant. Five of the events oc-Inspection & Safeguards (Post 870411). Ocicher 1991, ic3pp.

curred at NRC-licensod facilities, one involved a significant deg-9111110275. 59575:187, radation of plant safety at a nuclear fuel cycle facility, one in.

This penodical covers the results of inspections performed by volved a medical diagnostic misadministration, and three in-the N9C*s Vendor invection Branch that have been distnbuted volved medical therapy (nisadministrations. An Agreemont State 1

2 Main Citations and Abstracts (A'uona) reported one abnormal occurrence that envulved me*

NUREG 0327 ROL OWNERS OF NUCLEAR POWER PLANTS.

cal therapy misadministrabons.

WOOD.R S. Office of Nucinar Reactor Regulation. Director NUREG-0000 V14 N02: REPORT TO CONGRESS ON ABNOR.

st BM M N N WWM NM MAL OCCURRENCES Anni-June 1W1

• Othce for Analysis &

The report indicates percentagw ownership of commercial nu-clear power plants by utibty companies. The report includes all Evaluation of Operatonal Data. Director. September 1991.

31pp 9110290332. 59455 243-plants operating. under construction, docketed for NRC safety Section 208 of the Energy Reorgananton Act of 1974 ident" and envwonmental reviews, or under NRC antitrust review, but fees an abnormat occurrence as an unscheduled incKient or does not include those plants announced but not yet under event that the Nuclear Regulatory Commission determinsa to be review or those plants formalty cancelled. Part I of the report significant from the standpoint of putikc health and safety and lists plants alphabetically with their associated applicants or 14 requires a quarterly report of such events to be inado to Con

• consees and percentage ownership Part 11 tists applicants or li-gross = This report covers the penod April through June 1991-t ensees alphabehcally with their associated plants and percent-The ruport discussed five abnormal occurrences, none of which age ownership Part I also indicates which plants have recetved involved a nuclear power plant. Two of the events occurred at operating licenses.

NHC licensed faciht es one involved a potential citicahty accb NUREG-0383 V01 R14: DIRECTORY OF CERTIFICATES OF dent at a nuclear fuel cycle facfhty, and one involvod multiple COMPLIANCE FOR RADIOACTIVE MATERIALS medica! teletherapy misadministrations. The Agreement States PACKAGES Report Of NRC Approved Packages.

• Division of reported three abnormal occurrences, all involving radiation Safeguards & Transportation (Post 870413). October 1991, overexposures The repvt also contains informaton that uo-466pp. 9112310211. 60154:132, dates some pieviously reported abnormal occurrences.

This directory contains a Report of NRC Approved Packages HUREO-0090 V14 NO3; REPORT TO CONGRESS ON ABNOR-(Volume 1). Certificates of Comphance (Volume 2), and a MAL OCCURRENCES July September 1991.

• Office for Anaty-Repwt i NRC Approved Quahty Assurance Wograms tw Ra-ses & Evaluation of Operatonal Data, Director. December 1991, doactive Matorials Packages (Volume 3). The purpose of this 24pp 92011400f 2. 60299.187 directory is to make available a convenient cource of Informa-Section 208 of the Energy Reorgan:Tation Act of 1974 identi-ton on Qualiy Asswance Rograms and Padagg 6 fien $n abnormal occurrence as an unscheduled incident or have been approved by the U.S. Nuclear Regulatorv Commis-esent that the Nuclear Regulatory Commission determines to be aio o Shipments of radcactive material utihzing these packag-Si0nificant from the 1,tandpoint of pubhc health and safety and ings must be in accordance with the provisions of 49 CFR requims a guarterty report of such events to be made to Con-173.471 and 10 CFR Part 71, as apphcable. In satisfying the re-gress. This report covers the period July (thiough September quirem s of Secton N 2, it is the responsibihty of the hcens-1991. The report discusses two abnormal oct,urrences at NRC-ees to insure themselves that they have a copy of the current hconsed facihties, neither involving a nuclear power plant. One approval and conduct their transportaten activities in accord-involved radiaton exposures to members of the pubhc from a ance with an NRC approved quahty assurance program, lost radioactive source and the other involved a medical diag-NUREG-0383 V02 R14: OtRECTORY OF CERTIFICATES OF nostic misadministration. The Agreement States reported no ab-COMPLIANCE FOR RADIOACTIVE MATERIALS normat occurrences. Tho report also contams informaton that PACKAGES.Certshcates Of Compuance.

• Division of Safe-updates some previously rsported abnormal occurrences-guards & Transportaten (Post 870413). October 1991. 610pp.

NUREG 0304 V15 N04: REGULA10RY AND TECHNICAL RE, 92010602n 60203122.

PORTS (ADSTRAC1 INDEX JOURNAL), Annual Compilation See NUREG-0383,V01.R14 abstract For 1990.

• Division of Freedom of information & Publicahons NUREG 0383 V03 R11: DIRECTORY OF CERTIFICATES OF Services (Post 890205). March 1991; 137pp. 9104040288.

5726 0003-COMPLlANCE FOR RADIOACTIVE MATERIALS This }oumal includes all formal reports in the NUREG series PACKAGES R6 port Of NRC Appiovud Quahty Assurance Pro-prepared by the NRC staff and contractors, proccodings of con-grams For Radioactive Materials Packages.

• Division of Safe-forences and workshops; as well as intemational agreement re.

guarris & Transportation (Post 870413). Octotier 1991.153pP, 9112310225. 60153:039.

ports. The entries in this compilaton are indexed for access by title and abstract, secondary report number, perswal author, See NUHEG-0383,V01,R14 abstract.

subject, NRC organization for staff and internationai egree-NUREG 0386 005 R09: UNITEC STATES NUCLEAR REGULA-s ments, contractor, intemahonal organization, and licensed fee TORY COMMISSION STAFF PRACTICE AND PROCEDURE ty.

DIGEST. Commission. Appeal Board And Ucensing Board NUREG-0304 V16 Not: REGULATORY AND TECHNICAL RE-DeciMonc. July 1972 - September 1990.

• Office of the General Post 860701). February 1991. 573pp. 9103200069.

PORTS (ABSTRACT INDEX JOURNAL). Compilation For First 04 0 Quarter 1991, January-March.

• Division of Freedom of Informa-

- This Rehision 9 of the fifth edition of the NRC Practice and i atons S ices (Post 890205). June 1991. 43pp' 07 5

Procedure Digest contains a digest of a number of Commission, See NUREG-0304,V15.N04 abstract' Atomic Safety and Licensing Appeal Board, and Atomw Safety and Licensing Doard decisons issued during the period of July NUREG-0304 V16 NO2: REGULATORY AND TECHNtCAL RE-1.1972 to September 30,1990, interpreting the NRC's Rules '

PORTS (ABSTRACT INDEX JOURNAL). Compilaton For Practice in 10 CFR Par 12.

Second Quarter 1991, April-June.

• Division of Freedom of Infor-46p 91 20 77 24 NUREG-0386 D06: UNITED STATES NUCLEAR REGULATORY I

COMMISSION STAFF PRACTICE AND PROCEDURE See NUREG 0304,V15,N04 abstract.

DIGEST. Commission, Appeal Board And Licersing Decisions. July 1972 - December 1990.

• Office of tne G ineral NUREG 0304 V16 NO2: RECUMTORY AND TECHNICAL RE-Counsel (Post 860701). December 1991. 696pp. 9201140351.

PORTS (ABSTRACT INDEX JOURNAL). Compilaton For Third 60299:246.

Quarter 1991, July. September.

• Division of Freodom of informa-This sikth edition of the NRC Staff Practice and Procedure tion & Pubhcations Services (Post 890205). December 1991.

Digest contains a digest of a number of Commission, Atomic 47pp. 9201000097, 60232:275.

Safe'y and Licensing Appeal Board, and Atomic Safety and Li-See NUREG 0304,V15,N04 abstract.

consing Board decisions issued dunng the period from July 1, 1

1

-~

Main Citations and Abstracts 3

1972 to December 31, 1990 interpreting the NRO's Rutos of NUREG-0540 V13 N04: TITLE LIST OF DOCUMENTS MADE Practice in 10 CFR Part 2. This sath ed, tion replaces in part PUBLICLY AVAILABLE. Apnl 1 30, 1991.

• Divison of Freedom earher edihons and revisions and includes appropnate changes of Information & Pubhcations Seroces (Post 890205). June refiecting the amendrnefits to the Rules of Practice effective 1991. 386pp 9107010133. 58252:076.

d through December 31,1990, See NUREG 0540,V12,N11 abstract.

NUREG 0540 V13 N05: TITLE LIST OF DOCUMENTS MADE NUREG 0430 V10: LICENSED FUEL FACILITY STATUS PUBLICLY AVAILABLE May 1 31, 1991.

• Division of Freedom REPORT. inventory Difference Data July 1989 June 1990.(Gray of Information & Publicatens Services (Post 890205) July 1991.

Book II) BROWN C.; JOY,0 Office of Nuclear Matenal Safety a 335 OS' Safeguards. February 1991.18pp 9103200016. 57066:152 g

PEG 0 5 5M NRC is comrMted to the penodic pubhcation of licensed fuel facihties inventory difference data, tonowing agency review of NUREG-0540 V13 N06: TITLE LIST OF DOCUMENTS MADE the information and completion of any related NRC Invest:ga-PUBLICLY AVAILABLE. June 1 30, 1991.* Dnnsion of Freedom tons information so this report includes inventory difference of information & Publications Services (Post 890205). August data for active fuel febrication facilities possessing more than 1991. 315pp. 9109050321. 58988:187, om effective kilogram of high ennched uranium, low enriched See NUREG-0540,V t2,N11 abstract, uranium, plutonium, or uranium 233.

NUREG-0540 V13 N07: TITLE LIST OF DOCUMENTS MADE NUREG 0525 R17: SAFEGUARDS

SUMMARY

EVENT LIST PUBLICLY AVAILABLE, July 1 31, 1991.

• DNision of Freedom (SSEL) Pre-NRC Through December 31, 1990.

• Dvision of of Information & Pubhcations Services (Post 890205). Septem.

Safeguards & Transportation (Post 870413) July 1991.123pp_

ber 1991. 335pp,9110080399. 59309.306.

9108130182, 58764:182.

See NUREG 0540,V12,N11 abstract.

The Safeguards Summary Event List provides bnef summa' NUREG-0540 V13 N08: TITLE LIST OF DOCUMENTS MADE nos of hundreds of safeguards related events involving nuclear PUBLICLY AVAILABLE. August 1 31, 1991.

• Dvision of Free-matenal or facihties regulated by the U.S Nuclear Regulatory dom of information & Pubhcat ons Services (Post 890205). Oc-Commission. Events are descnbed under the categones: bomb-tobor 1991. 314pp 9110280064, 59449.036.

{

related, intrusion, missing / allegedly stolen, transportation relat' See NUREG4540,V12.N11 abstract.

ed, tampenng/ vandalism, arson, firearms-related, radiological sabotage, non-radiological sabotage, alcohol and drug related NUREG-0540 V13 N09: TITLE LIST OF DOCUMENTS MADE Chrough 1989), and miscellaneous. Because of pubhc interest, PUBLICLY AVAILABLE. September 1-30, 1991.

• Dvision of -

the miscellaneous section also includes eventi reported involv-Freedom of information & Pubitcations Services (Post 800205).

ing source material, byproduct material, an' aatural uranium, November 1991. 299pp. 9112310213. 60165:223.

which are exempt from safeguards requiremer's. Information in See NUREG-0540,V12,N11 abstract.

the event desc6ptions was obtained from official NRC reports.

NUREG 0540 V13 N10: TITLE LIST OF DOCUMENTS MADE NUREG-0540 V12 N11: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. October 1-31, 1991.

• Dvision of Free-dom of Information & Pubhcations Sennces (Post 890205). De-PUBLICLY AVAILABLE. November 1 30,1990.

• Division of comoer 1991c358pp. 9201090195. 60244:285.

Freedom of Informahon & Publications Services (Post 890205)

January 1991. 293pp. 9102040312. 50570.279.

See NUREG-0540,V12 N11 abstract. -

This document is a monthly publication containing desenp-NUREG 0675 S34: SAFETY EVALUATION REPORT RELATED tions of informat on received and generated by the U.S. Nuclear TO-THE OPERATION OF DIABLO CANYON NUCLEAR Regulatory Commission (NRC) This information includes (1)

POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-275 And 50-docketed material associated with cmlian nuclear power plants 323-(Pacific Gas And Electric Company)

ROOD,H.;

and other uses of radioactive matenals, and (2) nondocketed CHOKSHI,N.: MCMULLEN,R.; et al. Division of Reactor Pro}ects matenal received and generated by NRC pertinent to its role as

. - Ill,lV,V (Post 901216), June 1991. 354pp. 9107100057, a regulatory agency. The following indexes are included Per-58383.001.

- sonal Author, Corporate Source. Report Number, and Cross-Supplement 34 *.o the Safety Evaluation Report for the appib Reference to Pnncipal Documents.

cation by Pacific Gas and Electnc Company (PG&E) for licenses i

I to operate Diablo Canyon Nuclear Power Pit.nt, Unit Nosc 1 and NUREG-0540 V12 N12: TITLE LIST OF DOCUMENTS MADE 2 (Docket Nos. 50-275 and 50-323, respectively) has been pre-PUBLICLY AVAILABLE. December 1 31, 1990.

• Ovision fI pared by the Office of Nuclear Reactor Regulation of the U.S.

j' Freedom of Infoimation & Pubhcations Services (Post 890204 Nuclear Regulatory Commission. This supplement documents l

February 1991. 337pp. 9102280245. 56835:269.

the NRC staff review of the Long-Term Seismic Program con-See NUREG 0540,V12,N11 abstract.

ducted by PG&E in response to License Condition 2.C.(7) of Fa-NUREG-0540 V13 N01: TITLE LIST OF DOCUMENTS MADE atng c se PUBLICLY AVAiLABLE. January 1-31, 1991.

• Division of Free-dom C Information & Publications Services (Post 890205).

NUREG-0713 V10: OCCUPATIONAL RADIATION EXPOSURE AT March 1991. 330pp. 9103260124. 57153.035.

COMMERCIAL NUCLEAR POWER REACTORS AND OTHER See NUREG 0540,V12.N11 abstract.

FACILITIES.1988. Twenty First Annual Report. RADDATZ,C.T.

4 Dmsion of Regutatory Applications (Poc' 870413),

NUREG-0540 V13 N02: TITLE LIST OF DOCUMENTS MADE HAGEMEYER.D. Science Applice'ons International Corp. (for.

PUBLICLY AVAILABLE. February 1-28.1991.

• Division of Free-medy - Science Applications, Inc.).

July - 1991. 284pp.

dom of information & Publications Sentices (Post 890205) April

_ 0108190270 58827:261.

1991. 336pp. 9104250053. 57489;113.

This report summarizes the occupational radiation exposure See NUREG-0540,Vt2.N11 abstract.

Information that has been reported to the NRC's Radiation Ex-posure information Reporting System (REIRS) by nuclear power NUREG-0540 V13 NO3: TITLE LIST OF DOCUMENTS MADE facihties and certain 'other categories of NRC licensees during PUBLICLY AVAILABLE. March 1 31, 1991.

• Dvision of Free, the years 1969 through 1988. The bulk of the data piesented in dom of information & Publications Services (Post 890205). May the report was obtained from annual radiation exposure reports 1991. 388pp. 9105210080. 57808:012.

submitted in accordance with the requirements of 10CFR20.407 See NUREG 0540,V12,N11 abstract.

.and the technical specifications of nuclear power plants. Data

\\

4 Main Citations and Abstracts on workers terminating tnoe empl0yrnent at certain NRC L See NUREC N%M J rv05 lbsteset et+rised facilities were obtained f.cm reports submitted pursuant NUREG 0750 V33 NO3: NUCu AR REGULATORY COMMISGION to 10CFR20 408. The 1988 annual reports submitted by about (SSUANCES FOR MARCH 1991.Pages 175-232.

• Division of 429 hcensees 6ndicated that approomately 220.048 individuals Freedoc., of Informaton & Pubhcations Services (Post 890205).

were monitored, 113,000 of whom were monitored by nuclear power facihties. They incuned an average individual dose of May 1991. 64pp. 9105300258 5786th308.

See NUREG 0750,V32,N05 abstract.

0 20 rem (cSv) and an average rneasurable dose of 0.41 (cSv).

Termination radiation exposure reports were analy7ed to reveal NUREG-0750 V33 N04, aUCLEAR RW u, TORY COMMISSION that about 113.072 individuals completed their employment with ISSUANCES FOR APRIL 1981.Prm LQ3 ' Division of one or more of the 429 covered hcerisees dunng 1988. Some Froodom of information & Pubhcatrins SWm '.st 890205).

80.211 of these indsvidua!s terminated from power reactor facab-June 1991. 60pp. 9107010138, 58250114 ties, and about 8,760 of thom wore considered to be transient See NUREG-0750,V32,N05 abstract workers who recorved an average dose of 0 27 rem (cSv).

NUREG-0750 V33 N05: NUCLEAR REC MTar LOMMISSION NUREG-0725 R07: PUBLIC INFORMAT ON CIRCULAR FOR ISSUANCES FOR MAY 1991.Pages 295-459.

• Division of SHIPMENTS OF IRRADIATED REACTOR FUEL.

• Division of Freedom of informte A Pubhcatons Services (Post 090205),

Safeguards & Transportation (Post 870413). January 1991.

August 1991.174pp. 9109050275. 58999:011, 32pp. 9102060142. 56593 209 See NUREG-0750,V32,N05 abstract This circular has been prepared to provkle information on the shement of irradiated reactor foot (spent fue!) aubioct to regula, NUREG 0750 V33 N06: NUCLEAR REGULATORY COMMISSION tion by the Nuclear Regulatory Commission (NRC), and to meet ISSUANCES FOR JUNE 1991.Pages 461-619.

• Division of the requirements of Pubhc Law 96 295, The report provides a Freedom of information & Pubhcations Services (Post 890205) bnef description of NRC authonty for certain aspects of trans.

August 1991.168pp. 9110110237, 59358:124.

porting spent fuel.11 provides desenptive stat;stics on spent fuel See NUREG-0750,V32,N05 abstract.

shipments regulated by the NRC from 1979 to 1989 11 also hsts NUREG-0750 V34 Not: NUCLEAR REGULATORY COMMISSION detaned highway and railway segments used within each state ISSUANCES FOR JULY 1991.Pagas 1148,

• Divtsion of Free-from October 1,1987 through December 31,1989-dom of Information & Pubhcationa Services (Post 890205). Sep-NUREG 0750 V32102: INDEXES TO NUCLEAR REGULATORY tembo; 1991.156pp. 9110100235. 59345:039.

COMMISSION ISSUANCES. July December 1990.

• Division of S^e NUREG 0750,V32,N05 abstract.

Freedom of Informaton & Pubhcations Services (Post 890205).

NUREG-0750 V34 N02: NUCLEAR REGULATORY COMMISSION March 1991. 75pp. 9104250060. 574R8 326.

ISSUANCES FOR AUGUST 1991 Pages 149-183,

• Division of Degosts and indexes for issuances of the Commission, the Freedom of Information & Publications Services (Post 890205).

Atomic Safety and Licensing Appeal Panel, the Atomic Safety October 1991. 41pp, 9110290328. 59455:202.

and Licensing Board Panel, the Administrahve Law Judges, the See NUREG 0750,V32.N05 abstract.

Directors' Decisions, and the Den als of Petit ons for Rulomak-ing are presented.

NUREG-0750 V34 N03: NUCLEAR REGULATORY COMMISSION NUREG-0750 V32 NOS: NUCLEAR REGULATORY COMMISSION O

sion of Freedom of Informaton & Publications Services (Post ISSUANCES FOR NOVEMBER 1990. Pages 333 393.

• Division 890205). November 1991, 52pp. 9201060237, 60202:206.

of Freedom of Information & Pubhcations Se vices (Post See NUREG 0750,V32.N05 abstract 890205). January 1991. 60pp. 9102040114. 56571:212 Logal issuances of the Comm:ssion, the Atomic Safety and Li-NUREC-0750 V34 N04: NUCLEAR REGULATORY COMMISSION censing Appeal Panel, the Atomic Safety and Llcensing Board ISSUANGES FOR OCTOBER 1991. Pages 229-260.

• Division Panel, the Administrative Law Judges, and NRC Program Of-of Freedom of Information & Pubhcations Services (Post -

fices are presented.

800205). December 1991. 38pp. 9201060349. 60202:168.

See EM750M2,N05 aWran NUREG 0750 V32 N06: NUCLEAR REGULATORY COMMISSION ISSUANCES FOR DECEMBER 1990. Pagen 395-49R

• Otvision NUREG 0837 V10 N04: NRC TLD DIRECT RADIATION MONI-of Freedom of Information & Pubbcations %rvices (Post TORING NETWORK. Progress Report October-December 1990.

890205). February 199f.109pp. 9102280216. 50837:023.

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

See NUREG 0750,V32.N05 abstract April 1991. 325pp 9104290263. 57529:208.

NUREG-07L3 V33 tot: INDEXES TO NUCLEAR REGULATORY Tnis report provides the status and results of the NRC Ther-m mmscem Dosimeter M Nct Radawn Wnenng COMMISS!ON ISSUANCES. January-March 1991.

• Division of Network. It presents the radiation levels measured in the vicinity Freedom of Information & Pubhcations Services (Post 890205).

June 1991. 50pp. 9107220263. 58489.153.

of NRC licensed facilities throughout the country for the fourth See NUREG 0750.V32.102 abstract quaw of M NUREG-0750 V33102: INDEXES TO NUCLEAR REGULATORY NUREG-0837 V11 N01: NRC TLD DIRECT RADATION MONI-COMMISSION ISSUANCES. January June 1991,

• Division of TORING NETWORK. Progress. Report January-March 1991.

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

Freedom of information & Pubhcations Services (Post 890205)

October 1991. 87pp. 9110280071. 59448:208.

July 1991. 239pp. 9107220305. 58494:064.

See NUREG-0750'V32.102 abstract ~

This report provides the status and results of the NRC Ther-moluminescent Dosimeter (TLD) Direct Radiation Monitonng NUREG-0750 V33 Not: NUCLEAR REGULATORY COMMISSION Network. It presnots the radiation levels measured in the vicmaty ISSUANCES FOR JANUARY 1991. Pages 160.

• Division of of NRC licensed facihties throughout the country for the first Freedom of Information & Pubhcations Services (Post 890205).

quarter of 1991.

See UE 50 V32 5 a st act~

NUREG-0837 Vit NO2: NRC TLD DtRECT RADIATION MONh TORING NETWORK. Progress. Report. April-June 1991.

NUREG-0750 V33 N02: NUCLEAR REGULATORY COMMISSION STRUCKMEYER,R.; MCNAMARA.N. Region 1 (Post 820201).

ISSUANCES FOR FEBRUARY 1991. Pages61-173.

• Division September 1991. 231pp. 9110080396. 59309.075.

of Freedom of Information & Publications Services (Post This report provides the status and results of the NRC Ther-890205). Apnl 1991.12tpp. 9105160092. 57727:282.

moluminescent Dosimeter (TLD) Direct Radiation Monitoring

I l

Main Citations and Abstracts 5

Network it presents the rad aton levels measured in the vienty NUREG-0930 V09 N04: NRC REGULATORY AGENDA Quarterly of NRC heensed facihties throughout the country for the second Report, October-December 1990.

• Divison of Freedom of Infor-quarter of 1991 maton & Pubhcations Sennces (Post 890205). January 1991.

149pp. # 02250195. 5o789 215.

NUREG-0837 V11 NO3: NRC TLD dip,.

RADIATION MONI-The NRC Regulatory Agenda is a compilaton of all rule 3 on TORING NETWORK Progress Report July September 1991 0

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

December 1991. 231pP. 9201090199 60259 292-This report provides the status and resu!!s of the NGC Ther' mission and are pending depositen by the Commission. The Regulatory Agenda b updated and issued each quarter.

mofuminescent Dosimeter Direct RaSation Monitonng Network, it presents the radiation levels measured in the vicin,ty of NRC NUREG-0936 V10 N01: NRC REGULATORY AGENDA,Ouarterly licensed facihties throughout the country for the third quarter of Report. January-March 1991.

• Division of Freedom of informa, 1991.

tion & Publications Services (Post 890205). April 1991,156pp.

NUREG 0847 S06: SAFETY EVALUATION REPORT RELATED 9105150343 57717:117.

TO THE OPERATION OF WATTS BAR NUCLEAp See NUREG 0936,V09,N04 abstract.

PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50 391.(Ten-nessee Valley Authoritg TAM.P S. Division of Reactor Projects,

HUREG-0936 V10 N02: NRC REGULATORY AGENDA.Ouarterly 1/11 (Post 870411) April 1991.159pp. 9105150345. 57717:273 Rep RAprH-June 1991.

• Division of Freedom of Information &

Supplement No. 6 to the Safety Evaluation Report for the ap-Pubhcations Services (Post 800205). August 1991. 154pp.

plication filed by the Tennessee Valley Authonty for license to 9109050327. 58980.033.

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

See NUREG-093S,V09,N04 abstract.

50-390 and 50 391, located in Rhea County, Tennessee, ha been prepared by the Office of Nuclear Reactor Regulation o' NUREG-0936 V10 NO3: NRC REGULATORY AGENDA.Ouarterly the Nuclear Regulatory Commission. Thu purpose of this sup-Report, July-September 1991,

• Division of Freedom of informa-p!ement is to update the Safety Evaluation of (1) additional in' tion & N.)hcations Services (Post 890205), October 1991, formation submitted by the applicant since Supplement No 5 150pp. 9201060291. 60201:1'il was issued and (2) matters that the staff had under review See NUREG.0936,V09'N04 abstract' when Supplement No. 5 was issued.

NUREG-0940 V09 N04: ENFORCEMENT ACTIONS: SIGNIF1-NUREG-0847 S07: SAFETY EVAL 8tATION REPORT RELATED CANT ACTIONS FitSOLVED.Ouartorly Progress TO THE OPERATION OF WATTS BAR NUCLEAR Report, October-December 1990.

• Ofc of Enforcement (Post PLANT,0 NITS 1 AND 2. Docket Nos. 50-390 And 50-391.(Ten-870413). February 1991, 389pp. 9103050496. 56876 354.

nessee Vailey Authonty) TAM,P.S. Division of Reactor Projects.

This compilation summanzes sigr% cant enforcement actions 1 / 11 (Post 870411). September 1991. 76pp, 9110090253.

that have been resolved during one quarterly period (October.

59329 001.

December 1990) and includes copies of letters, Notices, and Supplement No. 7 to the Safety Evaluation Report for the ap-Orders sont by the Nuclear Regulatory Commission to licensees phcation filed by the Tennessee Valley Authonty for hcense to with respect to these enforcement actons. It is anticipated that operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos, the information in this publication will be widely disseminated to 50-390 and 50-391, located in Rhea County, Tennessee, has managers and employees engaged in activities licensed by the been prepared by the Office of Nuclear Reactor Regulation of NRC, so that actons can be taken to improve safety by avoid-the Nuclew Regulatory Commission. The purpose of this sup.

ing future violations similar to those described in this publica-piement is to update the safety evaluation of (1) additional infor-tion.

mation submitted by the apphcant since Supplement No. 6 was issued, and (2) matters that the staff had under review when-NUREG-0940 V10 N01: ENFORCEMENT ACTIONS: SIGNIF1-Supplement No. 6 was issued.

CANT ACTIONS.

RESOLVED.Ouarterly '

Progress Report, January-March 1991.

• Ofc of Enforcement (Post NUREG 0933 S0112: A PRIORtT12ATION OF GENERIC SAFETY 870413). May 1991. 255pp. 9105210085. 57807:117.

ISSUES, EMRIT,R.; RIGGS.R.; MILSTEAD,W.; et al. Division of This compilaton summanze significant enforcement actions Safety lasue Resolution (Post 880717). July 1991.1,512pp.

that have been resolved dunng one quarterly penod (January.

9108130354 58769 001.

March 1991) and includes copies of letters, Nothes, and Orders See NUREG 0933,S12 abstract.

sent by the' Nuclear Regulatory Commission to licensees with NUREG 0933 S12: A PRIORITIZATION OF GENERIC SAFETY respect to these enforcement actions, it is anticipated that the ISSUES. EMRIT R.; RIGGS,R.:. MILSTEAD,W4 et al Division of informaton in this publication will be widely disseminated to Regulatory Applications (Post 870413). January 1991; 265pp.

managers and empioyees engaged in activities hcensed by the 9101300169. 56536.018.

NRC, so that actions can be taken to improve Ssfety by avoid.

The report presents the pnority rankings for genenc safety ing future violations similar to those desenbod in this pubhca-issues related to nuclear power plants. The purpose of.these

tion, rankings is to assist in the t:mely and efficient allocation of NRC resources for the resolution of those safety issues that have a NUREG-0940 V10 NO2: ENFORCEMENT ACTIONS: SIGNIFi-significant potential for reducing risk. The safety prionty rankings CANT ACTIONS RESOLVED.Ouarterty Progress Repcrt, April.

are HIGH, MEDIUM, LOW, and DROP and have been assigned June 1991.

• Ofc of Enforcement (Post 870413). July 1991.

on the basis of risk significance estimates, the ratio of risk to 392pp. 9109050330. $8985:001.

Costs and other impacts estimated to result if resolutions of the This compilation summanzes signihcant enforcement actions safety issues were implemented, and the consideration of un-that have been resolved during one quarterly period (April -

certainties and other quantitatwe or quahtative factors. To the June 19911 and includes copies of letters, Notices, and Orders extent practical, estimates are quantitative, sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the NUREG-0933 S13: A PRIORITIZATION OF GENERIC SAFETY information in this publicaton will be widely disseminated to ISSUES. EMRIT.R.; RIGGS.R.; MILSTEAD,W.; et al. Dwision of managers and employees engaged in activities licensed by the Regulatory Applicatons (Post 870413). December 1991.386pp.

NRC, so that actions can be taken to improve safety by avoid-9201140354. 60298.072.

ing future violations similar to those described in this puolica.

See NUREG4933 S12 abstract.

ton.

l i

6 Main Citations and Abstracts NUREG-0940 V10 NO3: ENFORCEMENT ACTIONS-SIGNFl.

penses and for the Office of the inspector General fot fiscal CANT ACTIONS RESOLVED Quarterly Progress Report, July-years 1992 1993 bor 19 2 92 2460222 NUREG-1125 V12: A COMPILATION OF REPORTS OF THE AD.

This compliation summanzes significant enforcement actions VISORY COMMITTEE ON REACTOR SAFEGUARDS 1990 i

that have teen resoNvd dunng one quartetty period (July Sep, Annual.

• ACAS Advisory Committee on Reactor Safeguards.

tomber 1991) and includes copies of letters, Notices, and Apol 99L 142pp. 9105150335 57718972 Orders sent by the Nuclear Regulatory Commission to liconsees This compilation contains 31 ACRS reports submitted to the with respect to these enforcement actions. It is anticipated that Commission or to the Executive Director for Operations dunng the infoimation in this pubhcation will be widely disseminated to calendar year 1990, it also includes a report to the Congress on managers and employees engaged in activities licensed by the the NRC Safety Research Program. All reports have been made NRC, so that actions can to taken to improve safety by avoid-availcble to the pubhc through ihe NRC Public Document Room ing future violations similar to those described in this pubhca-and the U.S Library of Congress. The reports are divided into pgn two groups: Part 1: ACRS Reports on Project Reviews, and Part 2-ACRS Reports on Generic Subjects. Part 1 contains ACRS NUREG 0975 V08: COMPILATION OF CONTRACT RESEARCH reports alphabetaed by project name and by chronological FOR THE MATERIALS ENGINEERING BRANCH. DIVISION OF order within project name Part 2 categonzes the reports by the ENGINEERING. Annual Report For FY 1990

• Division of Engi-most appropnate ges, enc subrect area and by chronological neonng (Post 870413). March 1991, 335pp. 9104220205.

order within subject area.

295 NUREG-1144 R02: NUCL EAR PLANT AGING RESEARCH This report presents summanos of the research work per-formed ouring Fiscal Year 1990 by laboratones and organiza-(NPAR) PROGRAM PLAN. Status And Accomphshments.

• Divi-sion of Engineenng (Post 870413). June 1991. 176pp.

tions under contracts administered by the NRC's Matenals Engi' 9107220249. 58400:200 neenng Branch, Office of Nuclear Regulatory Research, Each contractor has written a more complete and detailed annual A comprehensive Nuclear Plant Aging Research (NPAR) Pro-report of its work which can be obtained by writing to NRC; gram was implemented by the U S. NRC Office of Nuclear Reg-however, we beheve it is useful to,have a summary of each ulatory Research in 1905 to identify and resofve technical safety contractor a efforts for the year combined into one volume, issues related to the aging of systems, structures, and compo-nents in operating nuclear power plants. This is Revision 2 to NUREG 0980 V01 N01:

NUCLEAR REGULATORY the NPAR Program Plan. This plan dcfines the goals of the pro-LEGISLATION 101st Congress.

• Office of the General Counsel gram, the current status of research, and summart2es the utilk (Post 060701). June 1991. 495pp. 9108190294. 58829 028.

zation of the research results in the regulatory process. The This document is a compilation of nuclear regulatory legisla, plan also desenbes major milestones and schedules for coordi-tion and other relevant matenal through the 101st Congress, nating research within the agency and with organizations and in-2nd Session, This compilation has been prepared for use as a stitutions outside the agency, both domestic and doreign. Cur-resource document, which the NRC intends to update at the rently, tne NPAR Program composes seven major areas' (1) end of every Congress. The contents of NUREG.0980 include hardware-oriented engineering rescarch involving components The Atomic Energy Act of 1954, as amended-Energy Reorgant.

and structures; (2) system-onented aging interac' tion studies; (3) zation Act of 1974, as amended, Uranium Mill Tailings Radiation development of technical bases for license renewal rulemaking:

Control Act of 1978; low Level Radioactive Waste Pokey Act; (4) determining risk significance of aging phenomena; (5) devel-Nuclear Waste Pohcy Act of 1982; and NRC Authorization and opment of technical bases for resolving generic safety issues; Appropnations Acts. Other matenals included are statutes and (6) recommendations for field inspection and maintenance ad-treaties on export licensing nuclear non-prohferation, and envi.

dressing aging concerns; and (7) residual lifetime ovaluations of ronmental protection.

maior LWR components.and structures. The NPAR technical database compnses approximately 100 NUREG/CR reports by NUREG-0980 V02 N01:

NUCLEAR REGULATORY June 1991, plus numerous published papers and proceedings LEGISLATION 101st Congress.

• Office of the General Counsel that offer regulators and Industry important insights to aging (Post 860701). June 1991. 44Jpp. 9100100333 59052:065.

characteristics and aging management of safety.related equip-See NUREG.0980 V01,N01 abstract, ment. Regulatory applications includa revisions to and develop-NUREG 1022 ROI DR FC: EVENT REPORTIN'l SYSTEMS 10 ment of regulatory guides and technical specifications; support CFR 50 72 AND 50.73 Clantication Of NRC Systems And to resolve generic safety issues; devstopment of codes and Guidehnes for - Reporting Draft Report For Comment standads, ma!uahn of & gnostic techniques (e g., for cables BOARDMAN.J.R.; BOBE,KE.; CROOKS,JL: et al. Office for and valves); and technical support for development of the li-conse reewal Me.

Analysis a Evaluation of Operational Data, Director. September 1991. 229pp. 0110100246. 59336.078.

NUREG-1145 V07; U.S. NUCLEAR REGULATORY COMM;SSION Revision 1 to NUREG 1022 provides clarification of the inime.

1990 ANNUAL REPORT,

• Office of Adminstration (Post diate notihcation requirements of Title 10 of the CodJ of Feder-890205). July 1991. 254pp. 9108290260. 58910:354.

al Regulations, Part 50, Section 50.72 (10 CFR 50.72), and the This report covers the major activities, eveats, decisions, and 30-day wntten licensee event report (LER) requirements of 10 planning that took place dunng fiscal year 1990 within the U.S.

CFR 50.73 for nuclear power plants This revision was initiated Nuclear Regulatory Commission (NRC) or involving the NRC.

to ensure events are reported as required by improving 10 CFR 50.72 and 50 73 reporting guidehnes and to consohdate these NUREG-1150 V03: SEVERE ACCIDENT RISKS: AN ASSESS-guidehnos into a single reference document. This document up.

MENT FOR FIVE U.S. NUCLEAR POWER PLANTS. Appendices dates and supersedes NUREG-1022 and its Supplements 1 and D And E. Final Report.

• Division of Systems Research (Post 2 This document does not change the reporting requirements 880717). January 1991. 93pp. 9102200273. 56744:039.

of 10 CFR 50 72 and 50 73.

This report summanzes an assessment of the risks from -

severe accidents in five commercial nuclear power plants in the NUREG 1100 V07: BUDGET ESTIMATES. Fiscal Years 1992 United States. These risks are measured in a numbcr of ways, 1993.

• Division of Budget & Analysia (Post 890205). February including: the estimated frequencies of core damage accidents 1991.185pp, 9102110174. 56653 037.

from intamally initiated accidents, and externally initiatM acci-This report contains the fiscal year budget justifications to dents for two of the plants; tha performance of containment Congress. Th6 budget provides estimates for salaries and ex.

structures unoer severe accident loadngs; the potential magni-3

Main Citations and Abstracts 7

tude of radonuchde releases and o%te consequences of such NUREG-1214 R08: HISTORICAL DATA

SUMMARY

OF THE SYS-accidents; and the overall rtsk (the product of accident frequen-TEMATIC ASSESSMENT OF LICENSEE PERF ORMANCE.

cses and consequences) Supporting this summary report are a ALLENSPACH,F Orvision of Licensee Performsnce & Quality large number of reports written under contract to NRC which Evaluation (Post 670411). August 1991.122pp 911n090309.

provide the detailed discussion of the methods used and results 59331:209, obtained in these nsk stud,es Volume 3 of this report contains See NUREG 1214,R07 abstract.

two appendices. Appendix 0 summanzes comments received and staff respises on the first (February 1987) draft of NUREG-1232 V03 S02: SAFETY EVALUATION REPCRT ON NUREG-1150 Appendix E provides a similar summary of com.

TENNESSEE VALLEY AUTHORITY. BROWNS FERRY NUCLE-rnents and responses, but for the second (Jur.e 1989) vorsion AR PERFORMANCE PLAN Crowns Ferry Unit 2 Restart.

of the report.

ROSS T.M. Desion of Reactor Projects - t/II (Post 870411).

January 1991,123pp. 0102110178. 56652.274.

NUREG-1199 R02: STANDARD FORMAT AND CONTENT OF A This safety evaluation report (SER) was prepared by the U.S.

LICENSE APPUCATION FOR A LOW 4EVEL RADIOACTIVE Nuclear Regulatory Commission (NRC) staff and represents the WASTE DISPOSAL FACILITY,

• Division of Low. Level Waste second and last supplement (SSER 2) to the staff's onginal Management & Decommission.ng (Post 870413). January 1901-SER published as Volume 3 of NUREG 1232 in April 1989. Sup-30pp. 9102200275. 56744132.

piement 1 of Volume 3 of NUREG-1232 (SSER 1) was pub-The Standard Format and Content of a License Application lished in October 1989. Like its predecessors, SSER 2 is com-for a Low. Level Radioact.ve Waste Disposaf Facility, NUREG-posed of numerous safety evaluatens by the staff regarding 1199, discusses the information to bo provided in the Safety specific elements contained in the Browns Ferry Nuclear Per.

Analysis Report and establishes o uniform format for presenting formance Plan (BFNPP), Volume 3 (up to and including Revision the information required to meet the hcensing requirements for 2h submitted by the Tennessee Valley Authority (TVA) for the land disposal of radioactrve waste as required by 10 CFR 61.

Browns Ferry Nuclear Plant (BFN). The Browns Ferry Nuclear The use of the Standard Format will (1) help ensure that the Plant consists of three boiling-water reactors (BWRs) at a site in Safety Analysis Report (SAR) contains the informaton required Limestone County, Alabama. The BFNPP describes the correc-by 10 CF R 61. (2) aid the applicant in ensuring that the informa-tive action plaris ar.d commitments made by TVA to resolve de-t on is complete (3) help persons reading the SAR to locate in-f ciencies with its nuclear programs before the startup of Unit 2.

formation, and (4) contnbute to shortening the time required for The staff has inspected and will continue to inspect TVA's im-the review process The Standard Format and Content piementation of these BFNPP ccrrect:ye acton plans vliat ad.

(NUREG 1199) ensures that the information required to perform dress statt concerns about TVNs nuclear programs. SSER 2 the revtew is provided. and in a utable format while the Sta -d' documents the NRC staff's safety evaluations and conclusions ard Review Plan, NUREG 1200, defines the technical review for those elements of the BFNPP that were not previously ad-Pmcess.

dressed by the staff or that remained open as a result of urre-NUREG 1200 R02: STANDARD REVIEW PLAN FOR THE solved issues identified by the staff in prevous SERS and in-REVIEW OF A LICENSE APPLICATION FOR A LOW. LEVEL spections.

RADIOACTIVE WASTE DISPOSAL FACILITY.

• Division of Low level Waste Management & Decommissioning (Post NUREG 1266 V05: NRC SAFETY RESEARCH IN SUPPORT OF 870413). January 1991.185pp. 9102200281. 56743:214.

REGULATION FY 1990.

• Office of feuclear Regulatory Re-The Standard Review Plan (SRP) is prepared for the guid-search (Post 860720), April 1991, 69pp. 9105160056, ance of staff reviewers in the Office of Nuclear Matenal Safety 57728.102.

and Safeguards in performing safety reviews of applications to This report, the sixth in a senes of annual reports, was pre-construct and operate a low-level waste disp 3 sal facility. The pared in response to congressional inquines concerning how poncipal purpose of the SRP is to assure the quality and uni, nuclear regulatory research is used, it summari:es the accom-formity of staff reviews and to present a well-defined base from plishments of the Office of Nuclear Regulatory Research during which to evaluate proposed changos in the scope and require.

FY 1990. The goal of this office is to ensure that safety-related monts of reviews. It is also a purpose of the SRP to make infor-research provides the technical bases for rulemaking and for re-mation about regulatory matters widely available and to improve lated decisions in support of NRC hcensing and inspection ac-communication and understanding of the staff's review process tevities. This research is necessary to make certain that the reg-by intorest6d members of the public and the nuclear industry.

ulations that are imposed on licenseos provide an adequate NUREG-1200 consists of 11 chapters containing approximately margin of safety so as to protect the health and safety of the 60 individual SRP sections. Each secten identifies who per.

public. This report desenbes both the d! rect contributions to sci-forms the review, the matters that are reviewed, the basis for entific and technical knowledge with regard to nuclear safety review, how the review is performed, and the conclusions that.

and their regulatory applications.

" "9 NUREG 1272 VOS Not: OFFICE FOR ANALYSIS AND EVALUA-NUREG-1214 R07: HtSTORICAL DATA

SUMMARY

OF THE SYS-TION OF OPERATIONAL DAl A.1990 Annual Report Power TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.

Reactors.

• Office for Analysis & Evaluaten of Operational ALLENSPACH F. Division of Ucenseo Performance & Quahty Data, Director. July 1991. 245pp. 9108130351. 58773:088.

Evaluation (Post 870411). February 1991.117pp. 9103120085.

The annual report of the U.S. Nuclear Regulatory Commis-56948:152.

sion's Office for Anatysis and Evaluation of Operational Data The Histoncal Data Summary of the Systematic Assessment (AEOD) is devoted to the activities performed dunng 1990. The of Ucensee Performance (SALP) is produced penodically by the repart is pubkshed in two separate parts. NUREG-1272, Vol. 5, U.S. Nuclear Regulatory Commission. This summary provides No.1, covers power reactors and presents a overview of the the results of the assessment for each facility by NRC region operating experience of the nuclear power industry from the and is further dividnd into the following sections: Section 1 pre-NRC perspective, including comments about the trends of some sents the most recent SALP report ratings for facihties in oper-key performance measure). The report also includes the princi.

ation and under construction Section 2 presents a chronologi-pal findings and issues idontified in AEOD studies over the past cal listing of all SALP report ratings for each operating facility.

- year and summarizes information from such sources as licensee Section 3 presents a chronological listing of all SALP report rat-event reports, diagnostic evaluations, and reports to the NRC's ings for each facility under construction. Fct historical purposes, Operstions Center. The reports contain a discussion of the inci-past construction ratings for facilities that recently have been li-dent investigation Team program and summanze the Incident censed also are hsted in Sect on 3.

Investigation Team and Augmented inspection Team reports for

8 Main Citations and Abstracts that group of licensees. NUREG-1272, Vof k No 2, covers Technica: Position (Rev 1, November 1970), (2) existing ODCM nonreactors and presents a review of the events and concerns gu<tance; and (3) a reproduction of Genenc Letter 89 01.

donng 1990 associated with the use of heensed matanalin non.

reactor apphcstions, such as personnet overexposuien and NUREG-1302: OFFSITE DOSE CALCULATION MANUAL GUID-medical misadministrabons Each volume conta ns a list of the ANCE: STANDARD RADIOLOGICAL EFFLUENT CONTROLS AEOD reports lasued for 1980 1989 FOR DOILING WATER REACTORS. Generic Letter 89-01,Sup-NUREG-1272 VOS N02: OFFICE FOR ANALYSIS AND EVALUA-piement No.1. MEINKE.W W,; ESStG,T.H. Division of Radiation TION OF OPERATIONAL DATA 1990 Annual Report. Nonteac-Protection & Emergency Preparedness (Post 870411). April tots

• Othee for Analysis & Evaluaton of Operational Data, Db 1991.127pp 9106180015. 58131:030.

rector. July 1991. 96op 9109050303. 58988.134 This report contains guidance which may be voluntarily used See NUREG 1272,V05,N01 nbstr=t by heensees who choose to implement the provision of Genenc Letter 89-01, which allows Radiological Effluent Technical Spec.

NUREG-1275 V06: OPERATING EXPERIENCE FEEDBACK tricatons (RETS) to be removed from the main body of the REPORT SOLENOID OPER ATED VALVE Technical Spec 6hcations and placed in the Offsite Dose Calcula-PROBLEMS Commer"mi oower Reactors ORNSTEIN.HL ton Manual (ODCM) Guidance is provided for standard effluent Office for Anatysis & _.aluation of Operational Data. Director.

controls definitions, controls for effluent monitonng instrumenta-February 1991,116pp. 9103040398. C90-01,56860.174.

tion, controls for effluent releases, controls for radiological envi-This report highhghts sigrdcant operating events involving ronmental monitoring, and the basis for controls. Guidance on observed or potential common-mode failures of solenoid-operat-the formulation of RETS has been available in draft form ed valves (SOVs) in U S. Plants. These events resulted in dug-(NUREG 0472 and -0473) for a number of years; the current radation or malfunction of mu!tiple trains of safety systems as effort simply rocasta those RETS into standard radiological ef-well as of multiple safety systems On the basis of the evalua-fluont controls for application to the ODCM. Also included for hon c1 these events, the Office for Analysis and Evaluation of completeness are: (1) radiological environmental monrtoring pro-Operational Data (AEOD) of the U.S Nuclear Regulatory Com-gram guidance previously which had been available as a Dranch mission (NRC) concludes that the problems with solenoid oper.

Technical Position (Rev.1, November 1970); (2) existing ODCM ated valves are an important issue that needs additional NRO guidance; and (3) a reproduction of Genonc Letter 09 01, and industry attention. This report also provides AEOD's recom-mondations for actions to reduce the occurrence of SOV NUREG-1303 R01: INCIDENT INVESTIGATION MANUAL common modo failures.

Office for Analysis & Evaluation of Operational Data, Director.

NUREG 1293 Rot: OUALITY ASSURANCE GUIDANCE FOR A November 1991,122pp. 9201060103. 60212:001, LOW LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY, The incident investigation Manual presenbes guidehnes for PITTIGLIO.C L; HEDGES,D. Driision of Low Level Waste Man, the conduct of investigatwe actwities of the U.S. Nuclear Regu-agement & Decommissioning (Post 870413L Apot i991,22pp, latory Commission (NRC) incident Investigation Teams (IITs).

9105030134, 57617:290.

The purpose of this manual is to provide llTs guidance to This document provides guidance to an apphcant on meeting ensure that NRC investigations of significant events are timely, the quality contivi (OC) requirements of 10 CFR 61.12(j) for a structured, coordinated, and formally administered. The guide-low-level radioactive waste (LLRW) disposal facihty. Tho OC re, hnes are iMunded to assist the investigation rather than hmit the quirements, plus audits and managerial controls 'reautrements, initiatives and good judgment of the lli leader or members. The estabhsh the need for developing a quality assurance (OA) pro.

IIT leader and team members should use their expenence and gram and the guidance provided herein, The criteria developed those techniques that provide the most confidenco in assunng for this document are similar to the critena developed for Ap, the lit oblectives are achieved. These guidehnes addren llT pendix B to Title 10 of the Code of Federal Regulations (10 activation, conduct of the investigation, corxtucting ir terviews, CFR) Part 50. Although Appendix B is not a regulatory require.

treatment of quarantined equipmnnt, preparation of the tesim ment for an LLRW disposal facihty, the criteria that were devel, report and followup of staff actions.

oped for 10 CFR Part 50 are basic to any OA program. This document estabhshes OA guidance for the design, construction, N'IREG 1307 R02-REPORT ON WASTE DURIAL and operation of those structures, engineered or natural sys-CHARGES EscalatEn Of Decommissioning Waste Desposal Costs At Low-Level Waste Burial Facihties.

• Division of Regula-perto'r ance b ctiv s f ubp of 0 CF Part 6 a tory Applications (Post 870413). July 1991. 42,pp. 9108130285.

e hmit exposure to or release of radioactivity.

58 65 108 NUREG 1301: OFFSITE DOSE CALCULATION MANUAL GUID-ANCE: STANDARD RADIOLOGICAL EFFLUENT CONTROLS licensees by the U.S. Nuclear Regulatory Commission (NRC) is FOR PRESSURIZED WATER REACTORS Generic Letter 89-for the hcensees to penodically adjust the estimate of the cost 01, Supplement No.1 MEiNKE,W.W,; ESSIG.T.H. Division of of decommissioning their plants, in dollars of the current year.

as part of the process to provide reasonable assurance that Radiation Protection & Emergency Preparednoss (Post B70411) adequate funds for decorrnissioning -will be available when Apnl 1991.122pp. 9107100056. 58384:001, This report contains guidance which may be voluntarily used needed, This report, which is scheduled to be revised annualty, by licensees who choose to implement the provision of Generic contains the development of a formula for escalating decom-missioning cost estimates that is acceptable to the NRC, and Letter 89-01, which allows Radiological Effluent Technical Spec-contains values for the escalabon of radioactive waste burial ifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calcula-costs, by site and by year. The hcensees may use the formula, tion Manual (ODCM). Guidance is provided for standard effluent the coefficients, And the bunal escalation from this report in their escalation analyses, or they may use an escalation rate at controls def nitions, controls for effluent monitoring instrumenta-least equal to the escalation approach presented herein. Revi-tion, Controls for effluent releases, controls for radiological envi-sion 2 of this report corrects several errors in the calculations ronmental monitonng, and the basis for controls. Guidance on and disposal costs for the reference PWR and the reference the formulation of RETS has been available in draft form BWR.

(NUREG-0472 and -0473) for a number of years; the current effort simply recasts those RETS into standard radulogical ef.

NUREG-1321: TESTING STANDARDS FOR PHYSICAL SECURI-fluent controts for application to the ODCM. Also included for TY SYSTEMS AT CATEGORY l FUEL CYCLE FACILITIES, completeness are: (1) radiological environmental monitoring pro-DWYER,P.A. Division of Safeguards & Transportation (Post gram guidance previously which had been available as a Branch 870413). October 1991,27pp. 9110280044. 59455:043.

1

Main Citations and Abstracts 9

This report is a cornpilahow of physical security testmg stand-NUREG 1369: PREAPPLICATION SAFETY EVALUATION ards for use at fuel cycle fa::ilities using or possessing fortnuta REPORT FOR THE SODIUM ADVANCED FAST REACTOR quantities of strategic special nuclear mr.tenal.

(SAFR) LIOUlO METAL REACTOR. KING.T.L. Office of Nucleai Rogulatory Research (Post 860720).

LANDRY,R.R.;

NUREG 1322: ACCEPTANCE CRITERIA FOR THE EVALUATION THROM.E.D.; et at Office of Nuclear Reactor Regulabon, Derec-OF CATEGORY I FUEL CYCLE FACILITY PHYSICAL SECURI-tor (Post 870411). December 1991. 267pp. 9201060347.

TV PLANS, DWYER,P.A. Division of Safeguards & Transpor*a-60201:261.

tion (Post 870413) October 1991. 32pp. 9110280054.

This safety evaluation report (SER) presents the final results

$9455 007, of a preapplication design revie.v for the Sodium Advanced Fast This report presents cntena developed from U.S Nuclear Reactor (SAFR) hquid metal reactor (Project 673) The SAFR Regulatory Commission regulabons for 'he evaluation of phys" conceptual desigr was submitted by the U.S. Department of col security plans rubmitted by Categor) I fuel facility licensees.

Energy (DOE) In acccidance with the U.S. Nuclear Rogulatory Category I refers to those beensees who use or possess a for-Commission (NRC) " Statement of Pohey for the Regulation of mula quantity or stzategic special nuclear materiat Advanced Naclear Power Plants" (51 FR 24643) which provides for the earty Commiwion review and interacbon. The standard NUREG 1350 V03: NUCLEAR REGULATORY COMMISSION IN' SAFR plant design consists of four identical reactor modules, F ORM ATION DIGEST 1991 Edition. OLIVE,K L Division of referred to as "paks," each with a thermal output rating of 900 '

Budget & Analysis (Post 800205). March 199t. 102w MWt, coupled with four steam turbine-generator sets. The total 9104200009. 57529:029.

electncal output was to be 1400 MWe. This SER represents the The Nuclear Regulatory Commission information Digest pro.

NRC staff's prehminary technical evaluation of the safety fea-vidos a summary of informahon about the U S. Nolear Regula-tures iri the SAFR design, it must be recognized that final con-tory Commission (NRC), NRC's regulatory responsibilities, and clusions in all matters diset 'ed in this SER require approval by the areas NRC licenses. This digest is a compdation of NRC-the Commission. Dunng the NRC staff review of the SAFR con-related data and is designed to provide a qwck reference to ceptual design, DOE terminated work on this design in S3ptem-major facts about the agency and the industry it regulates. M ber 1968. This SER documents the work done to that date and general the data cover 1975 through 1990, with exceptions no additional work is planned for the SAFR.

noted For operating U.S commercial nuclear power reactors, information on generating capacity and average capacity factor NUREG-1374: TECHNICAL FINDINGS RELr TO GENERIC is obtained from monthly operat.ng reports subrmtted to the ISSUE 79 An Evaluebon Of PWR Rep essel Thermal NRC directly by the licensee. This information is reviewed for Stress Dunng Natural Convection Cooide

. 3E,J.D. Division consistency only. No independent validation and/or venfication of Safety Issue Resolution (Post 8807U

..ay 1991.149pp.

is performed by the NRC. For detailed and comptote information 9106180011. 58130:241, about tables and figures, refer to the source publicabons. This This report summanzes work performed.s the Nuclear Regu-digest is pupshed annually for the general use of the NRC staff latory Commission staff to resolve Generic lasue 70, "Unana-and is available to the public.

lyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown (NCC)? The report evaluates the effects NUREG 1362: REGULATORY ANALYSIS FOR FINAL RULE ON of an NCC event on PWR reactor vessels (RVs), with particular NUCLEAR POWER PLANT LICENSE RENEWAL. Final Report.

• emphasis on the closure !!ange regiort A conservauve inde-Division of Safety issuo Resolution (Post 880717). December pendent confirmatory st ess analysis of a B&W 177. fuel as-1991. 200pp. 9201060099. 60197;184c sembly RV (b&W 177) was performed by the NRC contractor, This regulatory analysts provides the supporting information and an independent fracture mechanics evaluation was per-for the final rue (10 CFR Part 54) that defines the Nuclear Rog-formed by the staff, Based on these and a comparison of geo-ulatory Commission's requirements for renewing the operahng 16 metric sim'larity between the B&W 177 and other PWR RVs the censes of commercial nuclear power plants. A set of four spe-

. NRC staff developed findings that are applicable to all U.S.

cific Pltemativer for the safety review of license renewal appli' PWRs.

cabons is defined and evaluated. These are: Altomative A-cur-rent hcensing basis; Alternative B extension of Alternative A to NUREG-1375 V02: SAFETY EVALUATION REVIEW OF THE require assessment and managing of aging; Attemative C-ex-PROTOTYPE LICENSE APPLICATION SAFETY ANALYSIS tension of Altemative B to require assessment of design differ-REPORT.Balowground Vault.

• Division of Low-Level Waste ences against selected new-plant standards using probabilistic Management & Decommissioning (Post 870413). September j

risk assessment; and Altemative D--extension of Attemative B 1991. 52pp. 9110100255. 59336:344.

to require compliance with all new-plant standards. A quantita-The U.S. Nuclear Regulatory Commission (NRC) staff and live comparison of the four afternahves in terms of impact-to-consultants reviewed a Prototype License Applicaton Safety value tabo is presented, and Attemative B is the most cost-ben-Anafysis Report (PLASAR) submitted by the U.S. Department of ehcial safety review attemative.

Energy (DOE! for the be4owground vault (BGV) alternative method of low level radioa.:t ve waste disposal, in Volume 1 of NUREG-1363 V03: ATOMIC SAFETY AND LfCENSING BOARD NUREG 1375, the NRC staff provided the safety review results PANEL ANNUAL REPORT. Fiscal Year 1990. COTTER,B.P.

for an earth-moundod concrete bunker PLASAR. In the current Atomic Safety & Licensing Board Panel. September 1991.33pp.

report, the staff focused its review on the design, construction, 9 t t 1070099. 59549.152, and operational aspects of the BGV PLASAR. The staff devel-In Fiscal Year 1990, the Atomic Safety and Licensing Board oped review comments and questions using the Standed Panel (Panet) handled 40 proceedings involving the construc-Review Plan (SRP), Rev.1 (NUREG 1200) as the basis for eval-tion, operabon, and maintenance of commercial nuclear power uating the acceptability of the information provided in the BGV reactors or otner activities requiring a heense from tha Nuclear PLASAR. The detailed review comments provided in this report Regulatory Commission This report summanzes highhghts, and are Intended to be useful guidance to facihty developers and analy7es how the wide ranging issues raised in these proceed' State regulators in addressing issues likely to bu encountered in ings were addressed by the Judges and Licensing Boards of the reew of a hcense apphcetion for a low level waste dispos-the Panel during the yeah al facihty.

~

. -,. ~,

10 Main Citations and Austracts NUREG 13FT R02: NHC RI SEARCH PROGRAM ON PL ANT NUREG 1398: ENVIRONWNT AL ASSESSMENT F OR FINAL AGING llSilNG At4D SUMMARIES OF REPOR1S ISSUID RULE ON NUCLEAR POWER PLANT llCLNSE THROUGH JUf401991 KONDic N N ; Hit L.E L Diviuon of En-RENEWALFinal Report

• Dwiston of Smety issue Resolution guieonog (Pot,t 670413) Juty 1991 92pp-9108130174 IPost 8150717). December 1991. 64pp 929106028 t. 60201:052 68746 214 The possible enyttonmental eHects of promulgating tsuolear lhe U S Nacleat Reguletory Comewsion is conducting the power plant bcense renewal standards by the final rule,10 CF R Nucleuf Plant Aging Research (NPAR) Prog'am 1tus is a com-Part $4, rather than applying requiremertts in an ad hoc mannet Diehenuve haidee. Often'ed engineering fesearch program in indwidual hcensing actioris, are assessed The tule tcQu'res facusod on under andtng the agirtg mtKhanstmt of compo.

the development of informahon and ar,aiyses to idontify aging not ts and syt,terna in nucicar power plants The NPAR program probitms of systems, structures and componeritt that will be of n'so focuses on methods for simulahng ed monitoring the concern dJring the tenewal term and will not be controllert by agirig telated degradation c,f these comWr ents and egems susting regulatory programs, Required actons may be replace-In addition, et provides recommendations vor effective mainte-mont refurbishment, inspection, testin0 or monitoring Such ac.

riante to manage aging and for the impittrrentction ws the re-tions will generally be within the range of simivat actions taken semich results in the regfatory procols 1th documant con-for plants dunng the initial operating term. They would be pri-tains a hshng and indes of reports generated in the NPAR pro-matlly conhn4J within the plants with potential tot only rninor psm that were issued through June 1991 and summanos of disruptiori to the environment. it la unkkely that these octons those teports. Etch summary doetit es the elements of the re-would change the environenental effects atteedy beng esperi.

search covered in the report ard outivies the signif. cant results.

encet The promulgation of 10 CFR Part $4 has clear advan-f or the convenience o' the uwt the toports aie irviemed by tages relative to regulatory statukty and admitvstrative efficiency.

pornotal aathor, corporate author, and subtect However, d wdl not result in enytrotirnental effects signif;cantty NUREG 13 2; SAFETY EVALUAllON REPORT RELATED TO different from those ansing from tohcensing undet emsting regu.

tatens. The NRC concludes that promu6gation of 10 CFR Part THE F ULL TERM OPERATING LICENSE FOR OyS1ER ChELK NUCLEAR GENERAllNG STATION Docket No. 60 54 would not signihcantly affect the environment and, therefore, 219 (General Put5c Utthfies Nuclear Cotpat n')

• DivW of Re-a full envitonmen al impact statement is not requited and a acta Protects Ull (Post 870411) January 1pn 181pp.

Finding of No Gegnihcant impact can te made.

9101300M6 f4534121 NUREO.1400 DRFT FC: AIR LAMPLING IN THL 1he Safety Evalualon Report for the full te'm operating li-WORKPLACE Draft Report For Comment MCGUiRE,$ A. Dwi-con 9e apphcuton fdud by GPU Nuclear Corporation and Jesev Contral Power & Ught Company for the Oyster Creek NiAear son of Regulatorv Applicatons (Post 870413). HICKEtt E.;

STOETZEL G A1 et et Dettelle Memot alinstitute, Pacific North-Generating Stat on has been propated by the Office of Nuclea' west Laboracy, October 1991 97pp. 911107011C. 59549186, Reactor Regulation of the U S Nuclear Regulato) Cornmission-NUREG.1400 is a support document for Revison 1 of Rogu-The locihty is located iri Ocean County, New Jersey. The staff latory Guide 8 25, " Air Sampling in the Workplace." The docu.

concludes thet the f a;ilny can continue to be operated without ment addresses tha aspects of designing. Instalbng, and imple.

endangenna the heatth and safety of the pubhc.

menting an air samphnd program at e facekty licensed try the HUREG 1391: CHE MICAL TOXICITY OF URAN d4 HEXA.

U S Nuclear Regulatory Commmston to meet the requirements FLUORIDE COMPARED TO ACUTE EFF ECTS OF in the revision of 10 Cf R 20 Determinston of the need for air RADIATION Final Report MCGUIRE,S A Damson of Regulatory samphng is addiessed using an evaluaton piscess termed a Apphestnna (PW 870413) F ebruary Mt41.17pp 9103110209.

hazard indes calculation. Performance of a harard indu calcu-56942 190 laton will suggest the type and level of samphng needed to lhe chemical effects from acute exposures to uranium h6xa-adJ4uately assess the workplace se concentr bons. Guidance fluuhde are comparod to the nonstochastic effects from ecute is also provided on types of unphng available including a gen-ra:hntion doses of 25 rems to the whole body and 300 rems to eral ai samphng, breathing rone a;r samphng, and early warning the thyroid The ana'yes concludes that kn intake of about 10 ear sampling in addition, location of samplers, statistical tests mg of utsNum in eclutile form is toughly corl arable, in terms for determining samphng adequacy, dertved air concentrabon of early effectt to an acute whole body ese of 25 rems be.

ad}ustment for parbete slie analysis, cabbrat on for volume of att rusa toth are just below the threshold for significard nonsto-sampled, quakty contfoi, and evaluatori df program adequhty r eastic effects. Simdarly, an eeWe to hydrogen rarm ist g are discussed i

"entraton of 25 mg/m(3) tw W mmutes 66 toughly con. para-t ble occaiv there would be no synsficant nonstochosbe effects NUREO 1401 DRFT FC: REGULATORY ANALY31S FOR GENER.

For times

• other than 3C mine'en, the concentrabon C of hydro-IC ISSUE 23.

HEACTOR COOLANT PUMP SEAL gen fluoride coredered to have the same effect can be calcu-FAILURE. Draft Report For Comment - SHAUKAT,S Ka lated using a quadrabc equabon: C - 25 mg/m(3) (30 min /

JACKSON,J Ua THATCHER,0.F. Dwison of Safety issue Reso-t)(0 5) The purpose of these analyses is to provide informabon luton (Post 880717). Anr* 1991,77pp 9104250020, 57489.033 for developing design and sibng gurdelines based on chemical This toport presents ' 1 @ tory /backfit analysis for Gener.

toucity &f ennchment plants using uranium herkfluonde. These ic lasue 23 (Gla). " Ream +olant Pump Scal Failure " The -

guidehnes are to be similar, iri terms of stochastic health ef, regulatory analysis includes quahty assurance provisions for re-facts, to entona in NRC regutations for nuclear power i ants, actor coolant pump sea,s, instrumentaton and procedures for wh.ch are based on rad,ation doses.

morsoring seal periormance, and provisions for seal cochng during off normal plant conditions involving loss of eli seal cool-NUREG-1397: AN ASSESSMENT OF DESIGN CONTROL PRAC-ing such as stabon blackout TICdS AND CESIGN RECONSTITUTION PROGRAMS IN THE NUCLEAR POWER INDUSTRY, IMBRO.E.V. Dwision of Reactor NUREG 1407: PROCEDURAL AND SU3MITTAL GUIDANCE FOR lrspecten & Saloguards (Post 870411). February 1991,109pp IN0lV10UAL PLMT EXAMINATION OF EXTERNAL EVEN1S 9103120091. 56961:249.

(IPEEE) FOR StMRE ACCIDENT VULNERABILITIES Final This document summantes the results of a survey of nuclear Report CHEN,J.Ta CHOKSHI,N C., KENNE ALLY,R M et at Di-power riant cesyn control pracbees and design reconstituton vision of Safety labue Resoluton (Post BB0717). June 1991.

efforts conducted dunng 1989 at six utthfies and with cne nucle-81pp 9107P30240. 6B494:303.

ar steam sapply vendor. Conclusions and observat ons resulting Based on a Policy Statement on severe Accidents, the h-from the survey assessments are provided so that utshbes and Censee of each nuclear power plant is requested to pertorm an the NRC can consador actons to improve these programs indrvidual plant examination The plant examination systemati-m,

L

,i MalR Citations and Abstracts 11 taHv looks fut vulnerabmties to t.evere seidents and cat ettu signAant trwestgatae and audit actmties of the othce The 6-two safety 6tnprovements that leduce or v.ninate the importent rnonth reporting penod ends March 31 and September 30. Tha s

vulnerabiktiet This document presents guidance for performing tcport is submitted to th6 Chairman not later than April 30 and and r9 porting the ectufts of the individual plant enaminat.on of Octoter 31, reset >ctively, of each year. The Chairman prepares uternM events The gue.i&xe for reportirig the results of the in commets as required by the IG Act, and transmits the report to drodual piarit examinst on,f toternal events (IPE) is presented Congress in EO W NURE G.? d21: REGULATORY ANALYSIS FOR THE RESOL U.

NUREG 1412: FOUNDATION FOR fH? ADEQUACY OF THE LI*

TlON OF GENERIC ISSUE 130. ESSENTIA! SERVICE WATER CENSING BASES A rupplement 'io lhe Statement Of Consid-SYo1EM FAILURES AT MULT6-UNil SIT ES. L EONG,V4 er%tions For The Wee On Nude Pov et Piant Deense Renew.

BASDEKAS,Da MAZETIS.G, Division of Safety laste Raulution el (10 CrR Part f,e) Final Report ' ithee of Nuclear Reactor (Post 800717) June 1991. 34pp 9107080230 56307.099 Regulation, Dwecht (Poti 070411) December 1991. 119pp The essential service water system (ESWS) la PguWd to 92010tiOO78 60114 241.

provide cooling b nuclear power plantr dunng normal operation Tha objective of it.is reret is to descrAe the reOutatory proc.

.nd accident con:titions. The ESWS typically supports compo.

esses that assures tht<t any plant.specif6c hconting bases will nent coolitig water heat enchangers, containment spray heat ex-provide reasonable assurance that the oporation of nuclear changers, Ngh. pressure injection pump oil coolere, emergency power plants will not be inimical to the pubhc hemith and ufety diesel generators, and aunillary bwlding ventilation coolers Fail.

to 'the end of tenewal pe'iod,11 is on the adequacy of this proc

• ute of the ESWS f Action could ined to severe consequences est, that tM Commission has determinod that a formal renewal This report presents the regulatory analysis for Gl 130, "Essen.

hcorMteg review against the tull range of current safety require.

taal Service Water System Fanures at Mulh-Unit Sites" The ririk mente would i401 add h4Tif cantly to safety and is not needed to reduction estimGtes, cost / benefit analyses, t.nd other insights assure that continued operation thrf9ghout the tonewal term is gained during this effort have shown that implementation of the not inimice.1 to the pubhc health and safety or common defense rocommendations w61156gndicantly reduce nsk and that these and secunty. Ws document litustrates an general torms how the regulatory process has evolved in mQor safety issue areas it improvements are warranted in accordance with the backht rule, s

also provides exams les titustrating why it is unnecessary to re-10CFR$0.iODla)(3r revten an opWang plant's basis, except for age related degra-NUREG 1423 V02: A COMPILATION OF REPORTG OF THE AD.

dation unious to 16 cont.o rene*al, at the time of 16 cense rene**l.

VISORY COMMITTEE ON NUCLEAR WASTEJuN 1990 June lhe report is a supplement to the Statement of Considerations 1991, ' Advisory Committee on Nuclear Weste August 1991, for the Nuclear Regulatory Com nation's rule (10 CFR Part 54) 98pp. 9108290265. 54929 237, that establahes the enteria and standard, goveming nuclear This compilation contains 20 reports issued by the Advicory power plant bcense renewkt Committee on Nuclear Waste during the third year of its opon NUREG 1413: SAFETY EVALUATION REPORT RELATED TO ation, The reports were submiticd u the Chairman, U.S. Nucioer 1HE PREUMINARY DESIGN OF THE STANDARD NUCLEAR Regulatory Commission, or to the Director, Othee of Nucinar STEAM SUPPLY REFERENCE SYSTEM,RESAR SP/90. Docket Matonal Safety and Safeguards. All reports prepared by the No. 50-601 (Westinghouse Electnc Corporation, Inc )

• Division Cornmalee have been n ade available to the pubhc through the o Advanced Reactors & Special Projects (Post 901216) April NRC Pubhc Document Room and the U.S. Library of Congress, r

1991,398pp. 9105220026. 57824160.

NUREG 1426 V011 COMPILATION OF REPORTS FROM R5 This report provides the results of the NRC staff review of the SEARCH SUPPORTED BY 1HE MATERIALS ENGINEERING Westinghouse Electoc Corporation for a pechminary design ap*

BRANCH.DtVISION OF ENGINEERNG. 1965 1990.

provai of ttie SP/90 reactor contained in its reference safety HISER,A L Division of Engineenng (Post 870413) May 1991, analysis repart The standard safety analysis report describing

$5pp. 910000222. 57B67:261 the design of the facility was submitted from October 24. 1983 Since 1965, the Materials Engineenng Branch, Division of En.

through March 9,1987, Staff of the U S. Nuclear Regulatory Commission, Othee of Nuclear Reactor Regulation, prepared g,neenng of Ine Nuclear Regulatory Commission's Othce of Nu-this *Wty evntuatton report of the RESAR SP/93 Based on its clear Regulatory Research, and its predecussors dating back to review, the staff concludes that there are open lasues that be*

the Atomic Ener0y Commission (AEC), has sponsored research cause of the stage of tne design have not been resolved at this programs concerning the integ ity of the pnmary system pres.

stage of review. Tnese issues are discvssed in detNt throughout sure boundary of light watef reactofs The componenta of con-this eport, and a summary is provided 6n Sect 6on 1.6 of this corn in these retsarch programt have Mcludad the reactor report-pressure vessel (RPV), steam generators, and the piping These research programs have covered a broad range of tcpics, in-NUREG 1415 V03 N02: OFFICE OF THE INSPECTOR ciuding fracture mechanics arelysis and expenmental work for GENERALSomaannual Report. October 1990 March 1991, a RPV and piping apphcations, inspution method development Oihce of the inspector General (Post 890417) Apr611991. 34pp.

and qualification, and evaluatsen of irradiation effects to RPV 9107030211. $828v001.

steels This report provides as complete a hsting as practical of Inspectors General are required, by the IG Act of 1978, as formal technical reports submitted to the NRC by the investiga-amended, to prepare semiannual reports which sumtrMte the

- tors working on these research programs. This listing includes significant investigative and audit activities of the othee The 6 topical, final and progress reports, and is segmented by topic month reporting penod ends March 31 and September 30. The area. In many cases a report will cover several topics (such as report is submitted to the Chairman not later than April 30 and in the case of progress reports of multi faceted programs), but October 31, respecisely of each y3ar, The Chairmen propores is hated under onfy one topic. Therefore, in searching for reports cornments as required t, tne IG Act, ami transmrts the report to on a specihc topic, other related topic areas should be checked Corsgress also NUREG-1415 V04 ND1: OFFICE OF THE NSPECTOR

- NUREG 1428: ANALYSIS OF PUBLIC COMMENTS ON THE GENERALSemiannual Report April-September 1991.

PROPOSED RULE ON NUCLEAR POWER PLANT LICENSE GLENN W t. ; WATKINS.R. A ; HUBEA.D S. Othee of the inspec-RENEWAL

• Division of Safety issue Resolution (Post B80717) tor Generat (Post 890417). October 1991, 36pp 9201090191.

December 1991. 370pp. 9201060074. 60195 231.

430243 229.

This report provides a summary and anatysis of pubhc com-hapectors General are required, by the 40 Act of 1978, as ments on the proposed beense renewal rule for rWClear power amended, to prepare semaannual reports which bummarire the plants (10 CFR Part 54) pubbshed in the Federal Flegister on 17

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

o 12 Main Citations and Abstracts July 1990 It also documents the NR7s resoluton of me istun Nf40 staff is asuing this 6 aft new STS tot a 30 working day rawd by the commentors Comments from 121 organitatens comment penod Following the comment pered, the NRG statt and 76 indmdua4 were reviewed and analyred to dentity the wiu anatyre comments received, finalige the new STS, and issues, including thoue pertaining to the adet.luncy of the licens-Istuo them for plant-spoofic implemeritaten This report con.

Ing basis. the performance of an integrated plant asheshment, tains three volumes Volume 1 contains the Specifications for all ba3ht considerat ons, and need for public heanngs The analy.

Sections of the few STS Volume 2 cor tains the Bases for Sec-sis included grouping of commentors' views according to the tons t o 3 3 of the new STS and Volume 3 contains the issues rused The put.lc comments analyred in this toport were Dases for Sectons 3 4 3 9 of the new STS taker' into connteration in the development of the final rule and NUREG 1431 V2 DRF FC: STANDAf40 TECHNICAL SPECIFICA.

revis.ans to the supporting documents 3

gg p

g pg NUREG 1429 DRFT FC: ENVIRONWNTAL ST ANDARD REVIEW 3 3)Dratt Rep @ For Comment Division of Oporstiona' PLAN FOR THE REVIEW OF LICENSE RENEWAL APPLICk Events Assessment (Potit 870411F January 1991. 38 ?pp.

TiONS FOR NUCLEAR POWin PLANTS Draft Report Fot 9102140309. 56097,181-Comment

• Division of Advanced Reactors A Special Projects See NUREG 14M,V01,DAFJC abstract (Post 901216) August 1991 97pp. 9109300073 $9227.215 The Environmental Standard Review Plan for trie Review og NUREG.1431 V3 DRF FC: STANDARD TECHNICAL SPECll1CA.

Lcense Renewal Applica..ans for Nucicar Power Plants (ESRP=

TIONS WESTINGHOUSE PLANTS Buses (Sections 34-LR) is to be used by the NRC staff when performing envwerb 3.9) Draft Report For Comment Division of Operational mental fevices of applications for the renewal of power reactor Events Assessment (Post 870411) January 1991. 644pp.

licnnses the use of the ESRP.LR provides a framework for the 9

fL f[3i'v01'DRFJC abstract-4l0 staff to determine whether or not eruronmental issues impor-tant to hconse renewat have boon identified and the irnpacts NURE11432 V1 DRF FC: STANDARD TECHNICAL SPECIFICA.

evaluuled and providos acceptance standards to help ihe re-TiONS COMDUSTION ENGINEERING viewors comply with the Natonal Enysonmental Policy Act PLANTS Specifcations Draft Report for Comment ' Dwision of NUREO 1430 V1 DRF FCI STANDARD TECHNICAL SPECIFICA.

Operational Events Assessment (Post 870411) January 1991, a

TIONS BADCOCK AND WILCOR PLANTS. Specifcatons Draft 618pp 910??00257,66753 020.

Roport For Comment

• Dvison of Operational Events Assess.

This draft report documonts the sesults of the NRC staff ment (Post 870411) Januar/ 1991, 421pp. 9102190210.

review of new Standard Technical Spocihcations (STS) pro-567hku m posed t*y the Comtnistion Enginonnng Owners Group, The now This d/att report dommtnts the results of the NRC statt STS were deve'oped based on the critena in the interim Com-review ot new Stanoo d Technical Spec ficatons (STS) po-mission Poley Statement on Techncal Specifcation Improve-r posed by the Babcock and Wilcox Owners Group 1he new STS ments for Nuclear Powet Reactors, dated February 6,1967.

weie developcd based on the critene in the intonm Commission The new STS will be uned as bases for individual nuclear power Policy Statement on 'sechnical Specibcation improvements for plant cwners to develop improved plant. specific 16.:hncal spech Nuclear Pcwer Reactors, daw 1 Februar) 6,1987, The new STS femtions. The NRG staff is issuing this dra't new STS for a 30 will be used as bases for indwdual nuclear power plant owners working day comment period Following the comment penod, to develop improved plant specahe tochrwcal specibcations Tha the NRC staff will analyre comments received faaltre the now NRC statt is issuing this dcut new STS for a 30 workin941ay S'

and usue them for plant specnic 6mplementation. This comment ponod Following the comment ponod, the NRC staff report coritains three volumes. Volume 1 contains the Specifca-will abatyn comments received, finalare the new STS, ard tions 8or all sections of the new STS Volume 2 contains the issue them for piant specife irppiumentation. This report con.

Bases for Sechons 2.0 3 3 of the now STS and Volume 3 con-tains three vt.lumes Volume 1 contains the Specihcatons for all tains tha Bases for Sochons 3 4 - 3.9 of the new STS.

sections of the new STS Voiume 2 contains the Bases for Sec.

NUREO 1432 V2 DRF FC: STANDARD TECHNICAL SPECIFICA.

tons 2 0 3 3 of the new STS and Volume 3 contains the Bases for Soctons 3 4 3 0 of the n9w STS TiONS COMDUSTION ENGINEERING PLANTS 0ases (Soc.

tions 2.0 3 3) Draft Report for Comment

• Divison of Oper.

NUREG 1430 V2 DRF FC: STANDARD TECHNICAL SPECIFICA.

ational Events Assessment (Post 870411). January 1991.

TIONS DADCOCK AND WILCOX PLANTS. Bases (Sections 2 0 b60pp. 9102200262. f.6'151,100.

3 3) Draft Poport For Comment

• Division of Cperational See NUREG 1432,V01.DRF,FC abstract 1

Januay M 370pp NUREO 1432 V3 DRF FC: STANDARD TECHNICAL SPECIFICA.

1902 07 See NUREG 1430,V0bORF,FC abstrac"'

tions 3 4 3 9) Draft Report For Comment

• Divis6on of Open NUREG 1430 V3 DRF FC: STANDARD TECHNICAL SPECIFICA.

ational Events Assessment (Post 870411), Januaiy 1991.

TIONS DADCOCK AND WILCOX PLANTS. Dases (Sectons 'l 4 528pp 9102200266. 56750 012.

- 3 9)Dratt Report For Comment

• Dwision of Operational See NRUEG 1432,V01.ORF,FC abstract.

t Jan g S 47tpp' 2 90 4 56 57 064 NUREG 1433 V1 DRF FC: STANDARD TECHNICAL SPECIFICA.

See NUREG 1430,V0kDRF.FC atatract TtONS GENERAL ELFCTRIC UNIT S, BWR/

4,Specthcahons Omtt Report for Comment

• Division of Oper.

NUREG 1431 VI DRF FC: STANDARD TECHNICAL BPECIFICA-ational Events Assessment (Post 870411). January 1991.

TIONS WESTINGHOUSE PLANfS Specifcators Draft Report 485pp 9102140324. 56704 290.

For Comment

• Dwision of Operational Events Assessment This draft report documents the results of the NRC statt (Post 870411). January 19'11. 484pp 9102140299, 56696:057.

review of now Standard Technical Specifcations (GTS) pro.

This dratt report stocuments the results of the NRC staff posed by the BWR owners Group for the BWR/4 design. The review of new Standard Techrgal Specificatens (STS) pro-new STS were developed based on the enteria in the interim posed by the Westinghouse Owners Group, The new STS were t,urnission Policy Statement on Technical Specihcaton Im-developed based on the cnteria 6q the intenm cow, mission provements for Nuclear Power Reactors dated February 6 Policy Statement on Techrncal Specifcahon Improvements for 10P7. The new STS will be used as bases far individual nuclear Nuclear Power Reactors, dated February 6.1987, The new STS power plant owners to develop irnproved plant-specific technical will be used as bases for individust nuClDar power plant owners speufcations. The NRC staff is iskuing this draft new STS for a to develop improved plant-specife technical specihcations, The N worlung<$ay comment penod. Following the comment pertort, d

Main Citations and Abstracts 13 the NRC sta f will anal re comments received. finaue the new repod and prov(tes updated informat,on as of September 30, r

f STS, and issue them tar plant speof e implementaten. This 1991. The data contained an these NUREG reports are a prod-report contains three volumes Volume 1 contains the Specihts-Oct of the NRC's Safety issues Management System database.

tior,s for all sections of the new STU Volume 2 contains the wNch te maintained by the Project Management Staff in the Bases for Sections 2 0 3 3 cf the new STS and Volume 3 con-Othce of Nuclear Reactor Regulation and by NRC tegonW per-tains the B3ses for Sections 3 4 310 of the new STS.

sonnel. TNs report in to provide a comprehensive desenption of NURIO 1433 V2 DRF FC: STANDARD TECHNICAL SPECIFICA.

the 6mplementaten and serihcation status of TMI Action Plan TlONS GENERAL CLECTRIC UNITS, DWR/4 Beses (Sect:ons Requements, safety issues des 6gnated as USis, and GSis that 2 0 3 3) Draft Report For Comment

• Divmson of Operationht have been resotved and involve implementation of an action or Events Assessment (Post 670411). Janua'y 1991. 419pp actons by licensees This repor1 makes tre information avail +

9102140322 567U3 231 able to other iriterested parties, including the pubbe An addi-bee NUREG-1433.V01,DRFJC abstract tonal purpose of tNs NUREG repou a to se as a Mowq g

to NUREG 0933, "A Poonttraton of Generic Safety fasues.

0 NUREG 1433 V3 DRF FC: STANDARD TECHNICAL SPECIFICA*

wNch tracks safety issues up unul requirements are approved TIONS GENERAL ELECTRIC UNITS, DWR/4 Dates (Sectons for imposition at hcensed plants or until the NRC 6ssues a re.

3.4 310)Dratt Report For Comtnent.

• Des 6pn of Operational quest tot action by bcensees Events A$tessment (Post 670411). January 1991. 475pp, 9102140295. 56702:116 NUREO 1436 V01: STATUS OF SAFETY ISSUES AT LICENSED See NUREG-1433,V01,DRFJC abstract.

POWER PLANis.TMI Acton Plan Requirements.

• Program NUREGd434 V1 DRF FC: STANDARD TECHNICAL SPECIFICA, MeagenwnL Polwy Dmiopment & Analysis Staff (Post TIONS GENERAL ELECTRIC PLANTS.

DWR/

B704M) March 19% 872pp M04M02M E7mB1 6 Specaficatons Draft Report For Osmment

• Division of Oper.

As part of nngoing U S. Nuclear Regutatory Commission etional Events Asaessment (Post 870411). January 1991.

(NRC) efforts to ensure the quakty and accountabilRy of safety 497p 9102200248 56747:088, lasue informaton, lt program has been ettabhshed whereby an This draft report documents the traults of the NRC staff annual NUREG ones report will be pubished on the status of review of new Standard Technical Specihcat60ns (SIS) pro.

licensee implementaton and NRC vershcaton of safety issues in possJ by the JWR Owners Group for the BWR/6 design The major NRC requirement areas The data contained in tNa report new STS were developed bosca on the crftena in the intenrn are a product of (fie NRC's Safety fesues Management System Commitson Pokey Statoment on Techrucal Spocihcation Im.

database, wNeh ih maintained by the Project Managertient Staff prosements for Nuclear Power Reactors, dated February 6, in the Office of Nucleef Reactor Regulation and by personnelin 1997. The new STS will be ust'd as bases for Individual nuclea, the NRC fegions This report has been prepared in order to pro-power pMnt owners t-. wetop 6fnproved plant-specific technical vide a comprehensive description of the implementalon and specihcations The Nh; statt 6s issuing this draft new STS for a venfication status of all the TMI Action Plan requirements at 16-30 workng-day comrnent penod, following the comment penod, conned reack s, and to make tNs informaton available to other the NRC statt will anatyre comments recotved. hnahre the new interested parties. including the pubhc, A corollary purpose of STS, and issue them for plant specibe impiomontation. This this report is for it to serve as a follow on to NUREG 0933. "A report (:ontains throo volumos Volume i contains the $peshca, Priontitatiott of Generic Safety IBSues," WNCh tracl(s safety bons for all sections of the new STS Voturne 2 contains the isswa up until requirements ate approved for 6mpositen at h.

Bases for Sectons 2.0- 3,3 of the new STS and Volume 3 con.

conned fadistics, tains the Bases for Sections 3 4 3.10 of the new STS' NUREG 1435 V02: STATUS OF SAFETY ISSUES AT LICENSED NUREG 1434 V2 DRF FC: STANDARD TECHNICAL SPECIFICA-POWER PLANTS Unresolved Safety lasues. ' Program Man-TIONS GENERAL ELECTRIC PLANTS, DWR/6 8anos (Sect;ons agement, Pohey Development & Analysis Staff (Post 070411).

2 0 3 3) Draft Report for Comment. * (>ivision of Operatienal May 1991. 234pp. 9106120180, 5606??61.

Events Assessment (Post 070411). January 1991. 447pp.

As part of ongoing U S. Nuclear Regulatory Commission 9102200251. 56746 001.

(NRC) efforts to ensure the quakty and accountability of safety See NUREG 1434,V01.D'1F,FC abstract.

Issue information, a program has been estabbshed whereby en NURE31434 V3 DRF FC: STANDARD TECitNICAL SPECIFICA-annual NUREG report will be pubhohed on the status of keens.

TiONS GENER4 ELECTRIC PLANTS, DWR/6. Bases (Sections ce implementaton and NRC venhcaton of safety issues in 3 4 3.10) Draft Report For Comment.

• Division of Operational major NRC rgirement areas. TNs report, the second volume Events Assessment (Post 870411). January - 1991, 496pp.

of a three volume senes, addresses the status of unresolved.

9102200254. h6748 225 safety issues at beensed plants. The data contained in tNs See NUREG 1434,V01,DRF,FC abstract.

'eport are a product of the NRC's Safety issues Management NUREG 1435 S01: STATUS OF SAFETY ISSUES AT LICENSED System database, which is maintadied by the Project Manage.

POWER PLANTS TMI Acton Plan Requirements Unresolved ment Staff in the Othee of Nuclear Reactor Regulation and by personnel in the NRC regens. TNs report has been prepared in.

Safety lesuetGeneric Safety issues.

• Program Management, order to provide a comprehensive descripton of the implemen-Pohey Development & Analysis Staff (Post 870411). December tat on and venficaton status of all the TMI Action Plan sequeo-1991.107pp. 9201060172. 60207.075.

ments at hcensed reactors, af.d to make tNs informst60n avail-As part of ongoing U.S. Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety abb to other interestod part.es, including the pubhc, A corollary -

purpose of this report is for it to serve as s follow on to issue 6nformation, a program was estabbshed whereby an NUREG-0933,"A Pnontizaton of Genenc Safety issues." wNch annual NUREG report would be pubhshed on the status of 16-tracks safety issues up unbi requirements are approved for im-censee implementation anj NRC venhcabon of safety issues in positon at licensed f acihbes, mapr NRC requirement artas. This informahort was compiled and reported in three NUREO volumes. Volume 1, pubhahed in NUREG 1435 V03: STATUS OF SAFETY ISSUES AT LICENSED March 1990 addressed the status of Three Mile Island (TMt)

POWER PLANTS Generic Safety lasues.

• Program Manage.

Achon Plan Requirements. Volume 2, pubhshed in May 1901, ment, Pohey Development & Anatysis Staff (Post S70411) June addressed the status of unre. solved safety lacues (USis).

1991. 271pp. 9107080225. 58306:188 Volume 3, pubhshed in June i991, addressed the implementa-As part of ongoing U S. Nuclear Rogulatory Commission hon and wrihcation status of generic safety issues (GSis). This (NRC) efforts to ensure the quahty and accountabihty of safety annual NUREG repor1 combines these volumes into a single issue informat on, a program has been estabbshed whereby an

14 Main Citations and Abstracts annual NUREG repori will be published on the statss of tcrn this regWatney annlysis provides tne supporting enformaton eo implementation and NRC vent cation of safety issues in for e proposed rule that will amend the Nucitar Regulatory major NRC requirement areas. This report the third volume of a Commissiun's requirements for environmental review of apphca-three. volume series, addresses the status of genene safety t>ons for renewat of nucisar powet plant operating licenses issues at hcensed plants The data containod in this report are After considering various options, the staff 6dentified and ana+

a product of the NRC's Safety issues Management System da-lyzed two major etternatives Ailernat#ve A is to not amend the tabase, which le maintained by the Prosset Management S'$ff in regulations and to perform environmental reviews under the on-the Othee of Nuclear Reactor Regulaton and by personnel in esting regulations Altemative B is to assess, on a generic basis, the NRC regions This report has been prepared in order to pro-the environmentalimpacts of renewing the operating bcense of vedo a comt..ebenstve desenption of the 6mplementation and individual nuclear g eer plants, and define the issues that will vonfication status of all generic safety issues at heensed teac-tmed to be further analyred on a case-by-case bas s. The find-tors, and to make this informaton available to othet intetested 6ngs of this assessment are to be Codified in to CFR Part 61, parties, including the pubhc. A corollary purpose of this report is The staff has selected Afternatrve U as the preferred alternative for et to serve as a follow.on to NUREG 0933, *A Pnoritiration of Genenc Safety Iseues/' which tracks safety issues up until NUREG 14411 LESSONS LEARNED FROM THE POST EMER-requirerr.ents are approved for imposition at bcensed facihties.

GENGy TAULETOP EXERCISE IN. DATON NUREG 107 V1 DRF FC: GENERIC ENVIRONMENTAL IMPACT ROUGE, LOUISIANA,0N AUGUST 28 AND SEPTEMBER 18, STATEMENT FOR UCENSE RENEWAL OF NUCLEAR 1990. WEINSTEINE. Incident Response Branch D ATE S.G.

PLANTS Main Report Drafi Report For Comment

• DNisen of Region 4 (Post 820201). PEYTONL Federal Emaegency Man-Safety issue Resoluhori (Post B80717). Auguht 1991. $$9pp.

agement Agency July 1991.32pp=9108190268, FEMA HEP 18.

9109300088. $9229 005 68828,1 E This Genene Environmental Impact Statement (GEIS) exam.

On August 28 and September 18. 1990, Gulf States L'tilities, ines the possible environmental 6mpacts that could occur as a the States of Louisiana and Ministippi, five local panthe a, six tesuft of renewing heenses of individual nuclear power plants Federal agencies, and the Amencan Nuclear insurers participat-under the proposed 10 CF A Part $4. The GEIS, to the extent ed in a post.cmergency TABLETOP esercise in Baton Flouge, possible, establishes the bounds and sigwficance of these po-Louisiana The purpose of the exercise was to esamine the tontialimpacts. The analyses in tte GEIS encompass all operat-post emergency rolies, responsibilities, and resources of utility, f

ing hght water power reactors. For each type of environmental State, local, Federal and insurance organizations in response to 6mpact the GEIS attempts to esta)hsh genonc findings covenng a hypothetical accident at the River Bond Stat on in Louisiana as many plants as possible. Th:s GEIS has three principal ob-resumg in a signthcant release of radiation to the environment.

jectives (1) to provide an undorstanding of the types and sever

• In pursuit of this goal, five major focus areas were addressed:

fly of environmental impacts that rney occur as a result of h.

(1) ingestion pathway response; (2) reentry.. relocat6on and conse tenewal of nuclear power plants under 10 CFR Part $4, return; (3) decontamination of recovery; (4) indemnification of 19 (2) to identity and assess those irnpacts that aie espected to be nanciallosses; and (5) deactivsten of the emergency response.

genene to hcense renewal, and (3) to support a rulemaking (10 This report documents the lessons learned from that exercise.

CFR Part $1) to define the number and scope of lasues that need to be addressed by the apphcants in plant tiy plant bronse NUREG 1442: POST EMERGENCY RESPONSE RESOUHCES renewal proceedings. To accomphsh these objectives, the Gels GUIDE Dased On The Post-Emwgency TABLETOP Exercise in makst maximum use of environmental and safety documenta-Baton Rouge. Louisiana On August 28 And September 18,1990, tion from orginal beensing proceedings and informaton from WEINSTEIN,E. Incident Response Branch. DATES,0. Region 4 t, tate and federal regulatory agencies, the nuclear utility indus-(Post 820201). ' Federal Emergoney Management Agency, July try, the open hterature, and professional contacts-1991.38pp.9108290223. FEMA REP 17. 6tio10 216.

NUREG 1437 V2 DRF FC: GENERIC ENVIRONMENTAL IMPACT On August 28 and September 18.1990, the States of Louisi-STATEMENT FOR LICENSE RENEWAL OF NUCLEAR ana and Mississippi, Gulf States Utihties, five local padshes, six PLANTS Appendices Draft Report For Comment.

• Division of Federal agencies, and the American Nuclear insurers participat-Safety issuo Resolution (Post P80717). August 1991. 643pp, ed in a post emwgency TABLETOP exercise in Datan Rouge.

0109300000. 59230.284.

Louisiana One e,f the products developed from that expenence See NUREG 1437,V01,DRFEC abstract.

is this guide for understanding the responsib6hties and obtaining ma wrces a

news hom me vanwa pa$cpants, pan NUREG,1410. STAFF TECHNICAL POSITION ON REGULATORY I"U"" "3*"

8'*"*

CONSIDERATIONS IN THE E'ESIGN AND CONSTRUCTION OF THE EXPLORATORY SHAFT FACILITY. GUPTA D -

• 9

1. 8 PESHEL,1; BUNTING J. Division of High-level Weste Mana'g5 9 ""

ment (Post 870413) July 1991. 50pp. 9108130271. 58764:306.

emergency response when theirs have been exhausted.

The staff of the U.S Nuclear Regulatory Commission has pro' NUREG 1443: SAFETY EVALUATION REPORT RELATED TO pared tais afaff technical position for the purpose of compiling THE FULL TERM OPERATING LICENSE FOR SAN ONOFRE and further clanfying provous staff positions on regulatory con

• f40 CLEAR GENERATING STATION, UNIT 1.- Docket No. 50-sideratons in the design and construction of the exploratory 206(Southem Cahtomia Edison Company And San Diego Gas shaft facil,ty (ESF). Gho U.S. Department of Energy (DOE) no*

And Electnc Company)

• Division of Reactor Pro}ects tilIV,V &

refers to the ESF as the " exploratory studies fac6hty" DOE's Special Projects (8704119012 t 5),

July 1991.

43pp.

change in terminology does not affect the positions take9 in this 910B130M9 68746M guidance) This document hats the key regulations in 10 CFR The safety evaluation report for the lufhterm opstating hcense Part 60 that should be considered in the design and construc-apphcation filed by the Southern Cakfomia Erisson Company ton of the ESF and presonts the staff position statements and and the San Diego Gas and Electnc Company has been pre-corresponding discussions' pared by the Othee of Nuclear Reactor Regulation of the U S.

NUREG 1440 DRFT FC: REGULATORY ANALYSIS OF PRO.

Nuclear Rcgulatory Commission. The facekt/ is located in San i

POSED AMENDMENTS TO REGULATIONS CONCERNING Diego County, Cahfomia. The stati has evaluated the issues re-THE ENVIRONMENTAL REVIEW FOR RENEWAL OF NUCLE.

lated to the conversion of th3 provisional operating license to a AR POWER PLANT OPERATING LICENSES Draft Report For full term operating hornse and concludes that the facility can Comment.

• Division of Safety issue Resciution (Post 880717).

continue to be operated without endangerireg the health and

. August 1991,33pp. 9109300064. 59256;188 safety of the pubhc following the hcense conversion.

l

Main Citations and Abstracts 15 NUREG 144k REGULATOR f ANALYSl$ FOR THE HrSOLU eral nonsafety systems. Induding reacts control rod positon in.

TIOt4 OF GENERIC SAFETY ISSUE 29 00LTING DEGRADA.

dication, some reactor pc,wer and water indicaton, control room TlON OR FAILURE IN NUCLEAR POWER PLANTG.

annunciators, the plant comniurucatons system, the plant proc-CHANG,T.Y. Division of Safety issue Resolution (Post 800717) et.s computer, and i+ghting at some locations The reaciot was September 1991.116pp 9110100228 69334 00t.

subsequently brought to a safe shutdown. Following this event.

Genenc Safety issue (GSI).29 deals with staff contorns about the U S. Nuclear Regulatory Commisson dispatched an incident public risk due to degradation of failure of safety related totting investigaton Team to the site to deturmine what happened, to in nuclear power plants, The issue was initiated in November 6dentify the p<obable causes, and to make appropnale findings 1982. Valueimpact studies of a mandatory program on safety-and conclusions. This report describes the incident, the method-related bottog for operating plants were inconclusive; theretare, ology used by the team en its investigation, and presents the additional regulatory requirements for ope?ating plants could not teams findings and conclus ons.

be justified o accordance with provisions of 10 CFR 50.109. In additon, batied on (1) operating esporwince with botting in both NUPEO/CP-003h PROCEEDINGS OF 1HE BEMINAR ON AS.

nuclear and conventional power plants, (2) the actions already pg ggg7 taken through bulletins, generic letters, and information notices.

PIPING AND PRESSURE and (3) *.he industry proposed actions, the staff concluded that a MAYFIELD.M E* Office of Nuclear RegulatorYVESSELS'Research (Pos HISER,A L/

sufficient technical basis exists for the tesolution of GSI 29. The 860720). I ebruary 1991. 334pp. 91030$0499 b6080.187.

statt further concluded that leakage of botteo pressure joints is The 1990 Pressure Vessel and Poing Conference, sponsored possvle but catastrophic failure of a reactor coolant pressure by the Amoncan Society of Mechanica. Enginents (ASME), was boundary joint that will lead to significent accident sequences is held in Nashytile, Tennessee from June 18 to June 21,1990. As highty unkkely. For future plants, it was concluded that a new pad of that contwenct icpresentatives from the USNRC and Standard Review Plan section should be developed to cod 4fy AEA Technnlogy in the United Kingdom jointly or0antred two existing botting requiromants and industry developed initiatives.

panel sessions to discuss the current state of fracture prediction technologies for piping and pressure vessels. A total of nine NUREG 1446: STANDARDS FOR PROTECTION AGAINST RADI.

presentations were given, contrasting analytical prod ctions with ATION.10 CFR PART 20. A Companton Of The Existing And experimental results. This document provides summanes of Revised Rules COOLD A; PETERSON.H T. Division of Reguia-each presentation and copies of the pertinent figures and other tory Applicatons (Post 870413) October 1991. 133PP visual aids. This information has boon compiled and putAshed 9201060176 60207M82.

to permrt reasonabiy prompt disseminatens of the informaton On May 21,1991, the Nuclear Regulatory Commission (NRC) presented Based on the information presented dunng these issued a revision to its standards for protecton against ionst:n9 two panel sessions, it appears that, while the current state of radiation,10 CFR Part 20. Alth> ugh the revtsed part (Sections tracture prediction technology is reasonably well advanced.

20A00120 2a01) became effective on June 20,1991, licensees more work is needed to provde analysis methods capable of may detet implementation of the revised rule until January 1 accurately predicting ductile crack entension.

1993. Licensees continue to be required to comply with the pro.

visions of Sections 20140601 until the time they adopt the NUREQ/CP-0114 V01: PROCEEDINGS OF THE EIGHTEENTH provisions of Sections 20.1001 20 2401. Therefore, between WATER REACTOR SAFETY INFORMATION MEETING.

June 20,1991, and January 1,1993. both the provisions of WEISS.A J. Brookhaven Nationat Laboratory. April 1991,678pp.

Sections 20.1-20 001 and Socions 20.1001 20 2401 are in 9105030130. 67022 001.

ettect This NUREG presents a comparative text of the provi.

This three-volume report contains 100 papers out of the 12fl sions of the revised Part 20 (Sechns 20.1001202401) to the that were presented at the Eighteenth Water Reactor Safety In-text of Sections 20 1 20 001 for use by the NRC staff and NRC formation Meeting held at the Holiday Inn Crowne Plara Rock.

licensees.

ville, Maryland, dunng the week of October 22 24,1990 The NUREG 1450: POTENTIAL CRIT lCALITY ACCIDENT AT THE papers are ponled in the order of their presentaten tr, each ses-GENERAL ELECTRIC NVCLEAR FUEL AND COMPONENT si n and desenbe progress and results of programs in nucl car MANUFACTURING FACILITY, MAY 29,1991.* Ofc of the Ex-safety research c nducted in this country and abroad. Foreign ecutive Director for Operations. August 1991* 230pp' pa%paton in me mWing inM % Mmnt pays p 9108210183 58857 167 sented by researchers from Denmark, Egypt, Gctmany, IAEA, At the General Electrb Nuclear Fuel and Comporient Manu-a,

apan, way, aManWaM N N WsdN factunng facihty, located near Wilmington, North Carolina. on pa@rs and the names of the authors have been updated and May P8 and 29,1991, approximately 150 kilograms of uranium

[a er from those that appeared in the final program of the were inadvertently transferred from safe process tanks to an unsafe tank located at the waste treatment f acility, thus creating NUREQ/CP-0114 V02: PROCEEDINGS OF THE EIGHTEENTH the potential for a tocalized cnticahty safety problem. The WATER REACTOR SAFETY INFORMATION MEETING excess uranium was ultimately safely recovered when the tank WEISS.A.J. Drookhaven Natonal Laboratory. April 1991.595pp.

contents were contrifuged to remove the uranium beanng ma-9105150327. 57715:230.

tonal. Subsequently, the U S. Nuclear Regulatory Commissbon See NUREG/CP-0114,V01 abstract

$spatched an incident investigation Team to determine what happened, to 6dentify probath causes, and to make appropnate NUREQ/CP-0114 V03: PROCEEDINGS OF THE EIGHTEENTH ferdngs and conclutdons. This report desenbos the incident, the WATER REACTOR $AFETY INFORMATION MEETING.

methodology used by the team in its it:yestigStch, and presents WEISS.A.J. Brookhaven Na'ional Laboratory. April 1991,582pp, the team's findings and conclusions.

9105150310. 57710 300.

NUREC 1455: TRANSFORMER FAILURE AND COMMUN-MODE LOSS OF INS 1RUMENT POWER AT NINE MILE POINT UNIT NUREQ/CP-0115: PRDCEEDINGS OF THE CSNI WORKSHOP 2 ON AUGUST 13, 1991.

• Ofc of the Executive Director for ON PSA APPLICATIONS AND LIMITATIONS. MOLINA,T, Operatons. October 1991 237pp. 9111070103. 59551:291.

Sandia National Laboratones. February 1991. 485pp.

On August 13,1991, at Nine Mile Point Unit 2 nuclear power 9103040340. SAND 90-2797. 56869 096.

plant, located near Scuba, New York, on Lake Ontano, the main This report contains the full papers submitted to the Commit-transforrr,er exponenced an intornal failure that resulted in de-tee on the Safety of Nuclear installatons Workshop on Probabi-graded voltage which caused the siruuttaneous loss of five unin-listic Safoty Assessment (PSA) Apphcatons and Limitations terruptible power supphen which in turn cwsed the loss of sey-held in Santa Fe, New Medco, USA, on September 4 through 6.

16 Main Citations and Abstracts 1990, The purpose of the Workshop was to provelo an aanve tymabon on the remed LER rule The LER aummanes in this for d$cussions In the following areas (1) current PSA results, report are anangtd alphabebcally by facibty name and then (2) current ubes of PSA, (3) views on current hmitat uns. (4) chronologically t9 anl date for each facility. Component.

eme'l opinen and (5) low probatahty numters The papers system, keywon component vendor indenes follow the v

contained herein addecas these issues, along with several other summanes Vends are those identified by the utility when the related topics LER form is initiated, the keywords for the component, system.

NUREGICP 0116 V01: PROCE EDINGS Or THE 21S1 DOE /Nr4C at d general keyword indoes are esogned by the computer NUCLEAR AIR CLEAf 0NG CONFERENCE Sessions 1 8 Held using correlston tables from the Sequence Coding anet Search in San Diego, Cal.fornia Augubt 13 10. 1990 FIHSt M W Hare N"I"*

vard School of Public Hen'th, Boston. MA February 1991 NUREG/CR 2000 V10 N1: LICENSEE EVENT REPORT (LEl%

• tpp 9101200077 CONF 900813 57059 th3-COMPILATION Fer Month Of January 1991.

• Oak R dge Na-

'his document contains the paporn and the estociated dis' tonal Laboratory February 1991, 95pp 9103200049. ORNL/

Achs of the 21st DOE /NRC Nuclear Air Cleaning Confe'*

NSIC400. 57065 214.

ence Maiot topics uro (1) chemical processing syvems (2) re-See NUREG/CR 2000.V09,N12 abstract actor operations (3) 6ncineraton and vitnhcaton, (4) particulate fator developments, including fator testing and response to NUREQ/CH 2000 V10 N2: LICENSEE EVENT REFORT (LER) physical and temrerature stress, (5) adsorption and Insting of COMPILATION For Month Of February 1991 ' Oak Ridge Na-activated carbon and adsorber systems, (6) severe accident tional Lat oratory. March 1991,112pp 9104220209. ORNL/

mitigat on incQding modeling of emergency ter,ponse fiystems, NSIC 200 574bO 119 (7) nuclear wete management systems, (0) carbon.14 removat.

See NUREG/CR4000N09,N12 abstract (9) monitonng and measu'ement systems, (10) the dedopment of standards and regulatone and concerns with existing stand.

NUREQ/CR4000 V10 N3: LICENSEE EVENT REPORT (LER) aros and regulations, and bt) nuclear sit cleaning actwibes COMPILATION ror Month Of March 1991.

• Oak Ridse Nation-around the world.

at Eatoretory, Apra 1991.97pp 9105170174. ORNL/NSIC 200.

57771 222.

NUREQ/CP 0116 V02: PROCEEDINGS Or THE 21ST DOE /NRC See NUREG/CR 2000,V09,N12 abstract h0 CLEAR AIR CLEANING CONFERENCE SESSIONS 9 16 Held in San Diego, California, August 13-16, 1990.

NUREQ/CR4000 V10 N4: LICENSEE EVENT REPORT (LER) i IRST,M W. Harvard School of Putac Health, Boston, MA. Feb.

COMPILATION f or Month Of Apnl 1991.

• Oak Ridge Nabonal ruary 1991. aB4pp 0103200094 CONL900813 57001:001.

Laboratory May 1991. 9?pp. 91061201(15 ORNL/NSIG200.

See NUREG/CP-0116N01 abstract 58063.135 NUREQ/CP 0118: TRANSACTIONS OF THE NINETEENTH See NUREG/CR4000,V09,N12 absitect NATER REACTOR SAFETY INFORMATION MEETING.

NUREGICR4900 V10 N6: LICENSFE EVENT REPORT (LER)

WEISS.A J Office of Nuclear Regulatory Research (Post COMPILATION For Month Of May 1991 ' Oak Fhdge Nabonal 860720). October 1991. 211pp. 9110200060. 59451.205-kboratoiy. June 1991, 95pp 9107??O259. ORNL/NSIC400.

This toport contains summanes of papers on reactor cafety gg499,q n$

research to be presented at the 19th Water Reactor Safety in-See NUREG/CR4'000N09.N12 abstrad formation Meeting at the Bethesda Marnott Hotel 6n Bethes4a, Maryland, October 28 30, 1991. The summanos teriefly desenbe NUREG/CR4000 V10 N6: LICENSEE EVENT REPORT (LER) the programs and results of nuclear safety resoarch sponsored COMPILATION for Month Of June 1991. ' Oak Ridge National by the Office of Nudear Hegulatory Research, USNRC, Summa-Laboratory. July 1991. 09pp. 9108130330. ORNL/NSIC400 e

nos of invited papers concerning nuclear safety issues from 58766 100.

U.S Govemmer,t laboratores, the electnc Uhleties, the Electric See NUREO/CR 2000,V09,N12 abstract Prwer Research histitute, the nuclear industry, and from the Dovernments aM14ndustry in Eu' ope and Japan are also includ.

NUHEG/CR4000 V10 Wh LICENSEE EVENT REPORT (LER) ed. The summanos have teen compiled in one report to provde COMPILATION For Month Of July 1991. ' Dak Ridge Nabonal a basis for meaungful decussion and information exchange Laboratory. August 1991, 75pp. 9109050256. ORNL/NSIC400.

during the course of th6 meeting, and are gtven in the order of 5BD89.204, their prer,entaten in each session.

See NUREG/CR4000,V09,N12 abstract NUREQ/CR 2000 VD9N12: LtCENSEE EVENT REPORT (LER)

NUREQ/CR4000 V10 NB: LICENSEE EVENT REPORT (LER)

COMPILATION For Month Of December 1990.

• Oak Rdge Na-COMPILATIONfor Month Of August 1991,

• Oak Rdge Naton.

tonal Laboratory. January 1991. 82pp. 9102140277. ORNL/

al Laboratory. September 1991, 69pp. 9110100244. ORNL/

NSIC400 $M93 231.

NSIC 200,59335:147, inis (nor'thly report Contains Licensee Event Report (LER)

See NUREG/CR.2000,V09,N12 abstract.

operational )nformabon that was processed into the LER data l

file of the Nuclear Safety Informaton Center (NSIC) dunny the NUREO/CR4000 V10 N9: LICENSEE EVENT REPORT (LER) one month penod ident feed on the cover of the document. The COMPILAllON For Month Of September 1991.

• Oak Ridge LERs, from which this informahon 6s derived Ale subrrutted to Nabonal Laboratory. October 1991. 96pp. 9112310154. ORNL/

the Nuclear Regulatory Commisson (NRC) by nuclear power NSIC400. 60161:080.

plant heensees in accordance witn federal regulations. Proca-See NUREG/CR 2000,V09,N12 abstract.

dures for LER reporting for revisions to those events occurring NUREG/CR4000 V10N10: LICENSEE EVENT REPORT (LER) pnor to 1984 are desenbed an NRC Regulatory Gude 1.16 and COMPILATION For Month Of Octobot 1991.

• Oak Rdge Na.

NUREG.0161, "Instruchons for Preparation of Data Entry tonal Laboistory. November 1991,141pp. 9112310155. ORNL/

Sheets for Licensee Event Reports." For those events occurring NSIC 200. 60160:2994 on and after January 1,1984, LERs are being subrmtted in ac-See NUREG/CR4000,V09,N12 abstract.

cordance with the revised rule contained in Trtle 10 Part 50.73 of the Code of Federal Regulatons (10 CFR 50.T3. Laconsee NUREG/CR4000 V10N11: LICENSEE EVENT REPORT (LER)

Event Report System) which was pub'ished in the Federal Reg-COMPILATION For Month Of November 1991.

• Oak Ridge Na-toter (Vol. 48, No.144) on July 20,1983. NUREG 1022, "Li-bonal Laboratory, December 1991, 79pp. 9201140010. ORNL/

censee Event Report System - Description of Systems and NSIC-200. 60299.108 Guidelines for Reporting." provides supporting gudance and trv See NUREGICR 2000,V09,N12 abstract.

I Main Citations Lnd Abstracts 17 NUREG/CR4907 V09. RADIOACTIVE MATERIALS rtELEASED the report uplains ho.r the sorece enay be acceswd. The on-iROM NUCLEAR POWER PLANTS Annual Report 1989 line service will be updated as new informat on is recMved TICHLER.J NORDEN.K., CONFMI,J Brookhaven National Laboratory. July 1991. 331pp v100210010 DNL NUREG.

WEG/CR4916: PRESSURIZED MELT EJECTION INTO

$1681. 68743 001.

WATER POOLS. T ARBELL.W W.: PILCH.M. Sandia National Releases of tedioatteve mato'ists in airborne and hould ef-Laboratones ROSS.J W.; et al s. tech Corp. March 199t, fluents from corronercial light water reacturs dunno 1988 have 110pp 9103260215. SAND 841531. 57161:230.

been compiled and reported Data on solid =asts shipments as The report riescribes five experiments that were periormed to well as sa!ceted operating information have been it'cluded Tbc study the inttuence of water pools on the behavior of pressure report supplements earber annual reports issued by the former driven melts Four of ti.e tests used knear scated models of re-Atomic Energy Commission und the Nuclear hogulatory Conk actor cavities Tho core simulant was a motten mixtura of alumi-mission The 1968 release data are summrtired in tabular form, Data covenng specific radionuchdes are summarized-na and iron created by a metallothermite reaction. In all experk merits, the pressure dovon jet interacted energetically w+th the NUREG/CH 314$ V09: GEOPHYSICAL INVESTIGATIONS OF water pool The appatatus containing the watur pool was de.

THE WESTERN OHIO INDI ANA REGION Annual otroyed in all cases, showing clear evidence of a violent fuel-Report October 1989 4 September 1990. MEERT,J.: RUFF.L.;

ccotant interaction. Pressure records and high speed framing LAFORGE,R ; et al Michegan, Univ. of, Ann Arbor, MI January carneta data were attempted in each test The recorded pres.

1991. 42pp 9103260132. 57152.343 sure waveforms appear to correla'e with previous steam explo.

Earthquake activity in the Western OhioIndiana region has sion experiments.

been monitored with a prectoiori seismograph network con"SI-ing of nine stations located in west central Ohio and four sta.

NUREG/CR 3964 V02: TECHNIQUES FOR-DETERMINING tions located in Indiana Two ir ;al earthquakes have been r,.

PROBADILITif.S OF EVENTS AND PROCESSES AMECTING _

corded during this report portod with magrittudes of 1.Om(L) and THE PERFORMANCE OF GEOLOGIC 2 2 m(L) Two near. regional events were recorded by the not, REPOSITORIES Suggested Approaches. APOSTOLAKIS,G.

work (Fostoria. Ohio and Clinton, Ilhnois events) with magnb Cahtornia, Univ. of, Los Angeles, CA BRAS,R. Hatael Bras Con-tudes of 2.3 m(L) and 3 4 m(b)L(g). Three other regional events aulting Engweers. PRICE.L; et al. Sandia National Laboratorles<

occurred w'th magnttudes ranging from 2 9 rn(b) to 4 6 m(b). All June 1991,184pp,9107010105. SANDB6-0196 58265 035.

the regional events occurred in, nr near, regions with well estab-The U S Envitonmental Protection Agency has established a lished histones of seismcaty-standard for the performance of geologic repositor es for the NUREG/CR 3444 V08: THE IMPACT OF LWR DECONTAMINA-disposal of radioactive waste. This standard is probabil$tc in TIONS ON SOLIDIFICATION. WASTE DISPOSAL AND ASSOCI.

nature, but the methods for determining probabilities of events ATED OCCUPATIONAL EXPOSURE Effects Of Composition On and processes of Int rest in emplementing euch a standed are The Strength. Swelling. And Water immersion Propcoties of still being developed Decisiori Theory, which involves Bayesian Coment Solidified lon Exchange Resin Wastes. SOO.P.;

probability techniques, can serve ab a framework for estimating MILIAN.LW. Rrookhaven National Laboratory. October 1991 ths probatWitty of occurrence of processes and events that are 100pp.9112310150 DNL NUREG 51699. 60177.175.

14iy la disrupt a geologc topository. This report presents the A study has been completed on the degradation and fadure mathematcal basis for such a methodology and dertenstrates mechanisms in simulated decontamination waste ion-exchange an application of it 6n three areas: climate change, tectonic resins solidified in Portland cement. The mixed bed resins were events, and human intrusion.

loaded with LOMI (low oxidation state metal 4on) reagent and vanous Mtionic species to ascertain how they influenced the NUREG/CR 4063: AN INVESTIGATION OF CORE LIOUID LEVEL strength, swell", set time, and wa'erdmmersion integnty of the DEPRESSION IN SMALL DREAK LOSS OF COOLANT ACCI.

tesultant waste forms. It was found that the properties of the DENTS. SCHULTZ,R R. EG&G Idaho, Inc. (subs. of EG&G, waste forrt,s were very dependent on the composition, as eu.

Inc.). MOTLEY,F.E4 STUMPF.H4 t al. Los Alahios National pected, and that ulfferent mechanisms for degradation and fail-Laboratory. August 1991. 168pp. 9108200249. EOG 2636.

ute were paesent for difierent compositional ranges.

L8912:040.

NUREG/CR 3469 V06: OOCUPATIONAL DOSE REDUCTION At Core liquid level depression can result in partial core dryout NUCLEAR POWER PLANTS. ANNOTATED BIBLIOGRAPHY and heatup earty in a small break loss of coolant accident tran-sient, Such behavtor occurs when steam, trapped in the uppor OF SELECTEtsyEAD%S IN RADIATION PROTECTION AND ALARA. KHAN, A4 VULIN,D Sa LANE S G.1 et al. Brookhaven reg.ons of the reactor pnmary system (between the loop seal and the core inventory), moves coolant out of the core region Oh PP'

- N and uncovers tne tod upper elevations. The net result is core E $170 One of the functions of'the ALARA Center is to collect and liquid level depression. Core liquid level depression and subse-deseminate information on dose reduction at t.,tlear power quent core heatups are investigated using subscale data from plants. This is the sixth report in the teries of bibliographies of the ROSA-IV Programu 1/48-scale LO0e Scale Test Facikty selected readings in radiation protection and ALARA that toe (LSTF) and the 1/1Y05 seule Semecale facility. Both facihties Center pubhshes penod cally. The abstracts 66 this bibliography are Westinghouse type, four loop, pressurtzed watnr reactor were selected from proceedings of technical meeting *, journals, simulators. The depression phenomena and factors whch influ-rosearch reports, searthes of information data bases and re, ence the rninimum core level are described and illustrated using prints of pubbshed artectes provided to us by the authnrs. The examples from the data _ Analyses of the subject expenments, abstracts relate in one way or another to dose reduction at nu.

cunducted using me TRAC-PFl/ MODI (Version 1P.7) thermabhy.

Clear power plants, whether it is through good water chemistry, draulic code, are also described and summarized. Finalty, the improvements in nuclear matenais, better control of corrosion, response of a typical Westinghouse four loop plant (RESAR-3S) robotics, and remote tooling or good operational health physics.

was calculated to quahtatively study core liquid level depression The report contains 268 abstracts. Subject and author indces in a full-scale system, are provided The subject index covers all previous volumes in this sones All information in the curtunt volume is atso available NUREQ/CR 4214 RtP2At HEAL 1H EFFECTS MODELS FOR from the ALARA Center's on-hne service, which is accessible by NUCLEAR POWER PLANT ACCIDENT CONSEQUENCE personal computer with the help of a modem. The preface of

I 18 Main Citations and Abstrsets ANALYSIS Modificatons Of Models Resulting rrom necent Re-special technical assistaxe, (5) crack-arrest technology. (6) ports On Health Effects Of lorurir4 Radiation tow LEI cleavage-crack initiaton, (7) cladding evaluations, (0) pressur.

Radiation Part it Scientile Bates For Health..

lied thermul shoch technobgy, (9) analyms methods validation, ABRAHAMSON S.

Wisconwn, Univ.

of, Madison.

Wl.

and (10) fracture evaluation tests. The program tasks havo DENDER.M A.

Brookhaven Nationel Laboratory.

been structured to place emphasis on the resolution fracture DOECKER.D B : et al inhalation Toxicology Research Institute issues with near term hcensing s6gnificance. Resources to eie.

August 1991. 8Bpp 9110090265. LMF 132 59329 308 cute the research tasks are drawn from ORNL with subcontract The Nuclear Regulatory Commission has sponsored s&veral support from universites and other research laboratones Close sturiren to identify and quant'fy the potent >al heatth effects of contact is maintainod with related ecsea*ch programs both in accidental releases of radorwchdes from nuclear power plants.

the United States and abroad.

The most recent heetth effects tnodels resulting from these of-forts were published in two reports NUREG/CH 4214, Hey,1 NUREGICR 4236: SELECTION OF SILICEOUS AGGREGATE Part I (1990) and Part ll (1989) Several rnaior health efiects re.

FOR CONCRETE CLIF10N J R; KNAB.! ! National institute of ports have been published recem.y that may impact the health Standards & Technology (formertv National Bureau of Standa.

effects models presented in those reports This addendum to January 1991. 22pp. 9102060171. NISTIR 4327. 56651:156.

the Part 11 (1989) report. provides a review of the 1986 and AlkalLaggregate capanssve teachns are one of the potential-19B8 reports by the Uruted Nations Scientific Committee on the ly senous degradaten problems that could affect the structural Effects of Atomic Radiation, the National Academy of Sc ences/

stab 61 sty of underDround concrete structures for disposing of low.

Natonal Research Council BEIR V Committee report and Publi-level radioactive wasto (LLW) it appeats that all aggregates cation 60 of the Irnomatonal Commismon on Radiological Pro-teact to some degree with alkabes in coment. In the majority of tection as they relate to this report The three main sectons of cases the teactons are beneficial (e g, increasing the bond be-this addendum discuss early occumng and continuing effects, twoon aggtogate and hydrated cement paste) or innocuous. In late somatic effects, and genetic c*fects. The major changes to some cases, however, the reactions result in the formation of the NUREG/CH 4214 health effech enodels recommended in orpansive products which can cause serious cracking of the this addendum are for late somatic effects. These changes re-concrete. This report deals with the selection of sliccous aggre-flect recent changes In cancer nsk factors that have come from gates to avoid deleterous alkbl6 aggregate expans6ons. Current lenger tollowup and revised dosimetry in major studies like that practices used to prevent expanstve allutl6 sihca reactions and on the Japanese A-bomb survivors. The results presented in the standard test methods used to identify reactive aggregates this addendum should be used with the basic NL,aEG/CR 4214 aie first discussed. Then the results of a study on using a new reports hated above to obtato the most recent views on the po-alkalbailica teactivity test to select siliceous aggregates for use tential health effects of radonuclides released accidet, tally from in the Concrete of ELW disposal structures are pesented. It is nuclear powar plants recommended that siliceous aggregates, selected tot construct.

NUREG/CR-4219 V07 Nt: HEAVY SECDON STEEL TECHNOL.

6ng underground vautte for disposal of LLW. have an expanson OGY PROGRAM. Semiannual Progress Report For Oc'ober of less than 0.10 percent using the new test.

1989 March 1990 PENNEtt,W in Oak Ridge National Labora-NUREG/CR 4269: MODELS OF TRANSPOHT PROCESSES IN tor March 1991, 103pp. 9104220334. ORNL/TM 9503 CONCRETE, POMMERSHEIM,Ja CLIFTON J.R National Insto Tim Heavy Secteun Steel Technology (HSST) Program is con, tute of Standards & Technology (formerly NationW Dureau of ducted for the Nuclear Regulatory Commission (NRC) by Oak Standa, January 1991, 104pp 910l3001$1. NISTIR 4405.

Ridge National Labors %ry (ORNL). The program focus is on the 56535:024.

development and validaten of technology for the assessment of An apptcach being considered by the U S. Nuclear Regula-fracture prevention margins in commercial nuclear reactor pres.

tory Commission for disposal of lowdevel radioactive wute is to sua vessels. in the current repor1.ng penod, reorganization of place the waste forms in concrete vautts buned underground.

the onginal HSST program into separate programs with empha.

The vaults would need a setvice lite of 500 years Approaches ses on fracture mechanics technology (HSST) end matenals irra-

'O' Pd CI'ng the service life of concrete of such vaults include diaton ettects (HSSI) has been completed The revised HSST the une of mathematical models Mathematical models are pre-program is organized in 10 Tasks. These are (1) Program Man-sentW % this report tot the maior degradalen processes antici-agement, (2) Fracture Methodology and Analysis, (3) Material patec r the concrete vaults, which are corrosen of steel rein.

Characterization Tasks. (4) Special Technical Aswstance, (5) forcement, sulfate attack, acMI attack, and teaching The models Crack Anest Technology, (6) Cleavage Crack initiation (7) Clad.

mathematically represent rate controlling processes including ding Evaluatens, (8) Pressunred-Tnermal-Shock Technolo0Y, diffublon, convection, and reacton and sorpton of chemnal (9) Analysis Methods Val dation. (10) Fracture Evaluation Tests.

speces, These models can form the basis for predtCilng the life i

The program tasks have been structured to place emphaws on of concrete under 6n-service conditons.

the resoluton fracture esauen with near term heensing signifi-NUREG/CR-4195: DOND STRENGTH OF CEMENTITIOUS

"""C' BOREHOLE PLUGS IN WELDED TUFF. AKGUN,Ha NUREG/CR-4219 V07 N2: HEAVY SECTION STEEL TECHNOL-DAEMEN,J.J K. Anzona, Univ, of, Tucson, AZ. February 1991.

OGY PROGRAM. Semiannual Progrsss Report For Apni-Sep-315pp 9103200031. 57063-039.

tember 1990, PENNELLW E. Oak Hedge Nstional Laboratory.

This study includes a systematic invostigation of the bond September 1991. 139pp. 9110090303. ORNL/TM 9593.

strength of comentatious borehole plugs 6n welded tuff. Analyto 59327.001.

cal and numer' cal analysis of borehole plug rock Stress transfer The Heavy-Section Steel Technology (HSST) Program is con-mechanics is performed. The interface strength and deformation ducted for the Nuclear Regulatory Commission (NRC) by Oak are studied as a function of Young's modulus ratio of plug and Ridge Nabonal Laboratory (ORNL) The program focus is on the rock, p:ug length, and rock cyhnder outside-to-inside radius development and vahdaten of technology for the assosament of istio The tensile stresses in and near an axially loarko plug are fracture preventon margens in commercial nuclear reactor pres-analyzed The Inctional interface strength of an axially loadod sure vessels Reorgantration of the original HSST Pro 0'am into borehole plug, the effect of axial stress and lateral external separate programs with emphasis on fracture-mechanics tech-stress, and thermal effects are also analyzed Imphcations for nolog, (HSST) and matenaltWnudiaton effeca (HSSl} was pre, plug design are discussed The mair, conclusion is a strong rec.

viously completed. The revised HSST Program is organized in ommendet on to denugn friction plugs in shafts, dnfts, tunnels, or 10 tasks- (1) program management. (2) fractite methodology boreholes with a minimum length to diameter rate of fouA Such and analysis, 0) material characterization and propertes. (a) e geomelncal design will reduce tensde stresses in the plug and 9

[

Main Citations and Abstracts 19 in the host rock to a level which should rnarvmge the risk d plans sitebung AFW irsk important (emponents at the Byron /

long term detenoration caused by excessive lensile strettes Draidwood plants Push out tests have been used to determine the bond strength

(

by apply!ng an asia' toad to cement plugs emplaced in bore.

NUnlG/CR 4444: RADIATION SAFETY ISSUES RELATED TO holes in welded tuff cyhnders A total of 130 pushout tests RADIOLABELED AN11 BODIES BARBE R,D E.; BAUMJW.;

have been performed as a function of borehole sire, plug MEINHOLD C.D. Brookhaven Natonal Latoratory. March 1D31, longth, temperature, and degree of naturation of the hose tuff <

20Bpp 91040402D0. BNL NUREG-$2276. 57261:140, The ube of four different borehole radii enables evaluaton of Techniques related to the use of radiolabeled &ntibodies in we effects. A welldehned exponential strength doctease with humans are renewed and evaluated 6n this report it ts Intended increasing plug diameter results. While these estrapolated as an informational resource for the U.S. Nuclear Regulatory strengths can be used for the design of large diameter plugs.

Commission (NRC) and NRC heensees, Desenptons of tera-e g, in shafts or dr'fts, it would be desstable to confirm the en-naques and heatth and safety issues are provided Pnncipal t'apolations by tests on larger plugs.

methods for labehng antibodies are summartred to help identdy NUREG/CR 4302 V02: AGING AND SERvlCE WEAR OF CHECK related radiaton safety problems in the preparaton of dosages VALVES USED IN ENGINEERED SAFETY-FEATURE SvS-f r administraton to patients. The desenptons are derived from TEMS OF NUCLLAR POWER PLANTS Aging Assossmonts And an extensive literature review and consultations with esperts in Monstonng Method Evaluations HAYNES.H D. Oak Ridge Na-the held A glossary of terms and acronyms is also included Ao tonal Laboratory. April 1991. 73pp 9104223317. ORNL 0193

, asessment was made of the extent of the involvement of orga-

$744B 278 etizatons (other than the NRC) with safety issues related to re-Check valven are used extensively 14 riuclear power plant diolabeled antibody in order to identify regulatory issues which f

3 Hen

n. f ederal regulations and guides were Also re-

$dfety systems and balanco-of-plant systems The failures of these valves have resulted in significant maintenance efforts viewed for thsier relevance. A few (but significant) differences and, on occasion, have resulted in wator hammer, overpressurs-between the use of common radiopharmaceuticals and radola-raton of low-pressure systems, and damage to flow system beled antibodies were observed. The clearance rate of whole, components. These failures have largely bosn attributed to radolatWed imtnunoglobuhn is somewhat slower than common sovere degradation of integral parts (o g, hinge pins, binge radiopharmaceuhrals, and new methWs of administration are arms, discs, and disc het pins) re6ulting ffom instabihty (flutter) being used. New nuchdes are being used or considered (e g, or check va ve discs under normal plant operating conditions.

Re 186 and Al 211) for tatcling antibodies Sume of these nu-r Present surveillance regerements for nuclear power plant check clides present new dosimetry, instrument cahbrat on, end pahent valves have been inadequate for timely detecten and trending managemord poblems. Subjects related to radiaton safety thbt of such degradation becasse neither the flutter not the resulting require additional research are 6dentihed.

wear can be detected prior to failure. Conenquenti), the U S.

Nuclear Regulatory Commission has had a continuing strong in-NUREG/CR 4469 Vtt NONDESTRUCTIVE EXAMINATION terest in resotving check valve problems, in support of the Nu-(NDE) RELIABILITY FOR INSERVICE INSPECTION OF LIGHT clear Plani Ag ng Research Program. Oak Ridge National Labo-WATER RE ACTORS Semi-Annual Report, ApnbSeptember ratory has camed out an evaluation of several developmental Memonal Institu'S A4 GOOD.M.S'; GREEN E R; et al. Dattelle 1989. DOCTOR and/or commercially available check valve diagnostic monitor.

te, Pacific Northwest Laboratory. August 1991.

6ng methods, in particular, those based on measurements of 72pp. 9110090288. PNL 5711,59331:141.

acoustic emission, ultrasonics, and magnetic flun. in each case, Evaluaton and improvement of NDE Rehability for Inservice the evaluations have been focused on the capabikty of each inspection of Light Water Reactors (NDE Rehabikty) Program at method to provide diagnostic information useful in determining the Pacinc Northwest Latxiratory was established by the Nucle-check valve aging and service wear effects (degradation), check af Regulatory Cummission to determine the rehability of current valve failures, and undesvable operating modes A description Inservice intpecton (ISI) techniquet, and to develop recommen-of each rnonitonng method is provided an this report. Including dations that will ensure a suitably high inspecten relabihty. The i

examples of test data acquired under controlled laboratory con, objectives of this program include determirung the rehability of ditons. In some cases, field test data acquired in sita aie also ISI periormod on the primary systems of commercial light water presented The methods are compared, and suggested areas in reactors (LWRs), using probabihstic tracture mochanics analysis need of further development are identshed.

to determine the impact of NDE unrehability on system sale *y; and evaluating rekatukty improvements that can be achieved NUREG/CR 4427: AUXILIARY FEEDWATER SYSTEM RISK' with improved and advanced technology A final objective is to BASED INSPECTION bulDE FOR THE BYRON AND BRAID-formulate recommended revisions to ASME Code and Regula-WOOD NUCLEAR POWER PLANTS.

MOFFITT.N C ;

tory requiremer.th, based on matonal properties, sennce condi-GORE.B F.; VO,T.V. Battene Momorial Institute, Pacihc North-tions, and NDE uncertainties, The program scope ls kmeted to west Laboratory. July 1991. 35pp. 9108130320. PNL 7492.

ISI of the primary systems including the piping. vessel, and 58766 069 other components inscected in accordance with Section XI of in a study sponsored by the U.S. Nuclear RegulMory Com-the ASME Code. This is a progress report covenng the pro-mission (NRC), Pacihc Northwest Laboratory has developed and grammat:c work from Apnl 1989 through September 1989.

opphed a methodology for deriving plant specibc risk-based in-specton guidance for the auxihary feedwater (AFW) system at NUREG/CR-4513: ESTtMATION OF FRACTURE TOUGHNE33 pressunzed water reactors that have not v,dergone probabikstic OF CAST STAtNLESS STEELS DURING THERMAL AGING IN risk assessment (PRA). This meModcagy uses existing PRA re-LWR SYSTEMS CHOPRA.O K. Argonne National Laboratory.

suits and plant operahng exponence iniorma' ion. Existing PRA-June 1991,74pp. 9107010083. ANL40/42. 58249.001, based inspection guidance informahon recentty developed for A procMure ar ri ccrrelations are presented tw predicting the the NRC for various plants was used to identify ocneiic compos change in fracturg Wgnriess of cast stainless steel compo-nent failure modes This information was then combined with nerits due to thermai 9;ing dart'v,} service in hght water reactors plant spec he and industry wide component information and fat' (LWRs) at 280-330 C 635425 Fi The fracture toughness J-R ure data to identify failure modes and failure mechanisms for curve and Charpy-impet ener0y c8 oged cast stainless steels the AFW system at the selected plants. Byron and Draicwood are estimated trom kun material information. Fracture tough-were selected for the fourth study in this program. The product ness of a specific cast s'yniess steel is estimated from the of this effort is a priontired hsting of AFW failures which have extent and kinetics of thermal embrittlement The extent of ther.

occurred at tne plants and at other PWRs. This hsting is intend.

mal embnttlemon; is characterized by the room temperature ed for use by NRC. inspectors in the preparation of inspection "normahred" Charpy impact energy. A correlation for the extent

20 ain Citations and Abstracts of embrittlement et "saturrton," let, the minimum impact l'ragility estimates of seven equipment classes were pub-chergy that would be achieved for the anatenal after long. term br.hed in earlier reports. Tha.vport grebe-ts fragility analysis re-aging. so given in terms of a matenal parameter, 4, which 18 suits for eleven ad$twis! equipment categones_ The fragMy determired from the chemical cornositon. The f*acture tough.

levels are empressed in pitnbelistic terms For users' oonvte ness J.R curve for the matenal is then obtained from correla-ionce, the concluding report includes a wmmary of frag 4ty is tions between room. temperature Ct'arpy. impact energy and suits of att eighteen equipment classes A but of convers600 f4c-fracture toughness parameters. Fracture taughness as i func*

tors based on judgment is recommended for use of the informa-tion of tme and temperature of reactor service is estimated tion for early vintage equipment The knowledge gained in con-from the kinetics of thermal embnttlement, which is determined ducting the Comoonent Frag $ty Program and similar other pro-from chemical composition. A common

• lower < bound" J.R grams is expectod to provide a new dirDctoh for setsmic voiifb curve for cast stainiuss steels with unknown chnmtcal composi-Caton and qualificatton et equipment, tion is also defined for a given matonal specificat:on, ferrite con-tent, and tempef eture.

NUREu/CA.4666: LLOSEOUT OF IE BULLETIN 84-02. I'All-NUREG/CH 4561 V2 RIP 2: EVALUATION OF SEVERE ACCI.

URES OF GENERAL ELECTRIC TYPE HFA RELAYS IN USE DENT RISKS. QUANTIFICATION OF MAJOR INPUT IN CLASS 1E SAFETY SYSTEMS. FOLEY,W.J4 DEAN.H.Sa PARAMETER 9 Emperts' Determinaton Of Containment Loads-ttENNICK,A. PARAMD ER, Inc. January 1991. 54pp.

f And Molten Core Containment intoraction issues. HARPER.F.Ta 9104300323. PARAMET ER IE163, 57657:129.

PAYNE A.C.; DREEDINGft Ja et al Sanuia National Laborato-Documentaten is prwided in this report to clore lE Bulletin nes Apnl 1991.469pp 9105160319 SANDBM309. $7714121.

64 02 regarding the failure of General Electnc Type HFA telays in supped of the Nucleat Regulatory Commission's (NRC's) in Class 1E safety systems The relay failures were due to aging assessment of the risk from tevere accidents at commercial nu.

of coil wire insulation and nylon or Lexan rpools under certain clear power plants in the U.S. reported Irt NUREG 1150, the environmental conditons The bulletin was issued to nuclear Severe Accident Risk Reduction Program (SARRP) has com-power reactor hcensees and holders of constructon permits to pteted a revised conculation of the risk to the general pubhc provide assurance that the manufacturer's recommendations for from severe accidents at five nuclear power ;>! ants Surry, Se*

corrective actions would to implemented. The bulletin required quoyah. Zion, Pea:h Bottom, and Grand Gulf. The emphasis in this risk analysis was not on determining a "so-called' point es-four specific actions, plus a review of the generaf concerns of timate of risk. Rather,it was to determine the distribution of rif k, the bulletin even though 60me fact.bes had different retays from those of bulletin concern',Evalualson of utikty responses, NRC/

and to discover the uncertainties that account for the breadth of Ngon inspoction reports and regional telephone calls has to.

this distnbution. Off site nsk initiated by events, both internal to the power station and enternal to the power station was as, suited in bulletn closecut of 116 (98%) of the 118 facihties to sessed. Much of the 4mportant input to the logic modols wag which the bul'etin was Ibsuod for action Facilities which were generated by expert panets. Th's doNment prosent1 the oistr;.

shut down of had constructen halted indef,nitely or permanently butons and the ratonale supporting the distnbulkris for the when the report was issued are not included in this review. A questions posed to the Containment loads and Molten Core follow-up item is proposed 6n Appendis C for the two facihties interaction Expert Panels, with open status Background information is supplied in the Irv NUREG/CR 4599 V01 N1: SHORT CRACKS IN DIPING AND k duden ad @@ A PIPING WELDS Somiannual Report. March Set ber.1990 NUREG/CR 4667 V09: ENYlRONMENTALLY ASSISTED CRACK.

WILKOWSKI.O M.; AHMAD,J.: BRUST,F.; et al Battelle Memori-ING IN LICHT WATER REACTORS. Semiannual Report.Apni-al nati e.

May 1991. 129pp 9105300205. BMI 2173 Septerrber 1939 KASSNEH,TL; PARK,J.Y,; RUTHER.W.E4 et This is it$e first sem4 annual report of the U.S Nuclear Regula.

al.

Argonne Nstional Laboratory. March 1991. 30pp.

tory Commission's Short Cracks in Piping snd Piping Welds re, 9104220214 ANL 90/48. $7450.263.

search program. The program began in March 1990 and will This report nummarizes work perforrned by Argonne Nat6onal entend for 4 years. The Intent of this program is to venty and Laboratory on environinentally assisted cracking in light water improve fracture analyses for c6rcumferentially cracked large de reactors dunng the six months from April 1909 to September ameter nuclear piping with crack sites typically used in leak.

1989. Topics that were investigated include (1) atreus corrosion before-break analyses or in-service flaw ovaluations. Only quoi-cracking (SCC) of A533 Gr B steel in simulated bothng-water.re-static 10ading rates are evaluated since the NRC's Internationa actor environmonts, (2) SCC of Typen 347 and CF.3 cast Piping integnty Research Group Program is evaluating the of.

duplex t.tainless steel (SS), and (3) effects of heat to-heat vana-facts of seismic toading rates on cracked piping systems. Addo

. tion on SCC of Type 304 SS. Crs% growth-rate (CGR) tests tional efforts involve investigating phenomena discovered during were periormed On converitional (nr.,,tplated) and ryckel-or gold-the course of conducting the Degraded Piping program. These plated A533-Gr B specimens to prnvide insight into whether the include the evaluation of the occurrence of unstable crack surface layer 01 the low-alle'/ steel, either oxide corrosion prod-jumps in ferrttic stee's at LWR temperatures, and the occur.

. ucts or a noble metat,lnfluences the overall SCC process. CGR

'3nce of anisotropic fracture properties causing, hehcal crack tests were also conducted on specimens of Type 347 SS with growthJ Both of these phenomena may aff0ct the sably mar

• different heat treatmente, and a specimen of CF-3 cast S3 with gins impbcit in leak before break (LBB) analybes. Other invest" a fernte content of 15 6% CGR data on these specimens were gations deal with the fracture behavior of bi-metGC welds, and compared with reference fatigue crack growth Curves in the unprovements in crack opening area anatyses used in LBB.

ASME Bc3er and Pressure Vessel Code, Socton xt Appendix unce much of the work in this prograrn was just beginning

~ A. The influence of approximately 1.0 ppm of CuCl indeorygen-dunng this first reporting period and progress is hmited, a com' plete statement of work for the whole program is provided in tated water on the SCC susceptibility of Types 316NG and 347 SS and A533 Gr B and A106-Gr B ferntic steels was deter, q

mined in constant eittension-rate tensile (CERT) tests at 200 C.

NUREG/CR 4659 V04: SEISMIC FRAGILITY OF NUCLEAR The CERT results indicated that the alternative SSs were con.

POWER PLANT COMPONENTS (PHASE 1lLA Fragibty Hand

• Lederably more resistant to 500 than is sensitized Type 304 SS.

book-On Eighteen Components. BANDYOPADHYAY:

The low alloy ferritic steals exhibited oniy ductile tracture m this HOFMAYER C.H.; KASSIR,M K.; et al. Brookhaven National environment.

Laboratory. June 1991,36pp.9108130313. BNL NUREG 52007.

58766.031.

I'

.A._.s....

I MalR Citations and Abstracts 21 NUREG/CR 4667 V10: ENVIRONMENTALLY ASSISTED CRACb (CG45) of femtic steels to loading puamotors have been modF ING IN LIGHT WATER REACTORS.

Semiannual feed to incorpotste CGR data that we recentiy acquired at high Report.0ctoter 1989 March 1990.

RUTHER.W E ;

toad ration. The effect of water flow rate on the SCC behavor SHACK,W.Ja CHUNG.H M ; et al. I re Nat onal Laboratory of Type 316NG stainless ett t. (SS) was 6nvestigated in tracture.

March 1691,30pp,910422029( A 1/5, 67450.231.

mechanics CGA tests in HP oxygenated water at 289 degrees This repuil summartres work penu aed by Argonne Natonal C, Corrosion fatigue curves for austenstic SS in Section XI of the Laboratory on enwonmentally assated *acking in bght water ASME Doilor and Pressure Vesset Code have been modified to reactors dunng the six r%nthr frem Ooober 1989 s March be more consistent with SCC data in simulated LWR environ.

s 1990. Low cycle fatigue tests were pertnnw on Typ.

TNG monts at high load ratios. High and commercial-punty (CP)

SS to better utiderstand the effects of cyche strain range, fre*

specimens of Type 304 SS from BWR abtorber rod tubes irra-quency, and temperature on fattgue 1,4 in air aM in simulated diated dunng service 6n two rcactors to fluence levels of 1.4 2 x BWR water, and to assess the degree of conservatem ln the 10(21) n,cmt.21 (E >1 MeVI, were examined by Auger electron ASME Code Section 111 latigue design curven. Fracturo mechan-spectroscopy to charactertre irradiatort6nduced grain boundary les crack growth rate tests were carned out on a composite g,9,egation and depletion of alloying and 6mpunty elements, specimen of A$33.Gr0/loconel102/inconsl400, plated with which have been associated wm irradiation-assistea SCC of the tickel, to establish whether a transgranular crack will Initiate 6n steel Slow strain tate tensile tests have been conducted.n air the forntic steel from an intergranular crack in the inconel.182 and in simulated BWR water on specimens obtained from the weld metal at low stress intensit', associated with crack grath irradiated CP Type 304 SS absorber-rod tubes.

in the inconel 182 weld metal. Irradiated stainless.

• from abborber rod tubes, control-rod cladding and flux thimb!cs of NUREQ/CR 4670: RADIONUCLIDE UlSTRIDUTIONS AND Mi-several DWRS and PWHS were obtained to investigate the GRATION MECHANISMS AT SHALLOW LAND BURIAL nature and extent of ra6aton-induced segregation in the steels SITES Final Report Vf PNL Reseamh investigatons On The and correlate it with susceptibiity to intergranular failure in the Distribution, Migration Ar.d Containment Of Radionuchdes At matenals Specimens have been prepared for Auger electron Maney

Flats, Kentucky.

KIRBY,LJa TOSTE,A P.;

spectroscopy analyses of segregation of alloying elements on THOMAS,C.W.; et al. Badelle Memonal Institute, Pacific North-intergranulai fracture suriaces west Laboratory. February 1991. 95pp 9103120103. PNL 7582.

NUREQ/CR 4667 Vit ENVIRONMENTALLY ASSISTED CRACK-N90 2N ING IN LIGHT WATER REACTORS. Semiannual Roport,Apol.

Dunrig the past several years, Pacific Northwest Labordory Septembur 1990. CHUNG,H.M; VASSNL A.T.F.; SHACK,W.J.;

(PNL) has conducted research at the Maxey Flats Disposat Site et al. Argonne National Laboratory. May 1991. 37pp.

(MFDS) for the U S. Nuclear Regulatory Commission (NRC).

910$300212. ANL 91/9. 57867316.

This work has 6dentified the spectrum of radionuclides present This report summantes work performed by Argonne Nationai 6n the waste trenches, determined the processes that were oc.

Labcratory on environrrentally assisted cracking in hght water curnng relative to degradation of radioactive matenal wit * 'he reactors dunng the 6 months from April 1990 to September bunat trenches, determined the chemical and physical : Jac.

1990. Crack growth iate (CGR) tests were performed on a com.

tenstics of the trench teachates and the chemical forms of the posde A533 Gr 8/inconel182 specimen in which a stress cor.

leached radionuchdes, determined the mobitiy of these radionu-rosion crack in the inconel-182 weld metal ponetrated and grew chdes, invostigated the subsurface and surface transport proc-into the A533 Gr B steel. CGR tests were also conducted on esses, dr.termined the biological uptake by the native vegeta-conventir ial (nonplated) and Nu or Au-plated A$13.Gr D spec 6 tion, developed strategies for environmental monitoring, and in mens. CGR data o9 the A533 Gr D specimens were compared vestigated other factors that influence the long-term fate of the with the fatigue crack roterence curves in the ASME Boiler and radionuclide inventory at thr d'sposal site. This report is a final Pressure Vetael Code, Secton XI, Appendix A. High-and com.

Summary of the research conducted by PNL and presents the mercial-punty, HP and CP, respectively, specimens of Type 304 results and discussions relative to the above investigatNo areas.

SS from DWR absorber rod tubes, irradiated during service to fluence levels of Ex10(20) 2x10(21) n cm( 2) (E> 1 MeV) in two NUREG/CR 4674 V13: PRECURSORS TO POTENTIAL SEVERE reactors were examined by Auger electron spectroscopy ta CORE DAMAGE ACCIDENTS:1990 A STATUS REPORT. Main charactenze irradiaton induced grain boundary segregation and Report And Appendix A. MINARICK,J.W. Science Apphcatens depletion of alloying and impunty elements, which have been internatonal Corp. (formerly Science Apphcations, Inc) a6sociated with irradiaton ass!sted stress corrosion cracking of CLETCHER,J W. Professional Analysis, Inc, COPINGER,0 A.; et the steel. Intergranular f acture surf aces in high fluence CP rna-al. Oak Ridge National Laboratory. August 1991. 180pp.

tenal were character %d by relatively high levels of Si, P, and Ni 9109300062. ORNL/NOAC-232, 50227:001.

segregaten. Segregaton o, the impunty elements and intergian-Twentreight operational events with condit#onal probabihoes ular failure in the HP material were neghgible for a similar of core damage of 1.0 x 10( 6) or higher occurnng at commer-fluence level. However, grain boundary depletion of Cr was cial kght water reactors during 1990 are considered to be pre-more significant in HP matenal than in CP material, which indy Cursors to potential severe core damage These are desenbod cates that triadiationinduced segregation of impunty elements along with associated significance estimates, categon2aton, and deplebon of alloying elements are interdependent.

and subsequent analyses This study is a continuation of earher work, which evaluated the 19691981 and 19841989 events.

NUREG/CR 4667 V12: ENVIRONMENTALLY ASSISTED CRACK-Tne report discusses (1) the general ranonale for this study, (2)

ING IN LIGHT WATER R'cACTORS.. Semiana sal the selection and documentation of events as precursors, (3)

Report, October 1990 March 1991, SHACK,W.J.; H!CKSi.u; the estimation e $ use of conditional p.obabilities of subse-RUTHER W E.; et at. Argonne Nabonal Laboratory. August 1991,67pp. 9110090270. ANL 91/24. 59330:036. -

quent sevwre core camage to rank precursor events, and (4) the plant models used in the analysis process.

This report summanzes work performed by Argonne National Laboratory on environmentally assisted cracking in light water NUREG/CR 4674 V14: PRECURSORS TO POTENTIAL SEVERE.

= reactors dunng the six months frorn October 1990 to March CORE DAMAGE ACCIDENTS 1990

.A STATUS 1991 Fatigue hfe of A533-Gr B pressure vessel steel was stud-REPORT. Appendixes D And C, MINARICK,J.W. Science Apple eed in high-purity (HP) deoxygenated water, in simulated PWR cations International Corp. (formerly Science Apphcations, Inc.).

water, and in air Fatigue data are compared with the design CLETCHER.J.W. Professional Anaiysis, Inc. COPINGER,0.Aa et curve in Secten 111 Appendix A of the ASME Boiler and Pres-al. Oak Ridge National Laboratory, August 1991. 493pp.

sure Vessel Code Equatons in Section XI of the ASME Baer 9109300095. ORNL/NOAC-232. $9227;312.

and Pressure Vessel Code that relate crack growth rates See NUREG/CR 4674,V13 abstract.

m

__.m_2__---.u-

22 MalR Citations and Abstracts NUREG/CR 4690 V01 R1: GENERIC COMMUNtCATIONS This piogress report summanzes work performed by Argarine INDEX.Lishngs Of Communications 1971 1089 National Laboratory on long. term tN rmal embrittlement of cast HAGEMEYER 0; TOWLE H Science Applicatons international duples stainless steels tri LWR systems dunng the 6 mon'hs Corp (formerly Science Appimatons, Inc ) May 1991. 446pp.

from April to September 1989 Tensile and fracture toughner,s 91001902/6 3AIC40/1393 68826 002 data are presented for several heats of cast stainless steel that As part of its program to feed back informaton on opettling were aged up to 30.000 h at temperatures of 200-450 C. The expenonce to industry, the U S. NuclJar Regulatory Commission results indicate that thermal aging increases the tensile stress (NRC) it! sues genent communicatons called bulletins (sbout $/

and decreases the fracture toughness of the materials In gen.

yr) circulars (now discontinued), genenc letters (about 20/yr).

erel, CF4 steels are the least sentitwo to thermal aging embnt.

and informaton notices (about 100/yr), The report presents an tiement and CF BM steals are the most sensitive. The increase updated Genene Communications Inder (GCI, previously pub-an flow stress of fully aged cast stainless steels is -10% for lithed in NUREG/CR 4690, Vol 1, December 1907) of all such CF.3 steels and - 20% for CDB and CF-BM steeis. The trac.

cornmunications from 1971, when such documentaten started, ture toughness J(IC) and average leanng modulus for heats that to 1989 The GCI consists of records, one for each communica-are sensattve to thermal aging (o g., CF4M steels) are as low as tion, cantain'ng fields for 6dentificat on number, title, NRC techni-

- 90 kJ/m(2) and - 60, respectively. Corialations are presented cal contact, general kystem or topic, speafe compunent or for esternating the lacrease in flow stress of the steels from data topic, cause or defect potential effect, remaru M vendors in.

for the kinetics of thermal embnttlement, HU EG/CR 44 V05 N LOf TERM MBR TTL MENT OF a ns o cat st gs tc o ur tons m,

N9 REG /CR 4735 V07: EVALUATION AND COMPILATION OF SYSTEMS. Semiannual Report, October 1909 March 1990.

DCiti WASTE PACKAGE TEST DATA. Diannual Report: Febru.

CHOPRA.O K.; DUSH LY, Argonne National Laboretory, July ary July 1989. FRAKER A Ca ESCALANTE.E. Na'ond Institute 1991. 46pp. 9108130296. ANL 91/7,68765 260.

of Standards & Techr' logy (formerly Nstional Bureau of Th* progress report tummanzes work periormed by ANL on Standa INTERRANTE,(

Division et High-level Weste Man.

long term thermal embntilement of cast duples stainless steels agemern (Post 870413). Oecember 1991.136pp. 9201000106.

In LWR systems dunng the six months from October 1989 to 60232.001.

March 1990, lhe results from Charpy4mpact tests and micro.

This report summarties evaluations by the National Institute hardness measurements of the femte pht.se for several heats of Standards and Technology of Department of Energy activit.es of cast stainless steel aged up to 30,000 h at 290-400 degrees on waste packages designed for containment of radiosctive C are analyzed to estabbsh the kinetics of thermal embnttle.

high level nuclear waste for the six month penod, February ment. Correlations are presented for predicting the eirtent and through July,1989 This includes teviews of related matunals knietics of thermal emtntilement of cast stainless steels from research and plans, informaton on the Yucca Mountain, ma'enal information that can be determined from the certified Nevada disposal site activities, and other triformaton regarding mate,'tal test record. The extent of embrittlement is character.

supporting research and special assistance. Outhnes for trod by the ioom temperature "normahred" Charpy impact planned interpretatsve reports on the topics of aqueous corro.

onergy. Dased on the iriformaton ava'lable, two methods are son of copper,(nochanisms of stress corrosion cracking and in.

presented for estimating the extent of embottlement at *satura-tornal failute modes of Zarcaloy cladding are included. For the tion," le,, the minimum 6mpact energy that would be achieved publications reviewed dunng this reporting penod. short discus.

for the material after long term aging. The first method utiltres sions are given to supplement the completed review" and eval-only the chen tcal composrtion of the steel The second method uations. Includod tn this report is an overall review of a 1994 is usod when metallographic 6nformation on the fernte morphol-report on g! ass leaching mechanisms, as well as reviews for ogy, i 9. ferrite content 6nd mean fernte spacing of the steel, is each of the seven chapters of this report.

also svaltable. The change in Charpy-impact energy as a func.

tion of time and temperature of reactor service is then estimat-feUREG/CR 4744 V04 Nt: LONG. TERM EMBRITTLEMENT OF ed from the extent of embnttlement at saturatian and from the CAST DUPLEX STA!NLESS STEELS IN LWR conelations describing the kinetics of embrittlement, which is SYSTEMS. Semiannual Report, October 1988 March 1989.

expressed in terms of the chemical composition and aging be-CHOPRA,0K; CHUNG,H.M. Argonne National Laboratory. May havior of the steel at 400 degrees C, 1991,42pp. 9105300192, ANL 90/44. 57868.245.

This progress report summanros work performed by Argonne NUREG/CR 4744 V05 N2: LONG-TERM EMBRITTLEMENT OF National Laboratory on long-term e,bnttlement of cast duplex CAST DUPLEX STAlt.LESS STEELS IN LWR stainless steels in LWR systems dunng the 6 months from Oc.

SYSTEMS Semiannual Report, April September

1990, tober 1988 to March 1989. Charpyampact data are presented CHOPRA.O K. Argonne National Laboratory, July 1991,108pp for several heats of cast stainless steel aged at temperatures 9108130289. ANL 41/10,58765152.

between 320 and 450 C far times up to 30,000 h. Thermal This progress report summanres work performed by Argonne aging decre ases impact energy and shifts trans%n curves to Natonal Latostory on long terrr embnttlement of cast duplex higher temperatures A saturaton efioct is obse..,d for room.

stainless steels in LWR systems dunng the six months from temperaturo hpact energy and upper. shelf energy, Charpy data April September 1990. A procedure and correlations are pre-are anatyred to obtain the activation energy of the kinetics of sented for predicting fracture toughness J R curves and impact embrittlement, lhe results suggest that the actr<ation energy of strength of aged cast stainless steels from known material infor-embnttlement is not constant in the temperature range of 290 mation. Fracture toughness of a specific cut stainless steel is 400 C, but increases as temperature decreases. A correlation is estimated

• rom the extent and kinetics of embnttlement. The presented for estimating the extent of embrittlement of cast extent of embnttlement is charactertred by the room tempera-stainless steels from known material parameters. The degrada-ture Charpyimpact envgy. A correlation for the catent of em-ton in mechantcal properties can be reversed by anneahng the bnttlement at saturaton is given in terms of a materi9l parame-embnttted matenal for 1 h at $50 C and then water quench 6ng.

ter, e, wh;ch is determined from the femte morphotogy and/or chemical compositsort Charpy impact energy as a functon of NUREG/CR-4744 V04 N2: LONG TERM EMBRITTLEMENT OF time and temperature of reactor service is estimated from the CAST DUPLEX STAINLESS STEELS IN LWR kinetics of embrittlement, which are determined from chemical SYSTEMS Semiannual rieport,Apni-September 1989 composition The fracture toughness J R curvo for the matenal CHOPRA,0X; SATHER ' : BUSH.LY. Argonne National Labo-is then obtained from correlations between room-tempe'ature ratory. June 1991. 341pp,9107010128. ANL-90/49. 58251:095-Charpy-impact energy and fracture toughness parameters. A

Main Citations and Abstracts 23

'60*er bound" J R curve for cast stainless stects with unknown spe.tve semmic capacity levels SNe l'equency eucitaton chemical compWtson is also defined for a given matenal speci.

was owd for most of the test runs, multifrequency random fication and temperatutt. Mechanical-property dugradaton auf.

moton was also used for some numbor of test runs The test fored by cast stainless uteel components from the decommis-data have been evaluated and the results are presented in this sioned Shippingport reactor has been charactented. The results repo't are used to validate the correlatons and b6nchmark the labora-tory studies Cha'py-impact, tensile, and fracture toughness NUREG/CR 4893: TECHNICAL FINUNGS REPORT FOR GE.

data for matsnals from the hot. leg shutoff valve and cold-leg NERIC ISSUE 135 Steam Generator And Steam Line Overht!

check vanes at i pump volute are ;7esented The results inde.

Issues.

• SCIENTECH, Inc. May 1991.112pp. 9106040379 cate a modest degree of embnttlement.

SC:E 42 89. 57903 202.

NU%Q/CR 4757: LINE LOSS DETERMINATION FOR AIR SAM

• A detaned review of the tasks and available literature pertain-ing to Genonc lasue 135 (GI 135), steam Generator and Steerri PLER SYSTEMS. GLtSSMEYER.J A: SEHMEL,GA Battelle Line Overfill issues, has been conducted and is documented in Memonal Institute, Pacific Northwest Laboratory, February 1991.

this technical findings report The purpose of the review was to 10$pp. 9102280238. PNL 7597. 56B36.278-evaluate the current status of the issues and to determine lodine depositon can potentia!!y bias the results of radoio-whether sufftient informaton eusts for resolution, or whether dine air sampling systems. To deveop guidance and accept

• additonal work is required. Based on the revtew. It is concluded ante enteria for deterreinations of hne-loss correction factors-that all issues are i4ther resolved or are being pursother adds the data on laboratory sampler simulations, held tests on sam-tional work is required. Based on the review, It is concluded that piers and expentnentally treasured lodine deposition rates were all lasues are either resoved or are being pursued as part of reviewed Sampling system design features and operating corb othet activtties. In addition, a data secch and evaluaton were ditions at several power reactors are discussed. Measurements of iodine depositon rates on various air sampler construction conducted on the t*equency and effects of steam generator ovorfill events, Potential mitigating actions were considered it matenals were reviewed, and predicted air sampler performance based on the data was presented. Three examples of field tests was concluded that the public health and safety risks associat-of air sampier periormance for radiuiodine werv examined. A ed with these events are relatively minor and do nct justify adds-tonal mitigating actions or regulatons.

model of todine depossten and resuspension was extensively reviewed, and suggestions were made for incorporating variable NUREQ/CR 4911: INCENTIVE REGULATION OF NUCLEAR resuspension rates. Three pr6ncipal methods for determining re-POWER PLANTS BY STATE REGULATORS. MARTIN,R L:

doiodine line-loss factois were defined and compared; in-place BAKER.K.; OLSON,J. Battelle Human Affairs Research Centors.

field tests, laboratsy mock up with modelled extrapolations to february 1991,95pp. 9103040385. PNL 7596. 56869.001.

vanous release rate modes, and modelling based on laboratory The Nuclear Regulatory Commission (NRC) monttors 6ncen-data on semitar metenals Guidolines for appfytng these methods teve programs established by state regulators in order to obtain were given. Research was recommended to determine whether current mformation and to consider the potent al safety eHects the three methods were comparable to the lass-expensive of the incentive programs as applied to nuclear units. The cur.

method could be substituted for the preferred field tests, rent report is an update of NUr,EG/CH.5509, " Incentive Regu-NUREG/CFr4816 H01: PR-EDB. POWER REACTOR EMBRIT, lation of Nuclear Fower Plants by State Public Utility Commis-TLEMENT DATA BASE, VERSION 1.

Program Desenpton.

8'ons," published in December 1989. The information in this

)

STALLMANN,F.W.; KAM.F B K.; TAYLOR.B J. Oak Ridge Na.

mport was obtained from interviews conducted with each state tonal Labo'atory. July 1991. 37pp, 9108190281. ORNL/TM, regulator and each utility with a minimum entitlement of 10%

10328. 58827:148.

The agreements, orders, and settlements from which each in-Data concoming radiaton embrtttlement of pressure vessel centive program was implemented were reviewed as toquired.

Steels in commercial power reactors have been collected from The Interview and supporting documentation form the basis for available surveillance reports. The purpose of this NRC spon-the indriidual state reports descntang the structure and financial sored program is to provide the technical bases for voluntary impact of each incentwo program The orograms currently in consensus standards, regulatory guides, standard review plans, effect represent the adopton of an existing nuclear perform-and codes The data can also be used for the exploration and ance incentive program proposal and one new program in adde venfication of embrittlement prediction models. The data files tion, since 1989 a number of nuclear units have been included are given in dBASE Ill PLUS format and can be accccsed with in one existing program; while one program was discontinued any personal computer using the DOS operating system. Menu, and arother one concluded.

drivon software is provided for easy access to the data includ-Ing curve fitting and plotting facilities. This software has drasti-NUREQ/CR 4918 V0% CONTROL OF WATER INFILTRATION INTO NEAR SURFACE LL'N DISPOSAL UNITS. Progress cally reduced the time and effort for data processing and eval.

uation comparad to previous data bases. The current version of Report On Field Experiments At A Hemd Regon the Power Reactor Embnttlement Data Base (PR EDB) lists the Sete.Bettsville, Maryland. SCHULZ,R.K. Califomia, Univ c!,

test resuits of 117 bass) mar r als (plates and forgings), 85 6erkeley, CA. RIDKYAW, Maryland, Univ, of, College Park, welds, wi 86 heat affectedh materials that were irradiated MD. O'DONNELL,E. Waste Managemont Branch (Post 910830).

In 241 capsules of 82 resetors. Many capsules also contained October 1991, 23pp. 9111110278. 59575:330.

correlation matenals (standard reference matenals, SRMs) from The project objective is to assess means for controlling water the ASTM plate and two HSST plates (01 and 02). Matenal infi!tration through was's disposal unit covers in humid regions, from the Humboldt Bay reactor was used as an SRM for some Experimental work is being performed in large scale lysimeters General Enoctric reactors, The Electric Power Research institute (70'x45'10') at Beltsville, MD and resuits of the as%esMnent are (EPRI), roactor vendora, and utilities have provided back up applicable to disposal of LLW, uranium mill tailings, hazardous quality assurance checks of the PR-EDB' waste, and sanitary landfills. Three concepts are under investi--

gation: (1) resistrve layer barner, (2) conductive layer barrier, NUREG/CR-4867 RELAY TEST PROGRAM Sehes l Vibraton and bioengineering water management.1he resistive layer bar.

Tests. BANDYOPADHYAY; HOFMAYER.C.H.; SHTEYNGART,S.

rior consists of compacted earth (clay). The conductive layer Brookhaven Natonal Laboratory. January 1991. 164pp.

barrier is a special case of the capillary barrier and it requires a 9102250185. BNL NUREG.52277,56789-051, flow layer (e g., fine sandy loam) over a capillary break. As long Brookhaven National Laboratory has conducted a test pro-as unsaturated conditions are maintained water is conducted by gram on relays to determsne the influence of parameters related the flow layer to below the waste. This barrier la most efficient to design, eleCinCal conditions and vibratory motion on 1hoir re-at low flow rates and is thus best placed below a resistive layer

(

24 Main Citations and Abstracts barner. Such a combination of the resutrve la/er over the con.

traSground informaton and mput to the regulatory analysis ductive layer barrier promises to be highly effective provided repor1 for Gr23 there is no appreciable subsidence Boengin<ering water man.

agemont n a surface cover that is designed to accommodate NUREQ/CR 5282: ESilMATION OF CONTAINMENT PRESSURE subsidence it consists of impermeable pands which enhance LOADING DUE TO DIRECT CONTAINMENT HEATING FOR nm-off and terrut infdtration. Vegetation is planted 6n narrow THE DON PLANT. TUTU.N K. Brookhaven National Laboratory.

openings between panels to transpire water from below the PARK C K Korea Atomic Energy Research Institute.

panols. This system has successfully dewatered two tysimeters GRIMSHAW,C A.; et al. Margrove Consulting Ltd March 1991-thus demonstrating that this procedure could be used for reme-57pp.9103200234. DNL NUREG $2181. 571b9 239.

dial acton (" drying out") existing water logged d*posal sites at This report presents the results of a tones of calculations at low cost Brookhaven National Laboratory (BNL) to provide estimates of y

NUREQ/CH 5128; EVALUATION AND REFINEMENT Or LEAK.

the DCH containment pressure loading in the Zeon plant subject RATE ESTIMATION MODELS. PAUL D.D.;

AHM AD J.;

to a wide range of initial conditions and phenomenological as-SCOTT,P.M.; et al Battelle Memorial Institute, April 1991. DBpp.

sumptions. The containment loading calculatons were pot.

9104290259 BMI-2104. 57530:173.

formed using a vorsion of the CONTAIN code with update moda Lesk-rate estimation models are important elorrents in devet-fications, which parametrically charactortro DCH pheromena opng a leak-before-break rnethodology in piping integnty and (CONTAIN-DCH, Verson 1.1Cr The range of calculation param-safety analyses Existing thermal hydraulic and crack opening-eters was selected to reprewt tr any of the current uncertain-area modela used in current taakaste estimatons have been in' ties in DCH initial constions and uncertainties in modeling DCH corporated into a single computer code for leak rate estimaton-phenomena, The pararnsters vaned in the sensitivitj study 6n.

The code is called SOUIRT, which stands for Secoage QuantifF cluded. pomary system pressure at vessel failure core melt in-caton of Upsets in Reactor Tubes.1he FOUIR1 program has ventory, melt and steam flow tates through the reactor cavity, been validated by comparing its thermal hydraulic predictons with the hmeted experimental data that had been published on melt droplet aire, melt trapping rate, extent of hydrogen com-bustion, quenching of trapped debris, and w dispersal of water two-phase flow through slits brut cracks, and by companng its crack-opening area predictions Mth data from the Degraded from reactor cavity. The choice of CONTAIN calculation input Piping Program. In addition, leak 4 ate expenments were con-paramoters is discussed and results are presented for bNh a seven-cell and a si"9 e celi nodali7aton ot the lon contsiriment l

ducted to obtain vahdation data for a csrcumferential fatigue tveck in a carbon steel pipe girth weld.

building.

NUREG/CR 5139: DOSE REDUCTION TECHNIQUES FOR HIGH-NUREQ/CR 5285: CLOSEOUT OF IE DULLETIN 7913: CRACK-DOSE WORKER GROUPS IN NUCLEAR POWER PLANTS.

ING IN FEEDWATER SYSTEM PIPING. FOLEY,W J ;

KHAN,1 A; DAUMJW DIONNE,B A Grookhaven Natonal Lab-DEAN.R.S ; HENNICK,A. PARAMETER, Inc. March 1991,51pp oratory. March 1991. 82pp. 9103260083. BNL-NtlREG 52278 9103200106. PARAMETER IE176. 67152:148.

57152 011.

This report documents closcout of IE Butletin 79-13 regarding This report summarizes the main findings of a study of the ortent of radiaton dose received by special work groups in the cracks in the feed *S16r system piping of certain PWRs. Close-nuclear power industry. Work groups which chronically get large out la based on tmplementaten and venficaton of six required doses were investigated, using information provided by the in' actions by heensees and thrta required actions by designated dustry, The tasks that give high foses to these work groups apphcants for operating licenses (DAOLs). Evaluatons of hcens.

woro examined and techniques described that were found to be ce responses NRC/ Regional inspecton reports, and NRC particularly successful in reducing dose. Quantitattvu informaton memoranda in accordance with specific cntona indicates that on tne extent of radiation doses to various work groups shows the bulletin is closed for all of the 54 PWRs required to re-that significant numbers of workers in several Critical groups re-spond includng 13 DAOLs. It is concluded that (1) actions re-ceive doses greater than 1 and ovan 2 rem per year, particularty quked by the bullet;ti have besn taken by the affected facilittes, contract personnel and workers at BWR type plants. The and (2) the concerns expressed in the bulletin were validated in number of radiaton workorts whose lifetime dose is areater than that cracks were found and corrected at 18 of the 54 facihties, their age is much less. Although the techniques presored Background information (fi provided in the introducton and Ap-would go some way in reducing dose, it is likely that a st20atA pondx A.

redJcton to the high dose work groups may require develop-ment of new dose-reducten techaiques as well as mapr NUREG/CR 5288: CLOSEOUT OF IE BULLETIN 8006 ENGI-changes in procedures.

NEERED SAFETY FEATURE (ESF) RESET CONTROLS.

FOLEY.WJ: DEAN,R.S.; KLOEHN.BA; et al. PARAMETER, NUkEG/CR 5187: COST /DENEFIT ANALYSIS FOR GENERIC inc, February 1991, 33pp. 9102280242, PARAMETER IF.164.

ISSUE 23: REACTOR COOLANT PUMP SEAL FAILURE.

56836 246' NEVE.R G.: HEISELMANN.H.W. SCIENTECH inc April 1991

~

134pp.9104250014. SCIE-NRC-001-90. 57490.089.

Documentation is provided in this report for the closecut of IE The cost / benefit analysis for Genene issue (GI-23). " Reactor Bulletin 80-06 regarding the change of safety-related equipment Cootant Pump Seal Failure," is presented. The cost /benef t from the emergency or safety mode upon resot of the ESt-analysis compnSes three items: (1) treat the reactor coolant signal. Closeout is based on the implementaten and verificaton pump (RCP) seal assembly as an itom performing a safety-relat.

of four required actions. Evaluation of utihty responses and g

ed functon similar to other of the. reactor coolant pressure blRC/ Regen inspection reports, in accordanco with two enteria, boundary, applying quahty assur: ace requkements consistent indicates that the bulletin is closed for 61 (95%) of the 64 opor-with B of 10 CFR 50 and apphcable General Design Crtteaa of ating nuctsar power facihtaa to which it was issued for action.

Appendix A, (2) provide RCP manufacturer-recommended in-

' Follow-up items are proposed for the three facilities with opK strumentaten and instructons for monitoring RCP seal perform-status, Browns Ferry 1,3, and Mdistone t Facihtees whsr h were

' ance and detecting incipient RCP seal failures, and (3) provide shut down indefinitely or permanently at the time of issuWa of RCP seal cooling dunng oft normal conditionc involving loss of this report are not inc*uded in this review. Daekground 6: ma-all seal coohng such as station blackout. Cost /benesit analysis ton is presented in the introduction and Appendix A. The con-results are fuerthie for all items based on the estabhshed clusion is made thet the bulletin concerns have beea resol #

guidehne of $1000/ person tem. This report along Technical pending closeout of Browns Ferry 1,3. arvi Millstons 1.

Findings Document (NUREGICR 4948) are intended to provis

l t

Main Citations and Abstracts 25 NUREG/CR4300 V01: INTEGRATED RELIAD!LITY AND RiSV NUREO/CR-5331: MELCOR ANALYSES FOR ACCIDENT PRO.

ANALYSIS SYSTEM (IRRAS) VERSION 2 $ Reference Manual.

GRESSION ISE,UE S.

DINGM AN.S E.;

SHAF F ER.C J :

RUSSELL.K D.; MCKAY,M K.: SATTISON.M.D.; et at EG&G PAYNE AC ; et al. Sandia Notonal Latoratones January 1991.

Idaho. Inc. (subs. of EG&G. Inc ) March 1991. 43Bpp.

185pp 9102060102. SANDB9 0072. 56592.053.

9t04220309. EGG.26'l3 57448 346.

Results of calculations performed with MELCOR and HECTR The Integrated Rettability and Retk a *alysis System (IRRAS) in support of the NUREG 1150 stud < are presented in ths is a state of-the art, microcomputer-bas d probatubstic risk as.

report. The analyses examined a wide tange of issues The sessment (PRA) model development and analysis tool to ad-analyses included integral calculations covering an entire acci-dress key nuclear plant safety issues. IRRAS is an ir'tegrated dent sequence, as well as caleviatons that addressed specific

t. oft *nte tool that gives the usor the abihty to create and ana-issues that could stiect several accident sequences The results hre fault trees anri accident sequences using a microcomputer.

of the analyses for Grand Gulf, Peach Bottom, LaSalle, and Se-This program provides functions that range froM graphical fault quoyah are descrited, and the rnajor conclusions are summa-troe construction to cut set generaton and quantification Vor-rized sion 1.0 of the IRRAS program was released in February of 1987. Since that tirne, many user comments and enhancements NUREG/CR 5343: RADIONUCLIDE CHARACTER!2ATION OF have been incorporated into the program providing a much REACTOR DECOMMISSIONING WASTE AND SPENT FUEL more powerful and user.inendly system This version has been ASSEMBLY HARDWARE.P. ogress Report. ROBERTSON.D E.;

designated IRRAS 2 5 and is the bubject of this Reference THOM AS C.W.; WYNHOFF,N Ca et al. Dattelle Menional Insts Manual. Version 2 5 of IRRAS provides the same capabilities as tute, Pacific Northwest Laboratory. January 1991. 10$pp.

Verson 10 and adds a relational data base facility for manag.

91020$0011. PNL4806. 56575 314, 6ng the data, improved funcionality, and improved algorithm per.

This study is provict.ng the NRC and hcensees with a more formance.

comprehensive and defensible data base and regulatory as.

NUREG/CR 5304: RADIONUCLtDE BEHAVIOR IN THE ENVI.

RCNMENT, TVETEN U. Institutt for Energ:teknAh (Institute for co nmissioning and disposal of wastos generated dunng these Energy Technology).

• Sandia Netonal Laboratones. Septembe' activities Th; objectives of this study are being accomphshed 1991. 85pp 0201000126. SAND 904116. 60182.221.

dunng a two-phase samphng, savurement, and assessment

. Available data on ra60nuchda behaver are reviewed for qual-program involving ths actual becommissioning of Shippingport Station and the detailed analysis of neutron activated matenals Ity and consistency in the measurement of (1) initial ground con' centration in Norway of radionuclides from Chernobyl. and (2) from commercial reactors. Radiologica! charactertration studies subsequent concentrations of these radionuchdes in vanous on.

at Shippingport have shown that neutron activaton products, vironmental media as a functon of time The data were then dominated by (60)Co, make up the residual radonuchde inven-used to verify and indicate imprcvements in consequence tory. Fission products and transuranic radonuchdes are essen-models of radionuclide behavior in the MACCS code. The taally absent. Waste classification assessments have shown that models were of environmental processes such as trugrat on into all decommissoning matenals (encept reactor pressure vessel soII, Westhering, resuspenson, food chain contamination, and internals) could be disposed of as Class A waste. Measure.

loss or *econcentraton by runoff. In most areas of the MACCS ments and assessments of spent fuel assembly hardware have shown that (631Ni. (59)NI, and (94)Nb sometimes greatly code that were examined, the models and the data wNo in agreement. A few models were found to be faulty or inad-exceed the 10FR61 Class C hmit for some componentr, and equate.

thus would require disposal 6n a high level waste repository, These measuremer.,,, are providing the bas 4 for en at sessment NUREG/CR 5309: CLOSEOUT OF IE BULLETIN 83 07: APPAR.

of the disposal options for these types of highly radioactive ma-ENTLY FRAUDLLENT PRODUCTS SOLD BY RAY tenals. Compansons of predicted (calcula6d) actuajon product MILLER.lNC. FOLEY W.J.; DEAN R.S.; HENNICK.A. PARAME.

concentratons with the empirical data are provdng an assess.

TER. Inc. March 1991.43pp.9103260099. PAR AMET ER lE200.

ment of the accuracy of calculational methods

$7152 091 Documentation is provided in this report for the closeout of -

NUREG/CR-5345: FISSION PRODUCT FIELEASL AND FUEL BE.

Bulletin B3-07 regarding apparentty fraudulent products sold by HAVIOR OF IRRADIATED LIGHT WATER REACTOR FUEL Hay Miller, tr% to nuclear power and fuel facildies. The bulletin UNDER SEVERE ACCIDENT CONDITIONS. The ACRR ST 1 and two supplements were issued to all ho6ders of nuclear Expenment. ALLEN.M.D.; STOCKMAN.H.W.; REIL.K.0,; et al.

Power reactor or fuel facility operating heenses or construction Sandia Natonal Laboratories. November - 1991. 308pp.

permits. Four actions were required of all affected facilities to 9112310162. SAND 89-0308. 60159174, provide assurance that fraudulent items are not used in SOfety.

The Annular Core Research Reactor (ACP.R) Source Term related apphcations, unless quahtied by tests Review of utility (ST) Experiment program was designed to obtain time-resolved responses and NRC/ Reg on inspectiori reports shows that the data on the release of fission products from irradiated fuels bulletin is closed for all of the 118 power facihties and for the under well. controlled hght water reactor severe accident conO-two fuel facihties to which it was issued for act:on. Facihties tions. The ST 1 Expenment was the first of two experiments de-which were shut down or had constructon haited indefinitely or signed to investigate fission product release. ST 1 was conduct-penunently at the time of issuance of this report are not in, ed in a high'y reducing environment at a system pressure of ap-cluded it is concluded that all bulletin concerns have been re, proximately 0.19 MPa and at ranimum fuel temperatures of solved. Background informaton is supphed in the Introduction about 2490 K The data will be used for the development and and Appondix A, vakdation of mechanistic fisson product release computer codes such as VICTORIA.

NUREG/CR 5312: A THERMODYNAMIC MODEL OF FUEL DIS.

RUPTION IN ST 1. GRIMLEY,A.J. Sandia National Laboratories.

NUREG/CR 5352 R01: VAM2D + VARIABLY SATURATED ANAL.

Fetaruary 1991. 22pp,9103120079 SANDB8-3324. 56942:244.

YSIS MODEL IN TWO DIMENSIONS. Verson SS With Hystere-A thermodynamic model that quahtatively accounts for the ob, sis And Chain Decay Transport. Documentatice And User's served fuel disruption in the ST 1 test is presented. The model Guide. HUYAKORN.P.S.; KOOL.J.D.; WU,Y.S. HydroGeologic, is ba5M on Winslow a equaton for the oxygen pressure over Inc. October 1991. 297pp 9112310172. 60158.237.

hypostoichiometnc fuel and the reducing nature of the test at-This ' report documents a two-dimensional finite e!ument mosphere The stoichiometry of the fuel is calculated as a func-model, VAM2D, developed to simulate water flow and solute tion of temperature Tnis calculation predicts partial hquefaction transport in vanably saturated porous media. Both flow and of the irradiated fuel in the test, transport simulation can be handled concurrently or sequential-I

26 Maln Citations and Abstracts ly. The formutation of the governing equatons and the nume+

[4 cinc Power Research institu% and Babcock and Wilcon cal procedures used 6n the code are presented The flow equa-The unique features of the Babcock and Wilcon design, spectfs ton is approximated using the Galeskin finite element method.

cal!y the hot leg U-bends and steam generators. prevented the Nonhnear soil moisture characienstes und atmosphere bounda-use of existing integral 6ystem data of existing integral facihties ry conditions (e g, infiltration, evaporation and seepage face).

to adJress the thermal-hydrauhc SDLOCA questions. MIST was are treated uung Picard and Newton-Raphson itershons. Hyk specifica!!y dcsigned and constructed for this program, and an teresis sffects and ansotropy in the unsaturated hydrauhc nn*

existing facility-the Once Through Integral System (OTIS)-was ductivity can be tairen 6nto account if needed The contaminant a!so usec< Oata from MIST and OTIS are used to benchmark transport toimulation can account for advection, hydrodynamic the adequacy of system codes, such as RELAP5 and TRAC, for disportion, hnest equikbnum sorpton, and first order degrada" predicting abnormal plant transients. The MIST prog'am is re-ton Transport of a sinole component or a rnuttocomponent decay chain can be handled. The transport equation is approul-ported en 11 volumes Volumes 2 through 8 pertain to groups of mated using an upst eam weighted residual method Several Phase 3 tests by type, Volume 9 presents inter-group compan-test problems are presented to venfy the code and demonstrate sons; Vetume 10 provides compensons between the RELAP5/

its u%ty These problems range from simple one dimenssonal 1 MOD 2 calculations and MIST observations. and Volume 11 complex two-dimensional and axisymroetne problems.

(with addendum) presents the later Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire NUREQ/CR 537h REVIEW OF THE CHRONIC EXPOSURE MIST program Major topics include, Test Advisory Group (TAO)

PATHWAY MODELS IN MACCS AND SEVERAL OTHER issues, fr6cility scaling and design, test matrix, observatons, WELLANOWN PROBABILISTIC RISK ASSESSMENT companson of RELAP5 calculatons to MIST observations, and MODELS TVETEN,0. Institutt fo* Enorgiteknikk June 1930 MIST versus the TAG issues MIST generated consistent inte.

113pp,9101300222. $6534 000, The purpose of the mport is to document the results of the gral system data covenng a wide range of trent.ient interactions.

MIST provided insight into integral systairn behavior and assist-work performed by the author in conntw:tton with the following ed the code effort. The MIST observat'ons addressed each of task, perfurmed far U.S Nuclear Regalatory Commission, Office me TAG isms.

of Nuclear Regulatory Research, Division of Systems Research:

MACCS Chroruc Exposare Pathway Models Review the chron.

NUREG/CR 5423: THE PROBABILITY OF LINER FAILURE IN A se exposure pathway models implemented in the MELCOR Acct-MARK 1 CONTAINMENT.

T HEOFANOUS,T G.;

dont Consequence Code System (MACCS) and comparo those modds 1,. the chronic exposure pathway models implemented AMARASOOnlYA.W.; YAN.H; et al. Cahfornia, Univ. of, Santa in similar todos developed in countries that are members of BartJara, CA. AL9ust 1991, 561pp, 9110090250. 59327.140.

OECD. MACCS haa been compared to the following intomation.

An integrated analysis of Mark.1 kner attack in a postulated ally well-known the codes: ARANO (finland), CRAC/CRAC2 core melt accident is presented. The approach consists of the (USA), NECTAR (United Kingdom). NUCRAC (USA), UFOMOD mechanistic treatment of the sequence of a physical phenom.

(Federal Republic of Germany). A direct comparison has in ena that lead to liner contact by corium debns, and their cou-many respects proved to be difficult to perform, because of the pling through a probabilistic framework that allows representa-many bas!c difierences between the approaches chosen. But ton of uncertainties. We emphasize a physically consistent the repc t contains comprehensive descriptions of the vanous

tentment in each sequence, but atlow for qualitatively different approaches and default values of most of the important param-scenanos to represent the range of behavior due to model un-eters. It also contains numerous remarks / comments at points certainties The results are presented in a format that allows where the approach chosen (by MACCS or any of the other their direct use in PRAs, and, in particular, expert opinen is in-codes) may have weaknesses or faults; or where the descrip-corporated by a new methodological approach (first applied in tions/ manuals are incomplete, difficult to understand, or not our study of alpha mode failure-NUREG/CR 5030) that in-consistent with Information given in oter cocumentatio4 volves expert roview of, and comment on, a fully documented NUREQ/CR 5382

SCREENING OF GENERIC SAFETY ISSUES study all under one cover.

FOR LICENSE RENEWAL CONSIDERATIONS. FARAMARZI A

• HUGHES.A.A; SETH,S S. M'TRE Corp. December 1991, sipp)

NUREG/CR 5432 V01: RECOMMENDATIONS TO 1HE NRC 9112310175. MTR 90 WOO 467. 601E3156.

FOR SOIL COVER SYSTEMS OVER URANIUM MILL TAIL.

The U.S. Nuclear Regulatory Comml% on (NRC) is oevelop.

INGS AND LOW LEVEL AADIOACTIVE WASTES Identification ing regulations for renewing the operating hcenses of nuclear And Ranking Of Soils For Disposal Facihty Covers.

power plants to ensure that they operate safety beyond th, BENNETT.R D. Army, Dept. of. Army Engineer Waterways Ex-present license terms of 40 years. One consideraton relates to penment Staten. February 1991. 57pp, 9103200019, past resolutons of genenc safety issues (GSls) that did not 57066:174.

result in backfit requirements on the licensees. The consider.

The U.S. Army Engineur Waterways Expenment Station ation of an additonal operating term of 20 years which the pro-(WES) provides recommendations to the U.S. Nuclear Raguia-posed license ronewal rule allows. could have retrospective im-tory Commission (NRC) for the selection, placement, compac-phcation for the bases of those GSI resolut ons. As part of its tsun, testing and acceptance of soils proposed to be placed in technical support to the NRC for the Mvelopment of license re-cover systems over uranium mill tailings and low level radioac-newal regulatons, M!TRE has pedormed an indepe,idont review tive wastes, The recommendalons from WES are contained in of the G$ds to identify those that could be polentially affected three volumes of NUREG/CR 5432. Volume 1 identifies the var.

by hcense renewal cons:deratons This report desenbes the lous soil types and engineenng properties that are needed to screening provoss and the results of that work.

fulfill important soit cover functions. The identified soils are then NUREG/CR E3% V01: MULTILOOP INTEGRAL SYSTEM TEST ranked according to their capability to perform the low-permo-(MIST) FINAL REPORT. Summary. GLOUDEMANSJR. Babcock abihty and filter and drainage functons. Volume 2 provides rec-

& Wilcor Co. Apot %91.184pp. 9105220046, E PRI/ NP-6480, ommendations for conducting pertment laboratory and field 5782tl 165.

tests to ensure acceptable soil cover parformance. Volume 3 The Multiloop integral System Test (MIST) is part of a multi-covers recommendalons from WES on proper field construction phase program 4 tarted in 1983 to address srr.all-break loss of.

methods including guidance on quehty control testing and in-coolant accidents (SOLOCAs) speo3c to Dabcock and Wilcor spections. Recommendations are given for seahng penetratens designed plants. MIST is sponsored by the U S. Nuclear Regu-(e g-. Othervatton wells) that are required to penetrate covers latory Commission, the Babcock & Wilcox Owners Group, the for environmental monitoring of disposal facihty performance.

(

l

\\

Main Citations and Abstracts 27 NUREQ/CR 6432 YO2: RECOMMENDATIONS TO THE NRC The magnitude of the surface cha'go of thne amphotoric mate-FOR SOll COVER SyS* EMS OVLR URANIUM MILL TAIL.

r;als depends on the f atio of O(2)/AlmO(3), toil pH and cort-INGS AND LOW LEVEL RADIOACilVE WASTES Laboratory contration of electrolyte. Decreases in the SiO(2)/Al(2)O(3) rate And Fievi Tests For Soil Coverc. DENNETT R D. HO5LR C.

and soil pH tesult in an increase in soil AEC, Allophane and Army. Dept. of Army Ergneer Waterways Erpenment Station.

amogolite nch soils have an AEC ranging from 1 to 18 moa/

February 1991. 76pp. 9103200023 6706b 346-100g at pH about 6 Highly weathered soils domirmted by Fe Soo NURLG/CR.5432,V01 abstract and At oxides and kaohnste may develop a sigtvficant amount of NUREQ/CR 6432 V03: RECOMMENDATIONS TO THE NRC AEC as soll pH falls On a wide range of hose soils, AEC ranges frotti 0 to 2 meQ 100g at about pH 6 The totention of FOR Soll COVER SYSTEMS OVER URANIUM MILL TAIL,

/

INGS AND LOW LEVEL RADIOACTIVL WASTES ConstrucSon radenuclides, 6odine (I) and technetium (Tc), by soils is assoch Methods And Ouedance o, g,,1,ng Penetrations in Soil Covers ated with both soil organic mattet, and Fe and At oundes, where.

r GENNETT,R D.; KIMBRELLA F. Army, Dept, of, Army Engineer as sorpion on laye* sdicate minerats is neghgible. Fe and At Waterways Expenment Station. February 1991. 8100, oxides become more important in the retention of an6onic l, 9103200024 57066 06T.

40(3) and TcO(4). se pH falis, since more positive charge is do.

See NUREG/CR 5432,V01 abstract, veloped on the onde surfaces. Although few studies, if any, NUREO/CR 6440: CRITICAL ASSESSMENT OF SEISMiG AND have been conducted on I and Tc sorption by soll allophane GEOMECHANICS LITERATUNE RELATFD TO A HIGH LEVEL and imogolite, it is estimated that a surface plough soll (2 rnillon NUCLEAR WASTE UNDERGROUND REPOSITORY, pounds soit per acre) with 5 meq/100g AEC, as is commonly KANA.D D.; VANZANT.B Wa et al. Center for Nuclear Waste found in andisols, shall retain approximately 6900 kg I and 4500 Regulatory Analyses. DRADY,0.H G. Itasca Consulting Group, kg Tc, respectively, by the anion exchange rnechanism.11 is inc J 1991. 176pp. 9106250161. CNWRAB9-001.

conceivable that an anion enchanger such as an andisol could

- be used to modify the near feld environment of a radioactive -

A compichensive literature assessment hat beeri conducted waste disposal facility. This whole deposal system would then to determin@ the nature and scope of technical jnformabon ok simdar migration tesistance to ancoris as is normally afford-availab4 to charactente the seism 6c performance of an under.

eri to cations by usect and normal solls Future studies on this ground repository and associated faclirties. Significant deficien, subject are recommended cies were 6dentified in current practices for predicton of seismic res snsa of underground excavations in lointed rack Conven.

NUREG/CR 54th RISK BASED INSPECTION GUIDE FOR tional analytical methods, based on a continuum representation CRYSTAL RIVER UNIT 3 NUCLEAR POWER PLANT of the hosi rock mass may have limited applicability in a frac-SMITH 3 W.; DUKELOW,J S.; VO T V.; et al. Battelle Memona'l tured media Field observations and laboratory expenments indi-Institute, Pacific Northwest Laboratory. June 1991. N&p cate that in >nted rock, the behaver of the joints controls the 9107000262. PNL 7100. 68309.318.

overall performance of undeyround excavations. Further, under The Level 1 probabikstic risk assessment (PRA) fur Crystal repetitive seit,mic loading, sheat displacement develops pro.

River Unit 3 (CR 3) has boon anatyred to identity plant systems grossively at b:nck boundanes. Field observations correlating and components important to minimlang putlic nsk, as meas-seismicity and groundwater conditions have provided si0nificant ured by system :,tnbutions to plant core damage frequency, infortnation on hydrological response to seismic events. Howev.

and to 6dentity the pnmary failure modes of these components.

et, lack of a comprehensive model of geohydrological tosponse The report presents a sence of tables, organared by system and to seismicity has limited the transportability of conclusions from proritired by risk importance, which identify components assocl-field observations, ated with 90% of the inspectable risk due to plant operation.

"U NUREG/CR 54L8: ANALYSIS OF FLOW STRATIFICATION IN THE SURGE LINE OF THE COMANCHE PEAK REACTOR' are: L w Pressure injecton, AC Power, Service Water, Dominer.

a aW, @ Naswo Ingchon, M Nwm hgency SUNJG: SHEN,Y.H.; SHA.W.T. Argonne National Laboratory' Apnl 1991. SBpp. 9105160064 ANL-91/6. 57728:043 wow, Nam Mm Nssum Mo( and % h A number of nuciear power plants have toported failure of re-

mson, s ran% le basW on N Fusseheh wasum N na an e, e, adon d N Mal cm damage %

actor components due to flow stratification. Therefore, a funda-mental unoerstandina of, and a capability to predict, flow stratifi.

""U *# '"" I

'd

• U " "I # #

cation in a teactor s,st6m is entically important to reactor per.

NUREQ/CR 5481: DATA

SUMMARY

REPORT FOR FISSION formance and safety. The work presented here is the first step PRODUCT RELEASE 1EST VI 4.

OSBORNE,M F.;

In this directen and wl". contnbute to the resolution of the lasue of flow strauhcation. An analysis is performed using the LORENZAA.; COLLINS,JL; et al. Oak Ridge National Labora.

COMMIX 10 computer program for the surge line of the Coman-tory. January 1991, 72pp. 910 300072. ORNL/TM 11400.

56535.305 che Foan reactor, A companson 6s made between the calculat-ed results from the COMMIX code and the plant-measured Test Vlb, the fourth in a senes of high temperature ftssion data, Sr.d the agreement is good' product release tests try the wtical test rpparatus, was con-ducted in a flowing hyurogen-helium atmosphere. The test spec-NUREO/CR 5464: ANION RETENTION IN SOIL: POSSIBLE AP.

Imen was a 15 Fem-long section of a tual rod from the BR3 re.

PLICATION TO REDUCE MITGRATION OF BURIED TECHNE-actor in Delgium, which had been 6rradiated to a burnup of 47 TIUM AND LODINE.A Review. GU,0.; SCHULZAK. California, mwd /kg Using an induction fumace, it was heated under simu.

Univ, of, Berkeley, CA. October 1991. 42pp. 9111110288.

lated LWR accident conditons to a test temperature of 2400 K

$9576:272.

for 20 minuita Radinactivity meavements showed that the This report summarires a literature review of our present fuel collapsed after the 2ircoloy Mdir'g melted donng heatup.

tnowledge of the anion exchange properties of a number of The total release of fission products from the fuel was 85% for soils and minerals, which may potentia!Iy be used as anion ex-Kr.85,less than t% for Rw1013 9% for Sb 125,96% for both changers to retard migration of such anions as lodide (1-), lodate.

Cs 134 and 6137 and 13% for Eu-155 Most of the Eu was (10(3).) and penechnetate (TcO(4)-) away from the disposal site retalned in thn furr.M, but Wst of the cher elements were re-and thus prevent contamination of ground water, The amor.

leased to the cJicction system. Small fractions of other fission phous clays allophane and imogolite, dorived from volcanic products (Sr. Ts, and Ba), an well as fuel (U and Pu) were re-parent material, are found to be among the most important soil leased ako. Se total mass release from the 100 g fuel spec 6-componen3 Oapable of developing appreciable amounts of men was 0.40 g, witn 40% of this as vapor and 60% as aero-positive charge for anion exchange even at about neutral pH.

sol.

--w,_,

28 Main Citations and Abstracts NUREQ/CR 5455: CONCEPTUAll2ATION Of A HWOTHETICAL NUREG/CR-5522: A COMPARISON Or PARAMETLR ESilMA-HIGH4EVEL NUCLEAR WASTE REPOSITORY SITE IN TlOf4 AND SENSITIVITY ANALYSl$ TECHNIQUES AND THEIR UNSATURATED.F RACTURED TUF F.

PARSONS.A M ;

IMPACT ON THE UNCLRTAINTY IN GROUND WAT[ A FLOW OLAGUE,N E.: GALLEGOS D P. Sand'a National Laboratones MODE L PRE DICTIONS tiMMERMAN.D A,

Gram, Ine-January 1991.177pp. 9102110177. SAND 09 2965. 566513$0.

HANSON.R1 Intenor, Dept of. Geological Survey. DAVIS.P.A Under the bponsorshp of the U S Nuclear Regulatory Com.

Sanda Natonal loboratones. May 1991.19tpp 9107??O255.

miston (NRCL Sandia Nabonal Laboratories (SNL) is dev,ipp.

SAND 90 OtP8 56468175.

eng a penormance anriossmnnt rnethodology for the analysis of The Nuclear Rogutatory Comm>$sion (NAC) and the Environ-longterm deposal and isolation of fwgh# vel nuclear maste rnental Protection Agency (EPA) are the regulahng agencies for CiLW) in alternattve geologic rned>a As part of this exercise, high-level radioactrve *aste (HLW) rerositones. The regulations SNL created a corgsptuatiration of ground-water flow and rede P'omulgated by these agencWs stipuiste nomencal standards onuclarie transport in the far field O e, outade the disturbed for repository performance and esplicitly mandate the treatment zone) of a hypothoucal HLW repository site located in unsatu.

of uncertainty in the analyses performed h support of a reposi-tory license APPicabon. This work documents a companson of l

rated. fractured tuff formations This study provides a foundation for the development of conceptual rnathematical, and numeri-sens4Mty and uncertainly analysis tochtuques which are IActy tal rnodels to be used in this psrformance assessment rnethod-to be used in support of reposttory performance assessments to ology. This conceptualization is site specific h terms of geome-

[d dh ape er i n

try, the regenal ground-water flow systerra stratigraphy, and to a model of the Avre Valley equiter, Arizona Differences in structure in that the%e are based on informat on from Yucca the parameter estimates and estimabon erro's were compa'ed Mountain located on the Nevada lest Site. However, in terms and the effect that these differences have on the uncertainty in 01 processes in unsatutated and saturated, tractuied, porous the flow model predictions was ersminod Albo, the oficci that media, the model is ger enc. This report also provides a review different conceptual models can have on the output uncertainty and eva'uabon of previously proposed conceptual models of un-was examined Uncorialnty propagation was performed via saturated and saturated flow and solute transport. This report Monte Carlo t,imulabon and the importance of screening the provides a qualitatrve desertotion of a hypothetical HLW reposL t,ensmissivity real. rations for fealism was svaluated Two ap-tory site in fractured tu f. Howewr, evaluation of the current proaches to sensitivity analyses were used, statisticat and deter-r knowledge of flow and t/ansport at Yucca Mountain does not minishe; these were applied to evaluate the sensitivity of the yield a single conceptual model Instead, multiple conceptual groundwater travel time to changes in transmissMty. The effect models are poss'ble given the edshng informatiott of different boundary conatons on the calculated sentutMty de-rivativen was also evaluated. Parameter estimaten and estima-HUREG/CR 5518; OUALITY ASSURANCE PROCEDURES FOR tion errors were obtained via geostatistaal and inverse tech.

THE CONTAIN SEVEHE REACTOR ACCIDENT COMPUTER niques The patterns in these f, elds were generatty sumilar, dis-CODE, RUSSELL,N.Aa WASHINGTON.K Ea EERGEHONKDa crepancies were explained. It is shown that the best kriged estL et al. Sandia Nabonal Laboratones. January 1991. 147pp.

mate for use in a flow modelle not necessarily the one with the 91020$0015 SAND 90-0011 66576 0$9.

lowest kriging errors. Also paradox 6cally, the output uncertainty The CONT AIN quality assurance program follows a stnet set is greater when the input parameters are correlated versus of procedures designed to ensure the integnty of the code to when they are uncorrelated The " throughput" of the knging avoid errors in the code, and to prolong the life of the code techniques suggests that the mean estimates denved from The code itsett is maintained under a cod + configuration control these techniques are fremontly "off the mark" or inconsistent system that provides an histoncal record of changes. All with the conceptual model. With no acreening of the input pa-changes are incorporated using an update processor that allows remeter estimates for realism, non-conservative travel hme este separate identification of improvements made to each succes, mates were obtained The dHerential analysis sensitMty tech-sive code version Code modifications and improvements are naque is shown to be dependent on the choice of design point formally reviewed and checked. An othcJstive, muittlevet test provid6ng only a local measure of the sensitMiy. The statishCal program validates the theory and implementation of att code approach to sensnivity identifies parameters which are both changes through assessment calculations that oompare the sensitive and uncertain, le., it shows when the uncertainty in a t' ode prerkted results to standard handbooks or idealized test model parameter la important. SenratMty estimates are also cases A document trail and archive establish the problems shown to be dopondent on the choice of boundary Conditions-solved by the software, the venfication and validation of the usd software, software changes and subsequent reverification and NUREG/CR 5525: HYDROGEN. AIR DILVENT DETONATION revalsdation, and the tracking of software problems and actons STUDY FOR NUCLEAR REACTOR SAFETY ANAWSES.

taken to tesolve those problems. This document describes in STAMPS,0.Wa BENEDICK,W.B.I TIESZEN.SR Sande National detail the CONTAIN quality assurance procedures Emboratones. Jans ary 1991, 97pp. 9101300088. SANL>d9 2398.

NUREQ/CR 5520: PROCEDURES GUIDE FOR EXTRACTING AND LC/4 DING PROBABIllSTIC RISK ASSESSMENT DATA ne detonability of hydiogen air diluent mixtures was investh INTO MAR-D USING (RRAS 2,5. FOW,LER,R D4 JUDD.DL; gated expenmentally in the 043 m diameter,13.1 m long PHAM.Ma et al EG&G Idaho, Inc. (suba of EGAG. Inc) No-Heated Detonation Tube (HDT) for the ettects of vanations in vember 1991.110pp. 9112310179. EGG 2630. 60158 046.

hydrogen and dituant concentrabon, instat pressure, and initial temperature The os a were correlated using a ZND chemical The Models and Results Data Base (MAR-D) can be used to kinetics model. The detonation tmits in the HDT w9re obtained organize informabon from probabilistic risk assessments. Data experimentatty for lean and rich hydrogen-air mixtures and stoi-rnay be entered into MAR D electronically or manually This chometric hydrogen.nif-steam mixtures. The additon of a dilu-report concentrates c1 manual data entry methods and docu '

ent, sisch as steam or carbon dioxide, increases the detonation ments the use of the integrated Reliabill'y and Risk Analysis cell width for all mixtures in general an In' Jesse in the inibal System (IRRAS), Verwon 2 5, and ASCll text editors to road pressure or temperature produces a decrease h the cell width.

level 1 On1ernal event) PRA moJels into MAR-D. Step by step in the HDT, the detonable rance of hydrogen in a hydrogen-air instruchons for using IRRAS 2.5 are provided, which will help mixture inibally at 1 atm pressure is between 11.6% and 74 9%

the user transfer data from a pnnted (hardcopy) source to MAR.

for mixturen bl 20 degrees C, and 9 4% and 76 9% for mistures D.

at 100 deg'ees C. The detonation limit is between 38.8% and 2-.2..m

I

(

kaln Citations and Abstracts 29 40 t,% steam for a stoittuometric hydrogen-ait sicam routn user s' gudo. reference manuals, programmers' gudes, and as-initially at 100 degrees C and 1 atm. The detonsbon limit is be.

sessment and apphcation reports, is available in draft form and l*een ?9 0% and 319% steam for a stoichometnc hydrogeru is distributed to VELCOR users.

air-steam misture with a final predetonabon rmuture temperature and pressure of approximately 100 degrees C and 2 6 atm.

NUREG/CR 1436: DCM)U. A DUAL. CONTINUUM. THREE DI.

MENSIONAL., GROUND. WATER TLOW CODE FOR UNSA104 NUREG/CR 6676: ANALYSIS Of" RISK REDUCTION MEASURES RATED, FRACTURED, POROUS MEDIA UPDEGRAF F,0 D, APPLIED TO SHARED ESSENTIAL SERVICE WATER SYS-oram, Inc. LEE.C E Applied Physics, Inc. GALLEGOS.D.P.

TEMS AT MUlil VNil SIT E S.

KOHUT.P.; MUSICK!,2 i Sandia National Laboratories February 1991. 16100 TITZpATf0CK.R Brookhaven National Laboratory. June 1990 9103120076, SAND 90 7016. 66948 001.

171pp.9107010104. DNL NUREG.62225. t,8250 246 This tcport constitutes the user'$ manual for DCM3D. DCM3D This report summantes a study periottned by Brookhaven is a computer code for solang three. dimensional, ground-water National Laboratnry for the U S. Nuclear Regulatory Comm+

flow problems in vanably saturated fractured porous media The son in support of the resolution of NRC Genene issue 130. Gl*

code 6s based on a dualcontinuum model with porous media 130 is concemed with the potential core damage vulnerability composing one continuum and fractures compnsing the other.

resulting from failure of the emefDency service watet (E SW)

The continua are connected by a transfer term that depends on system in selected multiplant units. These multiplant units are

. tr e unnaturated permeability of the porous medium, An integrat4 all twin pressunrod water reactor designs that have only two ed finite difference scheme is used to discretae the govoming ESW pumps por unn (one per train) backed up by a unit to unit equatio is in

• pace The time dependent term is allowed to crotStie capabihty. 'This Genene issue apphes to seven U S-remain continuous. The resulting set of ordinary ddlerential anos (14 plants) The study established and anaYled the core equations (ODE's) is solved with a general ODE solver, damage vulnetsibly and dentrfied potential improvements for LSODES The code is capable of handhng transient, spatially the ESW tystem it obtained genene estimates of the nok re-dependent source terms and boundary condilsons. The bounda-duction potenbal and cost effectsveness of each potential im' ry condibons can be either prescribed head or presenbad flut provemeat. The analysis aiso 6nvesbgated the cost / benefit as-pects of selected combinations of potential tmprovements NUREG/CR 663h APPROACHES FOR THE VAllDATION Or NUREG/CR.6629: AN ASSESSMENT OF DWR MARK lit CON, MODELS USED FOR PERFORMANCE ASSESSMENT OF TAINMENT CHALLENGES, F/,tLURE MODES. AND POTEN.

HIGH-LEVEL NUCLEAR WASTE REPOSITORIES DAVIS,P.A.:

TIAL IMPROVEMENTS IN PERF ORMANCE, SCHROEDER.J A ;

OLAGUE,N E. Sanda National Laboratories GOODRICH.M T.

PAFFORD.DJ; KELLY,0L; et al EG&G Idaho, Inc. (subs of O'am, Inc. March 1991, 34pp 91042J0336 SAND 900575.

EA, ne.) January 199f, 307pp 9102060148 EGG.2594.

67447:24 This report descriles r$f significant challenges posad to ar.d concepts that can be applied in valdation of models used Mark 10 containmem systems by severe accdents as i$,ntihed in performan assessment of high4 vel waste (HLW) repositor-for Grand Gulf. Design simitanhos and differences between the ees The approaches are based on a valdation strategy that Mark lli plants that are important to containment periormance Sand a National Laboratories (SNL) has implemented as partici-are summanrod. The accident sequences temponsible for ths pants in the International Transport Valdation Study (INTRA.

challenges and the postulated containment failure modes asso, VAL). This strategy focuses on the demonstration that perform-ciated with each challenge are identified and desenbed. Im-ance assessment models are adequate representations of the-provements are discussed that have the potential either to pro, real systems they are intended to repre;ent, given the portinent vent os delay containment failure, of to mitigate the offsite con-mgdatory requirements rather than proving tbsolute correct-Sequences of a fission product release. N each of these po, nose from the purely scientific point of view. Positions that are tent al improvements, a qualitateve analysis is provided. A hmrted taken consist of the following- (t) due to the relevant time and quantitative nsk analysis is provded for selected potential im, space scales, models that are used to assess the performance provements of a HLW repository can never be valdated, therefore, (2) vali-dation is a procees that consists of building contdence in those NUREG/CR 6631: MELCOR 1.8 0: A ITER CODE FOR models and not providing " validated" models; 6n this..oniert.

NUCLEAR REACTOR SEVERE AC i SOURCE TERM (3) model valdahon includes compansons to " reality," however, AND AlSK ASSESSMENT ANAL, SUMMERS,R M ;

adequacy for the given purpose (assessing compliance with tog-COLE.R K.: BOUCHERONI.A.: et al % d National Laborato'.

ulations) is the overall goal, (4) compansons to " reality" consist net. January 1991, 177pp. 9101300080, SAND 90 03f 4 of companng model predictions against laboratory and f eld ex-5653k128 periments, natural analogues, and site-specahe information; (6)

MELCOR is a fdy integrated, engineenng, level cor,puter when comparing expermental data to modet predictions, a code that models io progression of severe accdents in light model en be either "6nvalid" or "not invald," based oh the null water reactor nuclear power plants. MELCOR is being devel-hypothesis concept, however, confdence in the model arises in opad at Sandia Nahnal Laboratones for the U.S. Nuclear Ret hnding a modet to be "not invaled" over a wide range of condo ulatory Commission as a second-goneration plant risk assess-tions; (6) an attempt should be made to consider in the va!ida-ment tool and the successor to the Source Term Code Pack-tion process all plausiblo conceptual models; and (7) when age The enhre spectrum of severe acedent phenomena, in-comparing expenmental data to rNdol predictions, a logical sys-cluding reactor coolant system and containment thermal-hydrau-10matic approach should be followed (ie, modet input tested bc response, core heatup, deg"adation and retocation, and fis-separately from model structure). This report dibcusses (1) the sion product release and transport, is treated in MELCOR 6n a defirm on of vahdation in the context of performance assels-unahed framework W both bolling water reactcts and pressur, ment for HLW repositones, Q) the need for valdat on, (3) en tred water reactors. MELCOR has been especially designed to approach to validation, and (8) an approach to companng facilitate sensitwity and uncertainty analyses. Its curr6nt uses in-model predictions with expenmental data proposed by the au-clude estimation of severe accdent source terms and their sen-thors.

.sittvites and uncertainties in a variety of applications This report is a summary of MELCOh 1.0.0, the code version re-NURENCR-6538 V01t INFLUENCE OF ORGANIZATIONAL FAC-leased in March 1989. Condensed information is presented on TORS ON PERFORMANCE RELIABILITY. Overview Ard De-its developmental history, structure, modehng features and ca-talled Methodological Development. HABER,S B.; O'BRIEN,J.N.;

pabilibes, verihcation and vahdation, and quahty assurance De-METLAY,0 S.; et al. Drookhaven National Laboratory. Decem-tailed documentahon on these aspects of MELCOR,6ncluding ber 1991,13Bpp 9201080112. BNL NUREG 5 2301,60232:137.

30 Main Citations and Abstracts This is the first volume of a two volume report Volums 11 will 6nddabon of an increased vulnerabilitr' to thormal damage due be pubished at a tatM date this report presents the results of to aging However, for the higher temperature exposures, no a research project conducted by Brookhaven National Laborsto-statistical differer.ce betweers the damage times for aged and ry for the United Stated Nuclear Reguatory Commisscn. Office unaged cable samples was noted For both cable types, the of Nuclear Regulatory Research. The purpose of the project changes in the thermal damage threshold served wete not con =

was to develop a general methodology to be used in the as-sidered 669nificant in terms of fira nsk setsment of the orgartrational factors which aff 6ct performance reliability Safety) m a nuclear power plant The research de.

NUREG/CR 65$0: PASSIVE NONDESTRUCilVE ASSAY OF NU-scribed in this report includes the development of the Nuclear CLEAR MATERIALS REILLY,D; ENSSLIN,N: SMITH.Ha et al.

Organgation and Management Analysis Concept (NOMAC)

Los Alamos National Laboratory. March 1991. 709pp This concept charactenzen the organizat,onal factors that 9108210188 LA UR 90 732. 58858 017, impact safety performance in 6 nuclear power plant and kienti.

This book is a general reference on the thoorv and applica-fies some inethods for systematically measunng and anatyring tion of passive nondestructive assey (NOA) techn64ues, or the influence of these factors on safety performance. This PANDA It is part of a four volume set on nuclear matenal report is divided into two parts. Part i presents an overview of measurement and accountabihty sponsored by the US Nuclear the deveinpment of the methodology, while Part ll povides Regulatory Commission (NRC) Although we discuss a few more details and a technical analysis of the methodological de.

active NDA techniques, they have been treated in detail in an-velopment Specifically, the results of two demonstration stud-othe' book in the NRC senes authored by T. Gozani. The son, the feasibility of the methodology, and a specific applicat on book's intended audience ranges from NDA neophytes to expe-for which the methodology ns developed are presented, rienced practitioners. While the major motivaten to write this NUREG/CR 6539: A SELF TEACHING CURRICULUM FOR THE book was provided by the NRC, there has long been a desire at NRC/SNL LOW. LEVEL WASTE PERFORMANUE ASSESS

• Los Alamos to prepare a text of this kind. Many of the tech-niques and 6nstruments desenbod herein were developed at Los MENT METHODOLOGY.

CHU,M S Y; KOZAK.M W.;

CAMPBELL J E ; et al Sandia National Laboratones January Alamos, and we welcome the opportunity to desenbe the tech.

1991.195pp. 9102190208. SAND 90-0585. 56754.178 niques more completely than is possible in reports or papers.

A performance assessment methodology han been developed NUREG/CR 56511 TWO NEW NDT TECHN:OUES FOR INSPEC-tur use by the U.S Nuclear Regulatory Commission in evaluat-llON OF CONTAINMENT WELDS DENEATH COATINGS. Final ing license applications for lowevel waste disposal facilites Report. October 1D89 March 1990. FITZPATRICK.G.;

This repo't provides detailed guidance on input and output pro-THOME,D.K. Physical Research, Inc. Junu 1991, ?6pp.

cedures for the computer codes recommended for une in the 9107220301. 5B489.054.

methodology. Seven sample problems are provided for vanous Tv o new nondestructive testing methods were evaluated int aspects of a performance assessment analysis of a simple hy-inspecton of containment welds beneath coatings, locluding pothetical conceptual model. When combined, these samplo magneto. optic imaging and Hall effect measurements. Tradition-problems demonstrate how the methodology is used to produce al inspecton (nethods, including magnetic particle inspection, a dose history for the stte under normal cond$ons, and to dom-are unsatisfactory in the nuclear containment environment be-onstrate an analysis of an intruder scenano.

cause paint or other coatings inust be removed to provide telu NUREG/CR 5543: A SYSTEMATIC PROCESS FOR DEVELOP.

able results. This creates radioactive wasta, potential airborne ING AND ASSESSING ACCIDENT MANAGEMENT PLANSc contaminaton, and piolonged radetion exposure to inspection HANSON.D J ; DLACKMAN.H S ; MEYER.O R.; et al. EG&G P0'sonnel, The new methods offer great improvement because Idaho, Inc. (subs of EG&G, ine ).

Apnl 1991, 94pp.

of increased sensitivity and rapid scanning capability. Resulta 910429025'l EGGE95. 57530 271.

obtained dunng Phase i demonstrated that magneto optic imag-This document describes a four step approach for developing ing methods offered good detectinn of cracking in weldod entena recommended for use in assessing the adequacy of ac.

carbon steel samples, Sven through paint. Direct, real-tsme cident management plans Two steps of the approach have images were obtained with this tcchnique in a video format ideal been completed and provide a prototype process that could be for complete documentation of the full inspection. A new used to develop an accident management pian. Based on this method for rapidN Inducing the required magnetic fselds for in-process, a preliminary set of assessment criteria are derived.

spection was also detnonstrated and offers the potential for These preliminary entena will be refined and improved when the eliminating bulky, high current power supplies or magnetic remaining steps of the approach are completed, that is, attor yokes. Results obtained with the Hall effect were not as promis-the prototype process is validated through application.

ing as they were on aluminum due to electncat interference NUREG/CR 5546: AN INVESTIGATION OF THE EFFECTS OF problems and vanable blasing caused by residual magnetic THERMAL AGING ON THE FIRE DAMAGEABILITY OF ELEC-fields in the parts. The technique may still be useful for inspect-TRIC CAB'.ES. NOWLEN.S P. Sanoia National Laboratones.

Ing hght spaces not accessible with magneto-optic 6maging de-May 1991. 96pp. 9106120194. SAND 90 0696. 58062.037.

vices, but wdl require significant development.

This report documents the findings of an expanmentalinvesti-NUREQ/CR 5555: AGING ASSESSMENT OF THE WESTING.

gabon of the effects of thermal aging on the hre damageability HOUSE PWR CONTROL ROD DRIVE SYSTEM, GUNTHER.W.;

of electnc cables. Two popular types of nuclear qualified cables SULLIVAN.K. Brookhaven National Laboratory. March 1991.

were evaluated For each cable type, both unaged (ie., new off 104pp.9104080294. BNL NUREG-52232. 57294.246.

the teet) and thermaHy aged samples were exposed to steady.

A study of the effects of aging on the Westinghouse Control state clavated temperature environments until conductor to con-Rod Drive (CRD) System was performed as part of the Nuclear ductor elettncal shorting was observed. Plots of the time to Plant Aging Resepech (NPAR) Program. The objectives of the electrical falture versus the exposure temperature were devel.

NPAR Program are to provide a technical basis for identifying oped thermal damage threbholds were tietermined. For one and evaluating the degradation caused uy age in nuclear power cable type, the thermally aged cables were less vulr.erable to plant systems, structures, and components. The information thermal damage than were the unaged samples as demonstrat-from this and other NPAR studies will be used to assess the ed by an increase in the thermal damage threshold for the aged 6mpact of aging on plant safety and to develop effective mitigat-samples, and an extended survival time at exposure tempera-ing actions. The operating exponence data were evaluated to tures above the damage threshold for aged samples compared identify predominant failure modes causes, and effects. For this to undgad samples. For the second cable, the threshold of ther-study, the CRD system boundary includes the power and logic mal damage was lowered somewhat by the agmg process, an cabinets associated with the manual control of rod movement.

Main Citations and Abstracts 31 and the control rod mechanom itself The aging related dog <a.

drywell flooding via containment spray operatiort and debris dation of the interconnecting cables and connectors and the quenching in Mark ll suppression pools is assessed.

tod position 6ndicahng system also were considered The eval' untion of the data. when coupled with an enessment of the NUREG/CR 66f t: THE RESPONSE OF BWR MARY lli CON-matenals of construction and the operating environment, leads TO SHORT TERM STAllON BLACKOUT to the conclusion that the Westinghouse CRD system is subject SEVERE ACCIDENT SEQUENCES GREENE,S R -

to degradation from aging. which could affect its intended sately HODGE S A.; HYMAN C R4 et al. Oak Ridge Natonal Laborat$$

functon as a plant ages. The number of CRD system failures ry' June 1991, 332pp-9107230200. URNL/1M-11549 whch have resulted in a reactor inp (challenge to the safety N

stem) warrants a higher level of regulatory and industry atten-This repcet descobes the resulte of a teries of calculations g

g, ments to short. term station blackout severe accident. so-NUREG/CR 6666: GENERIC ISSUE 87: FLEXIBLE WEDGE quences. The BWR.LT AS, BWASAR and MELCOR codes were GATE VALVE TEST PROGRAM Phase il Results And Analysis-cmployed to conduct quantitativa accident sequent-e progres.

STELLE,R., DEWALLK G.; WATKINS,J.C. EG&G Idaho, Inc, sion and containment response analyses for several statinn (subs of EG&G. Inc) January 1991,83pp. 9102110169 EGG-blackout scenarios.1he acc6 dent mitigaton effectiveness of 2600. % 653 222.

containment venting and backup emergency power for r:ontain-Quahtication and flow holatoa tests warre conducted to ana-ment hydrogen ignitors and drywell vacuum breake.s is as.

lyre the ability of selected bolling water reactor procest valves sessed.

to perform tticir containment isolation functions at high energy pipe break conditions and other more nortnal flow conditions.

NUREG/CR 667h EXTENSION AO EXTRAPOLATION OF J R Numerous parameters were measured to assess vatve and CURVES AND THEIR APPLICATION TO THE LOW UPPER motor. operator performance at various valve loadings and to SHELF TOUGHNESS ISSUE. JOYCE JA U.S, Naval Academy, assess industry practices for predicting valve and rnotor opera.

Annapolis, MD. HACKETT.E M David W. Taylor Neval Re-tot requirements. The valves tested were representattve of search & Development Center March 1991, 102pp-those used in reactor water cleanup systems in boiling water re.

9104020091,67222.193.

actors and those used in bothng water reactor high-pressure This d^cument develops methods of measunng expelmental-coolant injection (HPCl) steam lines. These tests w611 provide ly the limits of valid fracture mechanico data that can be ob-further information for the U.S Nuclear Regulatory Commission lainod from small fracture mechanics specimens The proused Genonc lasue 87 " Failure of the HPCI Steam Line Without 150 technique generally shows that present ASTM emits are overty lation" and Generic Letter 89-10 " Safety.Related Motor Oper, conservative and the new technique would tillow almost a ated Valve Testing and Surveillance."

three-fold increase in the amount of crack extention alioned in the testing of a surveillance specimen. Analytic re:ationahips are NUREQ/CR 6661: ANALYSIS OF BELLOWS EXPANSION JOINTS IN THE SEQUOYAH CONTAINMENT. GREIMANN.L.;

then developed to ellow use of the new expenmontally meas.

WASSEF W.; FANOUS,F4 et al. Iowa State Univ., Ames, lA De-ured limit to J controlled crack growth for design or feiture anal.

cember 1991,9Bpp. 9201000203. SAND 90 7020. 60244.187.

ysis applications to correlate best with the omega criterton which defines limits on both the manmum J level and the maxi.

Bellows expansion loints are an integral part of the contain-mum crack extension anowable for a partcutar speciman stre ment building pressure boundary in some nuclear power plants-and matorial twghness combinatiort The final section looks at They are used at piping penetrations to minimize the loadings the problem of extrapolaton of J R curve data when nesdod for on the containment shell due to dif'erential movement between the shell and piping. The purpose of this study was to investi.

a stncture fracture analysis. Several forms of extrapolaton rela-gate bellows behavior in the unlikely event of a severe accident tionships are compared from the point of view of accurate and conservative extrapolaton, partevlarly from the standpoir" of inside the containment building. The etudy began with a survey of available informaton on bellows design, analysis, and past tearing instabihty analysis of a growing ductile crack on the rna-test programs. This information was then used to assess the ul-terial upper shelf.

timate behavior of the bellows in the Sequoyah containment. tt NUREQ/CR 5581: UNSATURATED FLOW AND TRANSPORT was determined that the bellows at penetraton X 47 in the Se.

THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL quoyah containment would exponence the worst loading conde.

WASTE REPOSITORIES. Final Report 4 Phase lit. EVANS.D.D; tons donng a severe accident. Finite element calculatons of RASMUSSEN T.C. Arizona, Univ. of, Tucson, AZ, January 1991, bellows X 47 were conducted to examine the deformation and 79pp. 91020$0020. 56576.206 resutting strains caused by the combination of axlal compres, Research results are summarized for a U.S. Nuclear Reguia-tson, lateral offset, bending, and intwnal pressure that would be tory Commission contract with the University of Aniona focusing.

apphed to the bellows dunng a severe accident. Because of on field and laboratory methods for characterizing unsaturated convergence problems, the analyses could not be continued to fluid flow and solute transport related to high-level radioactive a point of obvious bellows failure. However, large inelastre waste repositories. Characterizatort activities are presenteo for bend:ng strains, up to 6%, were calculated. A test program to the Apache Leap Tuff field site. The field site is located in un-determine the ultimate bellows behavior and develop data for saturated, fractured tuff in centraf Arizona. Hydraulic, pneumatic, validaten of ana;ytical methods is recommended.

and thermal characteristics of the tuff are summarized, along NUREG/CR 5565: THE RESPONSE OF BWR MARK ll CONTAIN-with methodologies employed to monitor and sample hydrologe MENTS TO STATION BLACKOUT SEVERE ACCIDENT SE.

and geochemical processes at the field site. Thermohydrologic OUENCES. GREENE,S R; HODGE S.A.; itYMAN.C R4 et at eenmen s am re p

aba% W W Oak Ridge National Laboratory. May 1991.313pp.9106210012 ORNL/TM-11548. 58167116 and transprwt in unsaturated, fractured rock.

This report describes the results of a series of calculations NUREG/CG 5545: THE HIGH LEVEL VlBRATION TEST conducted to investigate the response of BWR Mark 11 contain-PROGRAM Final Report PARK,Y,J.;

CURRER1,J,R.;

ments to short. term and long. term station blackout severs acci-HOFMWE.R.C.H. Brookhaven National Laboratory. May 1991.

dent sequences. The BWR LTAS, BWRSAR, and MELCOR 488pp.9107030236. BNL NUREG 52240. 58295:349.

codes were employed to conduct ouantitattve acc6dont se-'

As part of a cooperative study between the United States and quence progression and containrnent response analyses for Japan, the U.S Nuclear Regulatory Commission (USNRC) and several station blackout scenar6os. The accident mitigation ei-the Ministry of Intarnational Trade and Industry (MITI) of Japan lectiveness of automate depressurizaton system actuahon,-

agreed to perform a test program that would subject to a large

32 Main Citations and Abstracts scale piping model to significant ptntic sterns under excitaten of the Depriment of Energ(s appbcaton to construct a 900-conditions gientor than the design conditon for nuclear power logic repository for disposal of highlevel radioactive waste. This plants The objectrve was to compare the results of the tests report cummart2es the results of esposure studies periormed on with state of. the-art ana'yses Compansons were done at differ-two copper base and f*o Fe Or N! alloys in simulated Tuff Re-ent excitation levels from elastic to elastic plast.c to levels pository conditions Testing was porformed at 90 C in three en-where crachry was induced h the test model. The vibration vironments; simulated J 13 well water, and two environments tests and 6 at-test examination were comed out in Japan by that simulated the chemical effects resulting from boihng and in the Nuclear Power Engineenng Test Center (NUPEC) Input radiation of the groundwater. Greviced specimens and U-bends motion development and pre and post test knal sis were car-were exposed to hquid, to vapor above the condensed phase, y

tied out in the United States at the E;ookhaven National Labo-and to attornate immersion. A rod specimen was used to mons-retory (BNL) and the Electne Powe' Research institute (EPRI).

tot corrosion at the vapor-tqud interface The specimens were This report descr:1,en the results of the cooperative studies per-evaluated by electrochem6 cal, gravimetnc, and metallopraphic formed both in Japan and the United States techniques following approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of exposure. Re-NUREG/CR 6592: ANALYTICAL STUDIES OF TRANSVERSE sWs of the exposure tests indicated that all four alloys exhibited STRAIN EFFECTS ON f RACTURE TOUGHNESS FOR CIA.

acceptable general corrosion rates in simulated J 13 well watw.

These rates decreased with time Incipient pitting was observed CUMFERENTIALLY ORIENTED CRACKS SHUM.D.K M.;

MERklE.J G ; KEENEtWALKER. et al. Oak Ridge Natronal under deposits on Alicy 82$ and pitting wns obs,erved on both Alioy CDA 102 and Alloy CDA 715 in ths simulated J 13 well Laboratory. Apr61 1991.151pp 9105160051. ORNL/TM 11bB1.

watw. No stress emose cramng M was @sorved in U.

$7729 023 bend specimens of any of the alloys in simulated J 13 well The objective of this report is to desenbe the development of nQ CWos' n raks of the copper base alloys ln an w

e analysin methods for estimating the decresse in crack initiation acW&conoton envuonmem were moderate, and no SCC was toughnsst, from a reference plane strain value, oue to posittve straining along the crack front of a circumferential flow in a re-observed. However, severe patting and crevice corros6on oc.

curred in this environment. Doth Altoy 304L and Alloy 825 ex-actor pressure vessel. The analysis methods are based on two differetit aptroachen that are currently being ceveloped to ana, hibited low general corroWon rates with no evidence of locahzod lyre and to explain the effects of transverse strain and stress conosen Ming, creva conoson or ln a png mon-states on fracture toughness. The first approach is a micro me-ment in the absence of hydrogen peroxide (H(2)O(2)) a species chanical approach that prov6 des a relation between fracture addod to simulate the oftects of radiolysis. Alloy 825 continued toughness and more fundamental matonal propertes that can to exhibit good corrotuon performance aftet Ht2)O(2) was added be determined expenmentally. The second approach focuses on to the pitting environment; whereas. Alloy 304L exhituted both the development of correlation parameters that relate fracture pitting and SCC as a result of the H(2)O(2) addition.

toughness with nominal stress and strain states. In the first NUREG/CR 6601: EFFECTS OF PH ON THE RELEASE OF RA.

phase of this work, the scope of the investigation is hmited to DIONUCLIDES AND CHELATING AGENTS FROM CEMENT-crack front constraint conditions that can be described in terms SOLIDIFIED DECONTAMINATION ION-EXCHANGE RESINS of conventional one-parameter (K or J) in-plans near-tip fields COLLECTED FROM OPERATING NUCLEAR POWER STA, and the transverse strain, Validation checks of the analysis TIONS. MCISAAC,C.Va AKERS D Wa MCCONNELLJ,W, EG&G methods against existing fracture dsta for conditions of con-Idaho, Inc. (subs. of EG&G. Inc1 June 1991. 316pp.

tained crack lp yieldings are promising but incomplete. Recom' 0107080245. EGG 2005. $8307.229.

mendations for subsequent phases of the work considered nec-Data are presented on the physical stability and leachabitsty essary to provde more precise estimates on the effects of posL of radionucides and chelating agents from cement noldfied de-tive out-of-plane straining on the crack initiat on toughness of contamination ton-exchange resin wastes collected from two ctrcumf erentially onented flaws are included operating commerciat hght water reactors Small-scale waste-NUREG/CR 6595: FORECAST: REGULATORY EFFECTS COST form specimens collected donng soidficat ons portorined at the ANALYSIS SOFTWARE MANUAL Version 3.0. LOPEZ,0.;

Brunswtek Steam Electnc Plant Unit 1 and at the James A. Fit 2-SCIACCA,F.W. Science & Engineenng Assouates. Inc. Novem.

Patnck Nuclear Power Station were leach-tested and subjected ber 1991.123pp. 9112310182. SEA 89 46111 A1,60156:289.

to compressive strength testing in accordance with the Nuclear Over the past several years the NRC has developed r gener.

Regulatory Commission'a " Technical Position on Waste Form" Ic cost methodology for the quantascation of cost / economic 6m.

(Revision 1). S mples of untreated resin waste collected from pacts assouated with a wide range of new of revised regulatory each sohdificatio, vessel before the soldfication process were requirements This methodology has been developed to aid the analyred for Concentrations of radionuchdes, selected transition NRC in preparing Regulatory impact Analyses (RIAs). These ge.

metals, and cholating agents to determine the quantites of neric costing rnethods can be useful in quantifying 6mpacts both these chemicals in the waste-form cpecirnent. The Chelating to Industry and to the NRC, The FORECAST program was de.

agents included oxahc, citnc, and picohn6c acids. In order to de-veloped to facihtate the use of the genenc costing methodology, tormine the effect of Isachant chemical composition and pH on This PC program IrGgrates the n,ajor cost considerations that the stability and leachabihty of the waste forms, waste, form may be reouired because of a regulatory change. FORECAST specimens were Isached in various teachants Results of this automates rnuch of the calculations typically needed in an RlA study Indicate that differences in pH do not affect releases from and thd reduces the time and labor required to perform these cement sohdified decontamination lon-exchange resin waste aWyses More importantry, its 6ntegrated and consistent treat, forms, but th.it differences in teachant chemistry and the pres-ment of the different cost elements should help assure compre.

ence of chelating agents may affect the releases of radionu-hensiveness, uniformiy, and accuracy in the preparation of chdes and chelating agents. Also, this study indicates that the needed cost estimates, cumulative releases of radionuclidos and Chelating agents are NUREG/CR 5598: IMMERSION STUDIES ON CANDIDATE CON".

t ete TAINER ALLOYS FOR THE TUFF REPOSITORY BEAVERS.J Aa DURR.CL Cortest Columous, Inc. May 1991, NUREG/CR $606: A REVIEW OF THE SOUTH TEXAS PROJECT 122pp. 9105300197. 57868.123.

PROBABILISTIC SAFETY ANALYSIS FOR ACCIDENT FRE.

Cortest Columbus Technologies is investigating the long-term OUENCY ESTIMATES AND CONTAINMENT BINNING.

performance of container materials used for high level radioac-WHEELER,T.Aa LAMBRIGHT.J.A.; et al. Sandia National Lab-tive waste packages. This information is being developed for oratones DARBY,J L. Science & Engineenng Associates, Inc.

the Nuclear Regulatory Commission to aid in the:r otsessment August 1991. 345pp. 9109050259. SAND 901970. 58989.281.

I 1

1

s.

Main Citations and Abstracts 33 The otqective of this review is in evaluate the SoJh Tem degrade, and in many cates, the fundamental promtes con-Prolect (STP) Probabibsbc Sa41s Ana'ysis (PSA) lot the trolhng periormance of the barriers will be differont for intact USNRC. The PSA was vocewod for thoroughness of ana'ysis, and degraded conditions This document esamines factors con-accuracy in plant modeling, legtimacy of assumptions, and trothng fluid flow through antact and degraded concreto dinposal overmil quality of tho work. The review ss limited to the internal facilities Simplitiod models are presented for predicting build up event analysrs and the fire accident analysis. This review is not of fluid above a vault, fluid flow through and around intact a pass / fail evaluation of the adequacy of the PSA The adequa-vaults, through flaws in coatings / liners applied to a vault, and cy of the analysis depends on the intended uses and rnust be through cracks in a concrete vault, and the influonce of d8Herent add'essed on a case-by-case balos by the licensee and the backfill matenals around the outside of the vault. Enampic cal.

NRC This recew ideritifies 6trengths. weaknesses, and areas culations are presented to 4tlustrate the parameters end proc.

whore add! tonal clantication would ass 41 the NRC in evaivating esses that influence fluid flow.

the PSA for specific regulatory purposas. The licensee, Houston Lighting and Power (HLP), toviewed this report prior to its f nai NUREQ/CR 66te: USER'S MANUAL FOR THE NETTRAN h retense to the NRC. Tho responsed provided by HLP are proved.

COMPU1ER

CODE, OLAGUE,N E :

LONGSINE,0 E.;

i ed an detad in appendices to this toport, and they are summa.

CAMPDELL,J E.; et al. Sandia National Latsoratories. relpuary nied in the main bod / of the report All issues remed in the 1991. 259pp. 0103050$03. SAND 90-2089 58 870 095, review were adoountely addressed by HLP in their responses.

This document describes the NLF1RAN 11 (Network Flow and NUREG/CR4611 ISSUES AND APPROACHES FOR USING and is intended to provide the reader with suf4cient :nfo6 mat on EQUIPMENT REttABILITY ALERT LEVELS LOFGREN,EN4 to use the code. NEF1HAN 11 was developer! as part of a pet.

GREGORY.S H Science Applications International Corp (lor-formancu assessment methodology for stnrage of high level nu-rnerly Science Applications, Inc) ' Drookhaven National labo-clear waste in unsaturated, welded tuff. NEFTRAN Il ta a suc-f atory. June 1991.137pp. 91070B0250. BNL NUREG.52251.

$830B 218.

cet40t to the NEFTRAN and NWFT/DVM computer codes and contains severet new capabilities. These capabilites include. (t)

This report desenbes work accomplished to 6dentify issues and approaches to estabhsh alert levels for component tehabil-the ability to input pore velocities directly to the transport model ity. Rehabil ty alert levels are estabhshed on standby component and bypass the network fluid flow model, (2) the ability to trans.

counts of success and laiture, where equipment demands are port radionuckdes in time. dependent velocity fields (3) the abill-ty to account for the efteCt of time-dependent saturation monitored and counted to ascertain if assumptions about ac' ceptable te!iability are likely to be Correct A Monte Carlo simu-changes on the retardation factor, und (4) the ability to account laton we a used to determine the detection responbne and falso for time dependent flow tates through the source regime. In 64 alarm rates for several alett level systems. The detecten re-dition to these Changes, the input to NEFTRAN ll has been modified to be more convenient for the user. This document is spor 3es were obtained in response to a specified reliabikty dog' radaton Two of the alert systems were demonstrated with divided into four mMn sectiorse consist ng of (f) a description of actual f. lure data on the Emergericy Diesel Generator (EDG)

Atl the models contained in the Code, (2) a desCnption of the for five plants. Durden and nsk measures of effectiveness were program and subprograms in the Code. (3) a data input guide, developed to compare different alert isvel schemes having dif' and (4) venfication and sample Problems. Although NEFTRAN 11 ferent detection responses and fatso alarm rates.

is ttle fourth generation code, this document is a complete de-senption of the code and reference to past user's manuals NUREGtCR 6612: DEGRADATION MODELING WITH APPLl;A.

should not be neC6ssary, TION TO AGING AND MAINTENANCE EFFECTIVENESS EVALUATIONS. SAMANTA P,K; VESELY,W E.; HSUf.; et al, NUREG/CR 6619: THE IMPACT OF THERMAL AGING ON THE Brovkhaven National Laboratory, March 1991, 73pp.

FLAMMABILITY OF ELECTRIC CABLES. NOWLEN.S p. Sandia 9104220330. DNL NUREG 52252. 57448.028.

National Laboratories, March 1991, 35pp. 9103200039.

This report desenbes a degradaton modeling approach to SAND 90 2121. 57065 309 analyM data on component degradation and failure to under-A0 iDV06t'gstion of the impact of thermat aging on the llam-stand the processes in aging of components. As used here, mabihty of two common types of nuclear grade electncal cables degradation modeMq is the analysis of informato1 of compo, has been performed. Four large scale flammability tests were nont degradation C sder to develop models of the process and perforrWI with each of the two Cable types tested in both an its implications This particular modeling focuses on the analysis unaged (ie., new off the real) and a thermally aged (artificially of the times of Component degradations, to model how t')e fate aged) Condition. In all cases, the fire was observed to Consume of degradation changes with the age of the Componefit The virtually all of the combustible cable Jacket and insulaton mate-methodology presented also discusses the effectivensts of flal present. However, for both Cable types tested, the thermal maintenance as applicable to aging evaluations The upectfic aging process caused a decrease in the cable flammability as applications whic presented also discussos the effectiveness of demonstrated by decreases in the fate of fire growth, peak fire maintonance as applicable to agsng ovaluatons The specific -

Intensity, total heat released, and near fire temperatures This apphcatons which are performed show quantitative m>dels of fesult is consistent with past Cable aging studies because it has component degradation rates and component failure r6tes from been observed that the thermal aging process will drive off Cor.

plant-specific data The statratical techniques which were devel, tain of the more volatile constituents of a polymenc matenal.

oped and applied allow aging trends to be effectively identihed Presumably, when these agod materia!S are subjected to a hre, in the degradaten data, and in the failure data tnatial estimates the evolution of volable C3mbustible gases is reducod as Com.

of the etiectrveness of maintenance in limiting degradations pared to the unaged materials, and hence, flammability la re-from becoming failures also were developed. These results are duced. The results of these tests indicate that, at least for the important hrst steps in degradation modeling and show that two cable types tested, the evaluation of cable flammabihty degradation Can be modeled to 6dentify aging trends.

using unaged cable samples will remain a conservative indicator NUREG/CR 5614: PERFORMANCE OF INTACT AND PARTIAL-LY DEGRADED CONCRETE DARRIERS IN LIMITING FLUlO NUREG/CR 5620: THATCH: A COMPUTER CODE FOR MODEL.

FLOW. WAL10NJC,; SEITZ,R R EG&G Idaho, Inc. (subs of LING THERMAL NETWORKS OF HIGH TEMPFRATURE GAS-EG&G, inc ) Ju'y 199t< 56pp. 9107220292, EGG 2614 COOLED NUCLEAR REACTORS.

KROEGER P.G.;

$8489.093.

KENNETT,RJ; COLMAN,Ja et al Brookhaven Natonal Labora-Concrete bamers will play a entical role in the long. term isola.

tory. October 1991. 354pp 9112310105. DNL NUREG 52297.

tion of low-level tadoactive wastes Over time the bamers will 6015LOS2.

=

m_,,m.,,__.--m.m.

34 Main Citations and Abstracts This report documents the THATCH code, which mortels t Surty was used as a reprt$entative dry containmelt plant for mal and flow networks of solids and Coolant channois rt, twu.

the evaluation of possible ways that containment performance dimensional geDmetries lhe ma* apphcation of THATCH is for could be improved Sensitivity studies using the NUREG 1150 teactot thermo hydraulic LFansLHs in High lemperatura Q33 models and methodologies were used to estimate the teddCt60n Cooled Reactors (HTGAs) The code simulates core heatup of r sk potentials resulting from bypass scrutitung and DC64 par-transients, heat transfer to gerwral sinks of to specific air of tial depressurtratiott These $1udieb showed that the gicatest fe-watet cooled teactor cavity cooling systems Graphite ondation duction of nsk occurs when bypass teleases are mitigated by during air or water ingress can be modelled, including the chem.

scruboing or prevented High pressure DCH are also important scal envrgy release A point kinetics modet is available for reac-The CONTAIN code was used to estimate reduction in peak hvity excursions. For most slow HTGR transients a user select.

containment pressure resulting from mitigation actions including ed nodabration of the cote in r.: geometry is used. A separate venting. partial depressuttration, 6ne litig and ignitors. Speci6 cal-model of heat trentifer to the symmetry element of each fuel to ths toductions were ~2 bar with earty depressurliation end-3 element is available for rapid transients The report desenbes bar with ignitors Limited studies of the benef to of venbng and the mathemahcal models and the method of solution, ft de-lnerting were made, but additional investigations are needed to scobes the code structure and its vannus procedures Details of complete this area of investigation. A brief discussion regarding the input data and file usage, ts given for the code and for the concepts to mitigate the consequences of bypass is presented.

preptocessing and postprocessing options. The 1 HATCH model CONTAIN-code calculations were periormed to invest' gate the of the current 3b0 MW(th) reactor is derscrited input data for possible overpressurization of the c0ntainment for the station four temple cases are given, with output available in fiche form.

blackout scenario Installation requirements, code limitations, and some common ortot endications are hsted NUREG/CR 5634: IDENTWICATION AND ASSESSMENT - OF NUREQ/CR 5623: BWR MARK 11 ELVESSEL CORIUM INTER, CONTAINMENT AND RELEASE MANAGEMENT STRATEGIES AC1 TON ANALYSE S. GREENE,S R.; LEVIN,A Ea HYMAN C R.;

FOR A BWR MARK I CONTAINMENT LIN.CCa LEHNER,J R Brookhaven National Laboratory. Septemtet 19914 212pp.

ei al Oak Ridge National Laboratory November 1991, 222pp.

9112310189 ORNL/TM 11644. 60156 067.

9110090260. BNL NUREU 52259 59329 072.

This report desenbos the results of a tones of studes con, This report identifies and assesses accident management ducted to investigate the behavior of core debne within a BWR strategies which could be irnportant for preventing containment Mark 11 containrtent Thet,e studies focused on the interact 6on failure and/or mitigating the release of f4sion products during a of core debos with concrete and steel structures (downcomers severe accident 6n a BWR plant with a Mark I type of contain-and in pedestal floor dra ns) within the dry

• ell, the transport of ment. Based or 6nformation available from probabilistic risk as-debos through these drains and downcomers into the wMwell, tietsmerts and other eristing severe accident research, and and on debns water teactions within the wet *cil. Estimates of using simplifed containment and telease event trees, the report the conditions under which debna would penetrate the in-pedes.

identifies the challenges a Mark I containment could f ace dunng tal drain lines, the time dependent behayk)r of the detris within the Course of a sevote accident, the mechanstme behind these the drain lines, and the hmount of debns which might enter the challeng9s, and the strategies that could be used to mitigate w

suppresnion pool via these drain lines are prov6ded. An assess.

the Challenges. A safety objective tree is developed which pro-ment of the conditio.is under which the upper lip of the down-vides the connection between the safety objectives, the safety comers would be expected to fail (te. me:t) due to exposure to functions, the challenges, and the strategtes. The strategies hot core debris is presented Finally, the unique charactenstics were assessed by applying them to certain severe accident so-of debris water interactions in Mark li containments are dis.

quence categones which have one or more of the following cussed, the existing knowledge base regarding core concrete characteristics have h6gh probability of core damage or high dens water int 6tactions is summanged, and an evaluation of consequences, lead to a number of challenges, and 6nvolve the the applicability of the MELCOR 1.8 0 code's debns-water inter.

failure of multiple systems.

action model to BWR Mark ll's is presented.

^

HUREG/CR 66& PENNSYLVANIA SDSMIC MONITORING FOR WASTE PACKAGE PERFORMANCE ASSESSMENT, NETWORK AND RELATED TECTONIC STUDIES Final Repor{t nW uc at as e a

Ana W ALEXANDER.S S. Pennsylvania State Univ University Par '

JOURNEL.A G. Stanford Univ., Stanford, CA. ABRAMSON,L.R4 PA. June 1991. 37pp 9107010103' 58251:05f a

a a a

a anu.

The maDnitude 4 2 earthquake thist occurred near Lancaster Pennsylvania on April 23, 1984 was among the largest in thd ay M N m228025L 56837M2.

hetone record for that area The mainshock occurred as an ob-This report 6dentifies and investigates methodologies to deal lique thrust on a s'eeply dipping NS-stnking fault at a focal with uncertainties in assessing high-levei nuclear waste package depth of 4.7 km The associated pnncipal stress determinations performancoc Four uncertainty evaluation methods (probability-showed a maximum compressive stress oriented approximately distobution approach, bounding approach, expert judgment, and N70E in agreement with a large booy of crustal stress data wonsitivity analysis) are suggested as the elements of a method-elsewhere in eastern North America. Relocation of eartior ology that without either diminishing or enhancing the input un-events near Lancaster tevealed an elongated and nearly NS eMainties, can evaluate performance uncertainty, Such a meth-trending rone of seismierty. The activity seems to be associated odology can also help identify entical hputs as a guide to reduc-with cross-strike features that intersect the ENE trending litho-ing uncertainty so as to provide reasonable assurance that the logic units of the Tnastic Basin in the Lancaster area Other ac-risk objoctives are met. This report examines the current quali-tivity dunng the monitoring interval of this report was Confined to tam wask CoMainment $ah OM sh how, h co$nc-eastern Pennsylvania in general the earthquakes that occurred tion with the identihed uncertainty evatuation methodology, a are located in areas of past histonc seismicity. Block tectonic hamework for a quantitative probabihty based rule can be devel-swctures resulting from pre-Ordovician tectonic displacement oped, which takes account of the uncertainties. Current NRC appear to influence the distnbution of contemporary seismicity regulation requires that the waste packages provide substan-in Pennsylvanta and surrounding areas.

tially complete containment" (SCC) dunng the containment

. penod. The term " SCC" is ambiguous and subject to interpreta-NUREQ/CR 5630: PWR DRY CONTAINVENT PARAMETRIC tion This report, together with an accompanying report whPh STUDIES. GIDO.R G4 WILLIAMS.D C4 GREGORY,JJ. Sandia describes the technical considerations that must be addressed National Laboratories April 1991, 212pp. 9105160046.

to satisfy high-level waste containment requiremonts, provides a SAND 90-2339. 57728.171.

basis for a third report to develop recommendations for regula-1

Main Citations and Abstracts 35 tory uncertainty reduction in the Tontainment" regmrement or to be estremely low, clue to low degrees of chemmal desorpt on, 10 CFR Part 60 liftoff, and a low involvoment of so$ne with dust Mechanisms NUREG/CR4641: STUDY OF OPERATIONAL RISK-BASED contro og Me distnbution and fittoff of fission product rnatenal CONNGURATION CONTROL SAMANT A.P,Ka KIM.1 S Drook.

m M pnmay s@m &MM Mo@ on N MW MW haven Natiorial Laboratory. VESELY,W E Science Applications of the indiv6 dual elements. Therefore, both plateout and liftoff International Corp (formerly Scence Applications, Inc L August rnodelt should reflect those unique chemical and physical prop-1991,154pp.9106290241 BNL NUREG42261. 68912 206 1his report studies aspects of a nak based configurstion con' NUREG/CR 6646: TRANSPORT CALCULATIONS Or NEUTRON trol systern to detect and cont

• Plant configuratons from a nsk 1RANSMISSION THROUGH STEEL US!NG E.NDF / B-perspectve Configuration r an the term is used here, is V, REVISED ENDF/B V AND ENDF/D VI IRON EVALUATIONS-the management of corv ofigurations to achieve spo WILLIAMS M L.; ADOUGHANTOUS.C.; ASGARLM ; et al. Louish cific objectives One imponet myctive is to control risk and ana State Univ., Baton Rouge, LA. April 1991. 60pp.

safety. Another is to operate efficiently and to rnake effective 9104290244. ORNL/TM 11686. 57531.00$

use of available resources. PSA-based evaluations are p*

The ENDF/D VI evaluated nuclear data file has been recently formed to study configuration contnbutone to core melt fre-released by the U S Nationat Nuclear Data Center dunng 1990 Quency and core melt probabihty for two plants. Some equip-Among the most eagerty awaited new cros&section evaluations ment configurations can causg large core-melt frequency and in this data collecton are those for the natural tron isotopes, tYe are a number of such configuratons that are r of currently due to their 6mportance 6n nuclear syt.tems analysis and be-convoiled tiy technical specifications Howevsi, the expected cause the previous ENDF/D data (version V, wh6ch was re-frequency of occunence of the impacting configurations is small leased in 1979) are known to underestimate the transmission of and the corewt probability r ontnbuttoris are also generally fast reutront through steel structures such as reactor pretsure small The ins gm from this evaluation are used to develop the ves.els and radiation $Nelding in this paper, a companson in framework for an effectrve nebased configuration control made of results obtained from neutron transport calculations system. The tocal points of such a system and the requiiements performed with those two ENDF/D versions (V and VI) of iron for tools devbiopment for implementing the sy;, tern are defined.

data as well as an intermediate, fevised version V evaluation The requirements of risk models needed for the system, and that was proposed in 1986, Several different response param-the uses of plant soecific data are also discussed.

eters that are sensitive to high energy neutrons are examined.

NUREG/CR 6646: ACOUSTIC EMISSION / FLAW RELATION-for a varety of geometncal configurauons and source spectra It SHIPS FOR INSERVICE MONITORING OF LWRS is found that the two newer iron ovaluations substantially in-HUTTON,P H.; KURTZ,RJ; FRIESELM.A; et al Battelle Me.

crease the transmession of high energy neutrons through steel monal inst,tute, Pacific Northwest Laboratory. October 1991.

components with an inc6derd fission spectrum source. Prelimi-1,125pp. 9112300090. PNL-7479. 60126.121 nary estimates indicate that 15e version Vi tron evaluation will The program concoming Acoustic Emission / Flaw Relation.

considerably 6mprove the agreement t etween calculations and ships for Inservice Monitonng of LWRs was initiated in FY76 expenmental dosimeter measuromonts used in light water teac-with the objective of validatirig the application of acoustic emis-tot pressure vessel fluence analysis. The calculated leakage sion (AE) to monitor nuclear reactor pressure containing compo-spectrum of D T fusion neutrons from an iron sphere is also im.

nonta dunng operation to detect cracking The program has proved for energies above t MeV, but large discrepancies with been supported by the U S. Nuclear Regulatory Commission, the measured spectrum are still observed at lower energies.

Office of Nuclear Regulatory Research with supplemental sup-port from the Tennessee Valley Authority. Research and devel.

NUREG/CR-5651: AN INVESTIGATION OF CRACK TIP STRESS opment has been performed by Pacific Northwest Laboratory, FIELD CRITERIA FOR PREDICTING CLEAVAGE CRACK INITI-operated for the Department of Energy by Battelle Memor al in-ATION. KEENEY WALKER; DASS,0.RJ LANDES.J D.

Oak stitute The program has shown the feasibility of continuous, on.

Ridge National Laboratory. September 1991.

52pp.

line AE monitonng to detect crack growth and produced validat.

9110060387. ORNL/TM 11692. 59326 001.

ed methods for applying the technology. Included are relation.

Cleavags crack initiation in large4cale wide-plate (WP) speci.

ships for estimating flaw severity from AE data and field applica, mens could not be accurately predicted from small, compact tions at Watts Bar Unit 1 Reactor, Limanck Unit 1 Reactor, and (CT) specimens utilmng a linear elastic fractuie mechanics, the High Flus Isotope Reactor, This report discusses the prc.

K(Ic), methodology, in the wide-plate testa conductod by the gram scope and organization, the three program phases and Heavy Secton Steel Technology Program at Oak Ridge Nation-the results obtained, standard and code activities, and instru-al Laboratory, crack initiation has consistently occurred at stress mentation artd software developed under tnis program, intensity (K(I)) values ranging from two to four times those pro-dicted by the CT specimens. The work centers around nonlinear NUREG/CR-5647; FISSION PRODUCT PLATEOUT AND LIFT

• two and three-dimensional finite-element Analyses of the crack-OFF IN THE MHTGR PRIMARY SYSTEM. A REVIEW.

tip stress fields in these geometnes. Analyses were conducted WICHNER.R.P. Oak Ridge Nationat Laboratory. Apnl 1991, on CT and WP specimens for which cleavage initiation fracture 127pp.9105030145, ORNL/T M 11685. 57617:163.

had been measured in laborstory tests. The local crack-tip fields A review is presented of methods for predicting radioactivit/

generated for these specimens were then used in the evalua-release resulting from depresavizaton o* an MHTGR pomary tion of fracture correlation parameters to augment the K(1) pa-system. The varous types of tieposition mechanisms effective rameter for predicting cleavage initiation. Parameters of hydro.

for iodine, cesium, strontium, and silver are discussed in terms static constraint and of maximum pnncipal stress, measured vo-of their chemscal characteristics and the nature of the materials tumetncally, are included in these evaluations. The results sug-m the pnmary systont Emphasis is given to iodine behavior, in-gest that the cleavage Initiation process can be entfelated with cluding the quantity available for release, the types of "pla*

the local crack tip fields via a maximum principal stress criterion teout" locations, and the effect of dust on distobution and re-based on achievng a critical area within a entical Stress con-letse. The behavior of fission products cesium, strontium, and tour. This criterion has been successfully applied to correlate sil' in such accidents is presented quelitatrvely. A major part cleavage initiation in 2T CT and WP specimen geometnes.

A review deals with expected dust leyels, types, and trans-poo. Avallable information on the level and natute of dust in the NUREG/CR 5654: CONTAINMENT VENTING ANALYSIS FOR HTGR primary system is reviewed. A summary a presented of.

THE SHOREHAM NUCLEAR POWER STATION dust deposition and liftoff mecnanisms. This study concludes GALYEAN.W.J.; KELLY.D.L. EG&G Idaho. Inc. (subs. of EG&G, that loaine releases from dry depressunzaten events are likely inc ). March 1991. 200pp. 9104080287. EGO-2fi32. 57321:172

_=

l 36 Main Citations and Abstracts An evaluation of the Sb' " m Mark 11 cont'iinment was per-ht ng. and an example of the use of F P) P-2 support the use fJrmed to 6dentify the efts - of containment venting on core of the code.

melt frequency, containment failure rnode, and offsrte conse-quentes The analysis was based on the Long Island L6ghting NUREQ/CR 5660: STATIC AND $!MULATED SEISMIC TESTING Compan(a updated 1988 probatslike risa assessment of the OF THE TRG 7 THROUGH.16 SHEAR WALL STRUCTURES Shoreham plant with the proposed Supplemental Coittainment FARRARCR: DOVE.,4 C. Los Alamos Natonal Looratory.

System (SCS) The SCS is a filtered containmont vent system BAKER,W E. New Mexico, Univ. of, Atbuquerque, NM E+ptem-based on the Swedish Filtra system installed at the Barneback bor 1991.112pp. 9110080384 LA 11992 MS 69308 323 Nuclear Power Stabon in southem Sweden The following ttuce Results from the static, simulated seismic base excstation, different containmerit venting strategos were examined for their and expenmental modal analysis testa performed on the TRG-7 cffects on piant risk: (1) venting using the proposed Filtra through 16 structures are reported These results were used to system, (2) venting using the existing equipment at Shoreham, establish the scalability of static and dynamic response meas-and (3) no venting in addition, the consequences of contain-ured on small structural models to the dynamic response of rnent venting were esamined in conjunction with two sats of an-conventonal concrete structures in additon, these tests provtd.

sumptons about the effects of a harsh reactor building environ.

ed information concerning cumulattve damage effects that occur ment, produced by containment failure or venting through the in concreto structures when they are sub ected to efferent dy-t entstang containment and reactor building heehng, ventilating =

and au condttoning systems, on the equipmer t loccted there.

namic load sequences in contrast to previous results obtained Specifically, the analyses studied the conserJuences when a in the early part of this progism, TRG 7 through 10 responded harsh reactor buikling environment is assurped to hs.ve either to simulated soismic encitations with theoretical stiffness values no adverse effect on eqaipment or to f ail all equipment.

until peak nominal base shear stress levels of 150 psi were NUREG/CR-5655: SUBMERGENCE AND HIGH TEMPERATURE t

togram t y vded STEAM TESTING OF CLASS 1E ELECTRICAL CABLES.

JACOBUS.M.J Sandia National Laboratones. FUEHRER,GE.

NUREG/CR 5662: HYDROGEN COMBUSTION. CONTROL AND Science & Engineenng Associstes, Inc May 1991, 9Bpp-VALUE lMPACT ANALYSIS FOR PWR ORY CONTAINMENTS.

9106160008. SAND 90-2629. 58130.143-YANG,J W.; MUSICKI,Za NiMNUAL S. Brookhaver$ Natonal This report describes the results of high temperature steam t.aboratory. June 1991 204pp. 9107230271. BNL-NUR50-ter, ting and submergence testing of 12 different cable products

$2271, 58496 001, that are representatrve of typical cables used inside contain.

monts of U S. light water reactors. Both tests were performed Hydrogen issues applicable to PWRs with dry containment after the cables were exposed to simultaneous thermal and ra-der,6Uns are reviewed based on eulsten9 information from the diation aging. followed by exposure to loss of-coolant accidbnt NRC's severe accident researct. program. Additir.,nal caicula-simularons. The results of the high temperature steam test Indi, tons were performed using the CONTAIN code for a multi com.

cate the approximate thermal failure thresholds for Sach cable partment model of the Zion plant. The review inc'udes in-vessel type. The results of the submergence test indicate that a and ex vessel hydrogen generation, time and modes of hydro-number of cable types can withstand submergence at elevated gen release, hydrogen mixing and transport in the conta,nment, temperature, even after exposure to a loss of coolant accident hydrogen combustion mechanisms, hydrogen control inethods simulation.

and the equipment survivability. A cost-benefit analysis of the NUREG/CR 5656: EXTRAN A COMPUTER CODE FOR ESTI-hydrogen 6gnition system was periormed for the Z6cn and Surry MATIN 3 CONCENTRATIONS OF TOxlC SUBSTANCES AT plants Potential for hydrogen detonation in these plants was CONTROL ROOM AIR INTAKES. RAMSDELL,J V. Battelle Me-evaluated.

f6 D M'h NUREG/CR 5663: RELAPS THERMAL HORAULIC ANALYSIS 9t 116 NL $10 5154 0 M

This report presents the NRC statt with a tool for assent,ing the potential effecte of accidental teleases of radioactive matere MARTIN.R P. EG&G Idaho, Inc. (subs. of EG&G, Inct May als and toxic substancus on habstrblity of nuclear f acility control 1991. 76pp. 9106040385. EGG-2633. 57004.014.

ronms. The tool is a computer code that estimates concentra.

Thermal-hydraulic analyses of five hypothetical accident sco-tions at nuclear facility control room air intakes gWen informa, nanos were performed with the RELAP5/ MOD 3 computer code tion about the release and the environmental conditions. The for it.e Dabcock and Wilcox Company Washington Nuclear name of the computer code is EXTRAN EXTRAN combines Project Unit 1 (WNPI) pressunred water reactor. This work was procedures for estimating the amount of airborne materjal, a sponsored by the U S. Nuclear Regulatory Commission (NRC)

Gaussian puff dispersion model, and the most recent algonthms and is being performed in conjunction with future andyms work for estimating W1uwon coefficients in building wakes It is a at ti,e NHC Technical Training Center in Chattanooga, Tennes-modular computer code, wntter' in FORTRAN 77, that runs on see. The accident scena1os were chosen to assess and bench-personal cornputers it uses a math coprocessor, if present, but mark the thermal-hydraulic capabilitics of the Technical Training does not require one. Code output may be directed to a printer Center WNP1 simulator to model abnormal transient condit ons.

or disk files.

NUREG/CR 6658: FPFP 2: A CODE FOR FOLLOWING AIR.

NUREG/CR-5665: A SYSTEMATIC APPROACH TO REPETITIVE DF'E FISSION PRODUCTS IN GENERIC NUCLEAR PLANT FAILURES. ODLAND,0.J. Sonalysts, Inc. February 1991,33pp.

9103110198. SI 14040000 1, 56942:209 F t.O /

PATHS.

OWCZARSKI.P.C.;

BURK KAV:

V W ' ELL.J.Va et al. Battelle Memonal Institute, Pacife North, This report presents a model of a systematic approach to ad-en i moratory March 1991, 82pp. 9104020084 PNL 7513.

dress and correct repetitive failures. In this context. repetitive b E.257.

f ailures are the recumng inability of a system, subsystem, struc-This report descobes the technical basw and use of the ture, or component to perform its intended function. The report computer code FPFP-2 (Fission Product flow Paths). FPFP-2 presents a systematic method for identifying repetitive failures, was developed to estimate the concemrations and flow rates of selecting the failwes to be investigated, determining root cause, acrborne fission products along a ges:eric flow path following a selecting corrective actions for implementation, and monitoring transient of puft source of fission prooucts at the beginning of subsequent system / component performance. Appendix A pro-the flow path. TNs report serves as a user's guide for FPFP-2.

vides an example of the use of this methodology at an operat.

A complete code description, code operating instructons, code ing nuclear generating stat on.

Main Citations and Abstracts 37 NUREQ/CH4666: PROGRAMMATIC ROOT CAUSE ANALVSi?

cation. PNt condiaeted a search to 1nd the most po tenent liter.

OF MAltaENANCE PERSONNLL PERFORMANCL PROB.

sture regarding toticity in humana and in empenmental ammals.

6 EMS INABA,K XY2YX Information Corp. January 1991.

Much of the literatu's is at least a decade old, not an unexpect-105pp 910211019f, 66%2169 ed finding since acute esposures oso less cunn periormed now This report presents a method for d' arm % the program.

ttan they were a few years ago in most cases, the studies did matic itet causes of personnet perforf '

)taems in the rot specihcaily enemine the e#ects of two-minute exposures, maintenance of nucleat power plants als uses enr.

thus, entrapolations had to be made from studes of longor as-e mally avabble maintenance work ordes.., ( 6dentify repeat posure penods Whenever possible, PNL gavu the greatest mairitenance caused by 6nadequate personnel perionnance.

weight to human data, with esperimental trumal data serving to The pnt tary emphat,is of the analysis is on corrective mainte.

stengthen the conclutnon airived at from considorathn of the nance, but the process will delect corrective maintenance ac-human data Although certain indiv6 duals show hypersensitivity lions caused by errors inade dunng scheduled tnatntenance to fnetenals IAe sulfur diondo, PNL has not.ittempted to factot Four logic trt+es are provided to help tsobte the causes of such this information irito the recommendations Attet the evaluation problems to program elements. The pr00'am elements consist of the da,a en the literature, PNL held a small workshop. Major of the technicians and their managers, as well att support e)e.

part6cipants in this workshop wore three consultants, all of ments and their manligers, such as the people responsible for whom were Diplomates of the Amercan Board of Toxicology, developing procedures and other documentation, developing and staff from the Nuclear Regulatory Commissios PNL's pre-and delWnng training programs, etc Because of the impor-liminary recommendations for two-minute esposure limits and tance of management commitment to improve maintenance, the fat!onale for them were d4 cussed and Consensus teached emphasis is placed on 6dentifying responsible managers, as a on final recommendations. Ther,e f 0 commendations are: (1) am-primary or co-cause of problems A sample applention of the monia 300 to 400 ppm; (2) chlonne 30 ppm; (3) Halon 1301 process to a plant is also presentad-6%; Halon 12112%; and (4) sulfur diouje 100 ppm Control NUREQ/CR 5667: INEL PERSONAL COMPUTER VERSION OF toom operators should be able to tolerate two minute exposures t these levels, don fresh ait enatin and continue to operate MACCS 1.5 JONES K R; DODBE,C A; KNUDSON.D L EG&G h reador H h tonc mawnal is cWnsM or saMy $M Idaho. Inc. (subs of EG&G. Ir c ) March 1991. 37pp 9103M0227. EGO 2634. 57152.307.

down the teactor if the toiuc gas remains The VELCOR Accdont Consequence Code System, Version NUREG/CR 5670: MUL11 LOOP INTEGRAL SYSTEM TLST 1.5 (MACCS 1.51, calculates potential consequences fesulting (MIST) MIS 1 FACILIT Y FUNCTIONAL SPECIFICATION.

from atmorpnene releases of radioactive matenais, Sandia Na-HABIB,TL; s,0KSALC G ; MOSKALT Ea et al. Dabcock &

tional Laboratones developed the code for the U S Nuclear Wilcox Co, Apnl 1991. 327pp. 91052*n035. EPRl/NP 7165 Reguistory Commission on a VAX/VMS miry computer. This

$782$193 report documents the Idaho Natio tal Engineering

'atory The Multiloop integral System Test (MIST) is part of a multi-conversson of MACCS 1.5 for compilation and execuc

) an phase program started in 1983 to address small break loss of.

80386-based IBM or IBM compatible pettional compt.

'C) coolant acc6 dents (SDLOCAs) specihc to Batcock and Wilcox The resulting PC version of the code is available throg, the designed plants MIST is sponsored by the U.S. Nuclear Regu-National Energy Software Center, Argonne National Laboratory, latory Commission, the Babcock & Wilcox Owners Group, thw 9700 South Casa Avenue, Argonne,IL 60439 Electnc Power Research Institute, and Babcock and Wilcox.

NUREO/CR 5668: DATA

SUMMARY

REPORT FOR FISSION The unique features of the Babcock and Wilcos design, specin-PRODUCT RELEASE TEST VI-5, OSBORNE,M F.:

cally the hot leg U bends and stoam generators, prevented the LORENZ,R. A.: TRAVIS.J.R ; et at Oak Ridge National Laborato.

use of eristing integral system data or existing integral fac44t.es ry. October 1991. 62pp. 9111110200. ORNL/TM 11743 to address the thermai-hyttraule SDLLJA questions MIST was 59575:355.

specihcally designed and constructed for this program, and an Test VI 5, the fifth in a senes of high-temperatuis boion existing facility-the Once Through Integral System (OTIS)-was product release tests, was conducted in a flowing mixture of hy, also used. Data from MIST and OTis are used to tenchmark drogen and helium The test specimen was a 15 2 cm-long sec.

the adequacy of system codes, such as RELAP5 and TRAC, fur tion of a foot rod which had been leradiated to a burnup of 442 predicting abnormal plant transients. Tho MIST Functional mwd /kg Using a hot cell mounted test apparatus, the fuel tod Specifcation documents as built design features, dimenbions, was he sted in an induction fumace under simulated (WR acci.

instrumentation, and test approach, it also represents the scal-dent co itions to two test temperatures,2000 K for 20 min and ing basis for the facility and serves to define the scope of work then 2700 K for an sodibonal 20 min. Based on fission product for the f acility design and Construction.

Invernones measured in the fuel or calculated by ORIGEN2, NUREG/CR 6672 V01: CHARACTERISTICS OF LOW LEVEL RA.

DIOACTIVE WASTE. Decontamination Waste. Annual Report fu or K (1 Cs ad 37)C

% r (125)Sb: and $7% for (154)Eu. Almost 3% of the lodine was scal W ar M AAC,@ MSM M a

of uay M W collected in a volatile form. In the hydrogen atmosphere, the Zircatoy cladding melted, ran down, and reacted with the UO(2)

T P e

• • Characteristics of Low-and some of the fission products. The total mass released frorn Level Radioactnre Oste: Decontamination Waste Forms" the furnace to the collection system was 4681 g. The results funded by the U.S. Nuvear Regulatory Commission, is to pro'-

from this test were compared with the CORSOR M and ORNI' vide base line data on the stability and teachability of solidified 3

diffusion release models.

decontamination wastes that are generated at operating Com-NUREG/CR 5669: EVALUATION OF EXPOSURE LIMITS TO mercial nuclear power stations following the CherrJcal decon.

TOXIC GASES FOR NUCLEAR REACTOR CONTROL ROOM tamination of pnmary coolant systems This work is being per.

OPERATORS. MAHLUM,D Da SASSER,LB. Battelle Memorial formed to assess the adequacy of tests identified in " Technical Instituto, Pacife Northwest Laboratw July 1991. 68pp Position on Waste Forms," prepared by the NRC Low level 9108190200. PNL-7522, 58828.323.

Waste Management Branch, to meet the requirements of Pacife Northwest Laboratory (PNL) has evaluated ammonia, IOCFR61, As part of this project, samples of decontamination chlonne, Halon {actually a genere name for several halogenat-

. waste stream resins and coment webte toims were obtained ed hydro-carbons). and sulfur dioxide for their possible ehects from commercial nuclear power stations Dunng Fiscal Year dunng an acute two-minute exposure in o' der to derree recom-1990, samples from the FattPetnck, Brunswick, and Peach mendations for maximum exposure levels. To perform this eva!-

Bottom nuclear stations were examined Samples were subject-

=

._...__.__.___.._..__._.___.-_------_--a-A-.-s--_m--

38 Maln Citations and Abstracts ed to the teach tests descritno.n " Technical Poution on Waste tory expenments have been performed on 17 tuff cdnders with Forms" to asaess the effects of the decontaminat on wastes on three types of fracturet (1) tenson+iduced crackt, (2) natural tho stacility and leachability of the was% forms. Dernineralized fractures, and (3) sawcuts. Pnor to grouting, the hydraulic con-water and four different synthetic leauhates with pH ranging ductivity of the intact rocli and of the fractures is measured frum 4.2 to 10.4 we's used for the tests. The res/ts of these under a range of rormal stresses. The surface mpography of tests are tabulated and prehminary analyses are presented, the fracture is mapped, ar1 the results are usert to determine NUREG/CR 567h A UNIFIED INTEP#RETATION OF ONE-FIFTH sper,ure distributions across the fractures. Grotis are injected TO FULL SCALE THEAMAL MIXING EXPERIMEf 4TS RELATED thr g al TO PRESSURIZED THERMAL SHOCK. THEOFANDUS,T.G ;

f ciur s un e a c rsta t norma'l strais Five g formulations have been tested. Bentonite (O to 5 percent by "I

weight) has been added to these grouts to inctcase their stabili-679p'p 9 01501'4. 5 7121'6 'Pressunzed Thermal Shock has 1

Thennal mixing in relat on to ty. Water to-cement ratios range from 0 45 to 1.0. Permeabihty been exerrnned expenmentally throughout the world in a vanety testing of grouted fractures is used to evahate the effect've-of scales. These I. clude the CREARE 1/5, the IVO/IVO (NRC).

ness of fracture grouting Post test visual hspection of grout 2/5, the PURDUE (UCSBM '2, the CREARE 1/2, the HDR 1/1 distribution confirms that permeatulity testing in an injection hole and the UPTF 1/1 test facihties. The Regional Mixing Modet is not a reliable method to assess the effec'.lveness of grouting.

and the associated computer programs REMIX and NEWMIX Grout distribution is highly non uniform, are used to interpret these cata, in this report, in a comprehen-NUREG/CR 5684: ANALYSES AND FIELD'fESTS OF THE HY-sive fashion. These interpretations indicate that cooldown tran~

DRAULIC PERFORMANCE OF CEMENT GROUT BOREHOLE sents anti deghse of stratificaton can be p*edicted with confe-SEALS. GNdER W.B.: DAEMEN.JJK Artzona, Univ. of, dance. Universal stratifsation solutions are also provided. i"

,j graphical 'orm, and a simple procedure for handes culation is' Tucson, AZ. April 1991. 527pp. 91043 CONS. $7557:185.

1. SO O'S Three tests for determining the hydraulic properties of bore-f hole seals are analyzed in detail. Two consist of monitonng the 9

NUREG/CR 568t: LOW LEVEL WASTE SOURCE TERM MODEL injection rate o water at constant pressure into one end of a r

h DEVELOPMENT AND TESTING. SULLIVAN,T,M.; S JEN,C J.

seal and monitoring the collection rate into a free draining 2one Brookhaven National Liboratory Msy 1991, 101pp.

at the other end. The third test is performed by shutting in the 910SXO183. BNL NUREG-52200. 57868:287.

collection zone and monitortng the buildup in hydrauhc head.

The uw level waste tource term mxtei devalopment project One-dimensional and axisymmetric three dimensional flow has adapted / developed two computer codes to predict the mi-models are presented for analyzing test results. In the one-di-gration of radionuclides emplaced at shallow land burial facili-mensional models, the seal is homogeneoin and isotropic. In ties. The computer code FEMWATER is used to predict watcr the axisymmetne models, the seal and rock mass are homoge-flow and moisture conunt. The cumputer code Bt T is used to neous and iso *opic porous medsa, The equation for saturated, predic* cor'tainer Breach, waste for n Leaching, and contami-confined ground water flore is assumed to apply. The hydraulic nant Transpect. Recerit work on this project focused on two properties of ? seal are expressed by its hydraulic conductivity areas. One involved improvenionts to the teaching modeis 6n-und specific surage. in the axisytranetne models, the conductic corporated in BLT. In particular, this triport describes an addi-ity and specific storage of the rock rnass are included in the for-tional model that was adcWd to BLT which simulates the waiste mulatiert Closed-form solutons are presented for the one-de-form using the method of finite differenceu and treats the con-mensional modeb. Numertral antdysis wtth the axisymmetric tacting solution as a mixing bath. This model improves upon the models uses an available finite riinment code for ground-water previous models in BLT in three reas: (a) it treats the release flow, We exar.iine the effects of vanations in hydrauhc pararn-orocesses of diffusion, dissolution, and surface rinse straulta-eters on the quantities measured A the tests (i.e, flow rates or neously; (b) 4 allows for partitioning between the waste form head) and compare the one dimensional and axisymmetric and solution; and (c) It permits so% tion feedback effects to in-models. Methods are presented for obtaining the hydraulic prop-fluence dsffusive releases Verification studies of the finite diher-erties of the seat and/or rock ifians by analysis of test results. A ence/minng bath model are discussed in detail. TN Second fourth test, a tracer travel tirne test, presents a means for de-arca of research involvej comparing BLT model prov A ns to tecting any high-velocity flow pnth throu;;h or around the seal.

expenmental data. This report presents the results of modeling The test methods are acplied to cement grout borotule seals taooratory scale wet / dry cycle leach oxperimento and lysimeter from 10 to 36 cm in length and 10 cm in diameter in.a nearly experiments conducted et Pacihe Northwest Laboratory. Based horizontal hole and in three vertical holes.

on this modeMg work recommendations for future areas of study are given.

NUREG/CR 5666: EFFECTIVENESS OF FRACTURE SEALING

^

NUREG!CRo682; SPECIFIC TOPICS IN SEVERE ACCIDENT 9'91j 19 pp a Univ.

cson ne 1 0 25 MANAGEMENT, MEYER,J F,; CHUNG,Dl; PANCIERA,V,W.; et -

58309;128 al. SCIENTECH, Inc, May 1991, 200pp. 9106040392.

Sentonite is known to have an extremely low permeabthty and T is r port examines five topical aress of concern to severe a self healing abihtv. It has therefore been selected as a major accident mans.gement. Thess areas are as follows; Human Fac-sealing L mPonent in several repusttory concepts. Bentonite tors, Accident Management During Shutdown. Information gr u a

f ng a amaget W sman pa% s%

Needs, Long term implications, and Uncertainties. The objective can t.e injected into smar fractures or voids, (2) suitable water of this report is to assitt the NRC in performing its research absorption properties, ca a produce gets at low concentrations 8

function and to provide guidance to the industry on accident management strategies, as weil as accident management pro-siderable longevity. Bentanite fracture grouting tesJ are per.

Grams in general.

formed on a rnadet made of circular acrylic plates with outer di-amet1r of 30 cm and a centralinjectron hote of 2.5 cm diame-NUREGICR-5683: LABORATORY TLSTING OF CEMENT ter. Suspensions wnh bentonite concentration of 15% to 31%

GROUTING OF FRACTURES -IN WELDED TUFF.

have been injectud into fractures with upertures of 9 to 90 mi-CHARPE.C.J.; DAEMEN,J.J.K. Arizooa Univ. of Tucson, AZ.

crons under injection pressures less than 0.6 MPa. Grouting re-March 1991.163pp. 9104220323. Si448:115.

duces the hydraulic conductivities of the fractures from the 10(-

The objectNe of this irr,estigat.on is to experimentally deter.

1) to the 10( 5) emis level. When the sith snci4"'i is thin enough mine the effectiveness of fracture sealing in welded tuff using and the fracture is very umall, channehng devthps in the grout-orpary poittar.J cerNnt and microhno cement grouts. Labora-ed fractures Prehminary resuth indicate that the permeabihty of i

W.:- r.WW V vtfM.7M.

Main Citations and Abstracts 39 a grouted fracture does not increase with time in more than 125 other aimed response personnel in ohysical fitness training and days The flow properties of bentonite suspon$ons visccMy.

in physical performance standards testing The inbrmation pro-shear strGss, yield stress and gelation, are investgatad Water vided in this NUREG will help hcensees determme if guards, flow inrough ungrouted fractures and movement of water in TRTs and other armed response, personnel can effectively per.

bentonite groot are studied The ph sical stability or bleeding form their normai and emergency duties without undue hazard

/

capacity of bentonite susoenssons is determined to themselves, to iellow employees. to the plant site, and to be f"jthn th 0"

NUREG/CR-5688: MECHANICAL CHARACTERIZATION Or of E gy s

n DENSELY WELDED APACHE LEAP TUFF FUENNAJORN.K.;

DAEME N.J.J K. Anzona, Univ. of, Tucse, AZ. June 1991, (DOE) Medical and Ff, ness implemerA.x"..i u : which was 125pp 9107080?$5 58309 001.

published in March 1991. The guid, n

.ained in this NUREG are not t "irenv ', and cor a is not required An empencal entonon is formulated to describe the compres-sho strength of densely welded Apache Leap tuff. It ir,s.orpo-NUREG/CR 569h INSTRUMENTATION AVAILABILITY FOR A rates the effects of size. L/D ratio, loading rate and density varb PRESSURIZED WATER REACTOR WITH A LARGE DRY CON-ations. and improves the correlation between the test results TA!NMENT DUNNG SdVERE ACCIDENT S ARCIERI,W.C.;

ano the failure envelope Uniaxial and inaoal compressive HANSON,0.1 Et M Ida% loc. (subs. o' EG&G, Inc ). March strengths. Brazilian tensile attength and elastic proporties of the 1991.120pp. 9 tv6120192. EGG-2638, 580f 2:133.

densely welded tyrown unit of Apache Leap tuff have been de-In support of the UE Nudear Regulatory Commission (NRW termined using the ASTM standard test methods. All tuff sam-Accident Management Research Program, the availability of in-pies are tested dry et room temporature w.6.h the coie axis struments to supply accident management information dunng a normal to Ine flow layers. The uniamal compressiva strength is broad range of severe accidents is evaluated for a pressunzed 73 2 t 16 5 MPa The Brazilian tonsile strength is 5,12 1.2 MPa-water reactor with a large dry containment. Hesults from this The Young's me.1ulus and Poisson's ratio aie 22.615.7 GPa and evaluation include the following' (a) identification of plant condo 020 1 0.03. Srnoothness and perpendicularlty do not fully meet tions that would impact instrument performanco and information ASTM requirements for all samples, due to voids and inclusions needs dunng severe acadents, (b) definition of envehpus of on the sample surfaces and the sample preparation methods-parameters that would be importani in assessing the perform-The investigations of loading rate, L/D ratio and cyche loadin9 Fro of plant instrumentation for a broad range of severe acci-ettects on compressive strength and of the size effect on ten-dent sequences, and (c) assessment of the availability of plant site strength are not conclusive The Coulomb strength cntenon instrun-ntation dunng covere accicents.

adequately represents the failure envelope of the tuff under cor. fining pren.ures frorn 0 to 62 MPa. The tuff is hi0hly hetero.

NUREG/CR-6692: GENERIC RISK INSIGHTS FOR GENERAL geneous as suggested by large vanations in the results. The ELECTRIC BOILING WATER REACTORS. TRAVIS,Ra vanabihty is probably caused by flow layers and by non-uniform TAYLOR,J. Brookhaven National Laboratory. CHUNG,J. Rak distr;butwns of inclusions. voeds and degree of welding Similar Application Branch. May 1991. 08pp. 9106210013. BNL-vanabil:ty of properties has been reported elsewhere for the To, NUREG 52282. 58167:132.

popah Spnng tuff at Yucca Mountain A methodology has been developed to extract genenc nsk-based information from probabihstic nsk assessments (PRAs) of NUREG/CR 5689:

MEDICAL SCREENING REFERENCE General Electnc boiling water reactors anu apply the insights MANUAL FOR SECURITY FORCE PERSONNCL AT FUEL gained to plants that have not bnen subjected to a PRA. The CYCLE FACILITIES POSSESSING FORMULA QUANTITIES OF available nsis assessments (six plants) were examined to identi-SPECIAL NUCLEAR MATERIALS. ARZlNO P.A.: BROWNf.H, ty the most probable,i e, dominant accident sequences at each Cahfc nia State Univ, Hayward Foundetson, Inc., Hayward, CA.

plant. The goal was to include all sequences which represented September 1991. 30pp. 9110110233. 59358:007.

at least 80% of core damage frequency. If the same plant spe-lhe recommendationn contained throughout this NUREG cific dominant accident sequence appeared wtthin this boundary were provided to the Nuclear Regulatory Cornmission (NRC) as in at least two plant PRAs, the sequence was considered, to be medical screening informattor' that could be used by physicians a representative eequence. Eight sequences met this definition.

Who are evaluating the parameters for 'he safe panicipation of From these saquonces, the most impodant component failures guards, Tact. cal Response Team members (TRTS), and all and human errors that contnbuted to each sequence have been other armed response personnel in physical fitness training and prioritized. Guidance is provided to prioritize the representative in physical performance standards testing. The information pro.

se@ences and modify selected basic events that havts been vided in this NUREG.All help licensees determine it guards, shown to be sensitive to it'e plant specif;c design or operat ng TRTs, and other armed response personnel can effectively per.

vanations of the contnbuting PRAs. Thq nsk based guidance f

form their normal and emergency dubes without undue hazard can be used for utihty and NRC activities including opecator to themsolves, to fellow employees, to the plant site, and to the training, maintenance, des:gn review, and inspections.

guneral public The medical recommendations in this NUREG are similar in cr,ntant to the medical standards contained in 10 NUREG/CR 5605: A PROCESS FOR RISK-FOCUSED MAINTE-CFR Part 1046 which, in part, specifies medical standards for NANCE. LOFGREN,E.Va COOPER,S.E.; KURTH,R.Ea et al. Sci-the pro.ective force personnel regulated by the Department of ence Applications International Corp. (formerly Science Applica-

nergy. The guidehnes cor,tained in this NUREG are not re-tions. Inc.). March 1991.141pp. 9104080273. 57321:031.

quirements, and comphance is not required.

This report presents a process for focusing maintenance ie-Sources on compononts that enable nuclear plant systems to NUREG/CD-5690: PHYSICAL FITNESS TRAINING REFERENCE perform their essential functions and on compowts whose fait-MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL ure may initiate challenges to safety systems, so as to have the CYCLE FACILITIES POSSLSSING FORMULA OUANTITIES OF greatese impact in decreasing nsk. The process provides crite-SPECIAL NUCLEAR MATERIALS. ARZINO,P.A.; CAPTAN,C.Sa na, based on nsk, for deciding wNch components are entical to GOOLD,R.E. Cahfoniia State Ur v., Hayward Foundation, Inc, nsk and determining what maintonance actnnties are required to u

Hayward, CA. Septerrber 1991. 39pp. 9110110218. 59358.059.

ensure renable operation of thew "nsk.cntical" components.

The recommendations contatned throughout this NUREG are Two approaches are provided for celection of nsk-cntical com-bc:ng prcvided to the Nuclear Regulatory Commission (NRC) as ponents. One approach uses the results of a Probabihstic Risk a referer;ce manuel which can be used by licensee manaam Assessment (PRA); the other is based on the methodology de-ment as they develop a program plan for the safe participato, veloped for this report, which has a basis h PRA although it of guards, Tactica! Response Team members (TRTs), and ('i d 4 s not use the results of a PRA ctudy. Following identification 4

40 Main Citations and Abstracts of nsk-entical componenth tioth approaches use a single meth-transport codes, other portions of performance assessment odology for determnng what maintenance activities are to methodolsgy were evaluated as part of modifying the methodol-quired to ensure reliable operaton of the lduithed components ogy for tutt The scenario methodology developed under the The report also provdes demonstrations of apphcation of the bedded sait program. considered adequate, was not altered, but two approaches to selection of nsk critical components and has been apphed to tuff, An investigaton of the apphes'Jhty of demonstrations of apphcation of t% methodulogy for determin-uncertainty and wensitivity analysis techniques to nonliner ing what maintenance activit+s are required to an actwo stand-models indicates that Monte Carlo simulation remains the rmst by safety mystem, a normally operating system, and nassive robust technique for these analyses No changes have b6Jn mmponents.

recommended for the dose and health effects models, nor the NUREG/CR-5G96: tRRADIATION EFFECTS ON CHARPY biosphere transport models. Addibonally, a number of outstand-IMPACT AND TENSILE PROPERTIES OF LOW UPPER-SHELF ir'g but unresolved, technical issues have been identified.

WELDS.HSSI 3ERIES 2 AND 3.

NANSTAD,R.K.;

DERGGREN,R G Oak Ridge Natonal Laboratory. August 1991.

NUREQ/CR 5702: ACCIDENT MANAGEMENT INFORMATION 240pp.9110090295 ORNL/TW 1804. 52326:111.

NEEDS FOR A BWR WITH A MARK I CONTAINMENT.

The objective of the Second ar'd TNrd irradiation Senes was CHIEN.D.N.; HANSON,0.J, EG&G Idaho, Inc. (subs, of EG&G.

to investigate the effects of irradiation on the ductile fracture Inc ). May 1991.1Wpp. 9105220020. EGG-2639. 57824:001.

toughness of seven commercially fabiicated, low upper-shelf in support of the U.S. Nuclear Regulatory Commission Acci-wolds. All seven suomerged-arc welds were fabncated with dont Management Research Program, informaton needs dunng copper coeted wire and Linde 80 flux cnd had average bulk severe accidents have been Muated for Boiling Water Reac-copper contents from 0.21 to 0.42% with nickel levels of about tors (BWRs) with MARK l

nments. This evaluation was 0.6% in addition to the fracture toughness specimens which performed using a methodology that identifies plant information were irradiated at nominalty 288 degrees C, Charpy V notch and needs necessary for personnel to

(a) oiagnose that an accident tensile specimens were included in the capsules at available to-is in progress, (b) select and implement strategies to prevont or cations whic'T were subject to wide vanations in irradiation tem-mitigate the accident, and (c) monitor the effectiv9 ness of these perature and fluencA This report presents analyses of the stogress, (b) select and implement strategies to prevent or miti-Charpy impact and tensile test data. Analyses tevealed a de-gate the accident, and (c) monitor the effectiveness of those pendence of yield strength on irradiation temperature of -1.1 strategies. The information needs and capabihties identified are MPa/ degrees C, while the Charpy impact r 3rgy dependencies intended to form a basis for more comprehensive information were about -0.5 degrees C/ degrees C for transiten temperature needs assessments. These assessments will be performed shift and 0.06 J/ degrees C for upper shelf decrease. After ad*

during the analysis and development of specific ctrategies, justment to an irra$ation temperature of 288 degrees C and which will be used in accident management prevention and miti-normalizaton to a fluence of 8 x 10(18) neutrons /cm(2) D1 gation' MeV), the Charpy transiten temperature stufts ranged from 59 to 123 degrees C while the upper shelf energies ranged froin 58 NUREG/CR-5703:' LOWER-BOUND - INITIATICN TOUGHNESS to 70 J WITH A MODIFIED.CHARPY SPECIMEN DALLY,J.W.;

NUREG/CR 5697: USE OF THICKNESS REDUCTION TO ESTI, FOURNEY,W.L.; 1RWIN,G.R.; et al. Maryland < Univ. of, College MATE VALUES OF K. IRWIN,G R. Maryland, Univ. of College Park, MD. November

• 991. 44pp. 9112310203. ORNL-Park, MD.

• Oak Ridge National Laboratory. November 1991.

SUB797778/7. 60155:311.

24pp. 9112310207. ORNLSUB797778/5. 6015F285L

" Lower bound" initiation toughness of A 533 B reactor grade Using resulta for two 152 mm-thick wide-olate tests at the Na-stoel was determined over the temperature range from 0 to 57 tonal Institute of Standards and Technology, estimates of K degrees C by using a modified-Charpy specimen. The lower-were made using the restdual thickness reduct'on near the bound measurements were attainod by utilizing the following plane of fracture. These results corresponded well to the aver-procedures: (1) dynamic loading, (2) modification of the geome-a0e of K valuo3 for cleavage arrest and reinstiaton obtaintd at try of tho specimen, and (3) axial precompreuion of the notch.

Oak Ridge National Laboratory using generation mode, dynam-The rerort describes in detail the key features of the modihed ic-analysis computations.

geometry, the method of precompressing the specimens, and NUREG/CR 5701: A PERFORMANCE ASSESSMENT METHOD.

the strain-gage procedure. The dynamic initiation toughness OLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE DISPOSAL K(It'), which correlates Wh the lower bound toughness, was de-IN UNSATURATED FRACTURED TUFF. GALLEGOS.D P.

termined by enalping strain time records from the specimen.

Sandia National Laboratones. July 1991. 45pp. 9107230228.

The results from a fractogaphic analysis wore coitalated with SAND 910539. 58546:161.

tnose from the strain-time analysis. An empincat correlation was Sandia National Laboratones, under contract to the U.S. No.

developed relating K(I) to the energy absorbed (E(evi) dunng clear Regulatory Commission, has developed a methodology for the fracture of the specimen. Finally, the lower bound tough-performance assessment of deep geologic disposal of high.

ness from this study compared favorably with K(t) and K(Id) level nuclear waste. The applicability of this performance as.

measurements from the same matenal estabMhed in other pro-sessment methodology has been demonstrated for disposal in gram?

bedded salt and basalt; it has since been moditted for assess-ment of repositories in unsaturated, fractured tuff. Changes to NUREG/CR-5706: POTENTIAL SAFETV RELATED PUMP LOSS:

the methodology are primarily in.he form of new or modified AN ASSESSMENT OF INDUSTRY DATA.NRC Bulletin 88-04.

ground water flow and radonuclide transport codes. A new CASADA.DA Dak Rielp National Laboratory. June 1991. 5?pp.

computer code, DCM3D, has been developed to model three.

9107010081. ORNL 6671. 58248.306. -

dimensional ground water flow in unsaturated, fractured rock This report documents the results of a study of the nuciear using a dual-continuum approach. The NEFTRAN li code has

. industrVs response to NRC Bulletin 88-04. The work was con-been developed to efficientty model radonuchde transport in ducted for the U.S. Nuclear Regulatory Oommisson (NRC) Nu-time-dependent velocity fields, has the abdity to use extemally clear Plant Aging Research Piogram. All wntten correspond-calculated pore velocities and saturations, and includes the ence between utilities and the NRC was reviewed and classi-effect of saturation-dependent retardation factors. In order to fied. Major pump vendors were interviewed to discuss thair per-use these codes together in performance-assessment-type spectives on low-flow degrt.dation of pumps. Individual sites analyses, code-coupler Drograms were developed to translate were visited to review the detail? of system design and proce-DCM3D output into NEFTRAN 11 input. Iri addition to flow and dural controls relative to the Bulictin issus4.

n

---

m.,

Main Citations and Abstracts 41 NUREG/CR 570h APPLICATION OF CONTAINMENT AND RE-NUREG/CR 5713: A REVIEW OF ENVIRONMENTAL CONDI-LEASE MANAGEMENT TO A PWR ICE-CONDENSER PLANL TIONS AND PERFORMANCE OF THE COMMERCIAL LOW-NEOGY,P.; LEHNER J.R. Brookhaven National Laboratory. July LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY NEAR 1991.104pp.9108190283 BNL NUREG-52286 58828:219.

SHEFFIELD.lLLINOIS. MURPHY,E.M.; BERGERON.M P. Bat-This report identifies and evaluates accident management telle Memonal Institute, Pacific Northwest Laboratory. May strategies that are potentially of value in maintaining contain.

1991.137pp. 9105300177. PNL-7621. 57869.028.

ment integrity and controlling the release of radioactivity follow-The Sheffield low level radioactue waste disposal site is 10-ing a severe accident at a pressurized water reactor with an ice cated about 5 km southwest of the town of Sheffield, Bureau condenser containment The strategies are identified using a County, in northwestern Illinois. Lnw. level radioactive waste was logic tree structure leading from the safety object ves and safety buned at the site between August 1967 and April 1978. The functons throgh the mechanisms that challenge these safety E

• " U tualized as containing two separate aquifer systems: a regional functions, to the strategies. The strategies are applied to sovere confined bedrock aquifer system and a local unconfined aquifer accident sequences which have one or more of the following system in the shaliow sequence of unconsolidated quaternary.

chareteristes: significant probability of core damage, high con-aged sediments. The most significant hydrogeologic unit on tho sequences, give nse to a number of potential challenges, and site is a pebbly-sand unit found within the Toulon Member of include tne f ailure of important safety systems-the Glasford Formaton that grades into a coarse gravel with sand and pebbles east of the disposal site. In an area east of NUREG/CR 5711: ASSESSMENT OF UNCERTAINTIES IN the site, a narrow, channel-IAe depression is filled with coarse, MEASUREMENT OF PH IN HOSTILE ENVIRONMENTS CHAR

• gravelly sand of the pebbly-sand unit of the Toulon Member, ACTERISTIC OF NUCLEAR REPOSITORIES. KREIDER,KG; providing a hydrauhc connection between the site and nearby TARLOV,MJ.; HUANG.P.H. National Institute of Standards &

strip-mine take. Three major problems resulting from the waste Technology (formerly National Bureau of Standa. October 1991, burial at the Sheffield site include subssdence of trench covers, 105pp.9111110285.$9576:167.

significant erosion, and elevated concentrations of tntium in the This report focuses on evaluation and charactenstics of sput-vadose zone ano ground water at Shettmid.

tered th,,1 film pH electrodes which can be used to assess the corrosivity of hot (100 degrees C) aqueous solutions present in NURt!G/CR 5714: HYDROGEOLOGIC PERrORMANCE AS-nuctoar repositones. Sputtered thin films have the advantages SESSMENT ANALYSl* OF THE LOW-LEVEL RADIOACTIVE of high temperature capabihty, ruggedness, and low cost. The WASTE DISPOSAL FACILITV NEAR SHEFFIELD, ILLINOIS.

Indium oxide films were found to have a knoar, 58mV/pH, ~

SERGERON.M.P; HOLFOBL,i)J.; KEMNER.M L.; et al. Battelle sponse to changes in pH. They had little hysteresis but drifted Wm dal inse, Pacmc Mww LaMamm May N approximately 0.2V over a period of two days exposure to pH 2-143pp. 9105300168. PNL 7633, 57869;185.

^

1J solutn.ns. The films were found to be insensitNe to interfer.

ence from most ions such as alkalilons but had redox sensitivb about 3 mi southwest of the town of Sheffield, in Bureau ty to ferri-/ ferrocyanide ions. Although special surface treat-County, northwestern llhnois. The site has 21 trenches, which ments were needed for the films for good adherence at 200 de-contain about 900,000 m(3), of buried waste and about 60,000 grees C the films were not degraded after 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> exposure at Ci of nuclear by-product matenal. The disposal trenches cut pH 4, 7, and 10 at 200 degrees C. Authenium oxtde sputtered through a complex senes of Quaternary deposits, and are com-films performed equally well to the indium oxide films in parallel posed primarily of silts, clays, and sands. Ground water beneath tests. The report also contains information on electrochemistry the site, which ranges iri depth from 1.5 to 14 m, generally and testing of thin film electrodes and the charactenzatior' of moves in two directions: ncrtheast to east toward a strip-mine tho thin films by x-ray photoemission spectroscopy, ultraviolet lake and snuth to southeast toward small tributary channeta be-photoemission spectroscopy, and ion scattenng spectroscopy.

longing to Lawson Creek, wh4ch eventually drains into the stnp-mine take southeast of the site. The results in the performance NUREG/CR 5712: MORECA: A COMPUTER CODE FOR SIMU-assessment, which focused on the site ground-water pathway, LATING MODVLAR HIGH TEMPERATURE GAS-COOLED RE-suggest that tntium, Sr 90, and C 14 would be the only radionu.

ACTOR CORE HEATUP ACCIDENTS. BALL S.J. Oak Ridge Na-chdes released from the Sheffield site in any swificant concen-tional laboratory. Octuuer 1991.70pp.9112310198. ORNL/TM-trations. A companson of simulated tritsum concentrations east 11823. 60156:001.

of the site in the time frame of the burial history would suggest The design features of the modular high-temperature gas.

that model results are greater than the highest measured values cooled reactor (MHTGR) have the poter tial to make it essential.

by a factor of 2 or 3. The discrepancy between actual and pred-ly invulnerable to damage from postulated core heatup accp hat model results are greater than the highest measured values dents. This report descntas the ORNL MORECA code, which by a factor of 2 or 3 The discrepancy between actual and pre-was developed for analyrng postulated long-term coro heatup dated concentrations hkely reflects errors in the assumed triti-scenarios for which active coohng systems used to remove af-um inventory estimates, availabihty in the inventory, and/or the

- terhost following the accidents are not necessarily available.

actual release from the multitude of waste forms considered in the performance assessment. A comparison of transport results Simulations of long-term loss-of-forced. convection accidents {

both with and without depressurizaton of the primary cuolan aM M b M posse se ew has be b have shown that rre mum core temperatures stay below the "0

point at which any sg # cant fust failures and fission product re-NUREG/OR 5715: REFERENCE MANUAL FOR THE CONTAIN leases are expected. Sensitivity studies also have been done to 1.1 CODE FOR CONTAINMENT SEVERE ACCIDENT ANALY-determine the effects of errors in the predictions due both te SIS. WASHINGTON,K.E.: MURAT A,K.K.; GIDO R G.; et at uncertainties in the modnhng and to the assumptions about Sandia National Laboratones. July 1991. 260pp. 9108130345.

operational parameiers. MORECA models the U.S Department SAND 91-0835. 58781.001.

of Energy reference design of a standard MHTGR. This pro.

This report describes the phenomenological equations and gram was sponsored by the U.S. Nuclear Degulatory Commis-the numerical precedures used by the CONTAIN 1.1 code to sion to assist in the preliminary determinations of ticensabihty of determine the condihons within stuclear power platit contain-the reactor design.

ment dunng a severe accident. The CONTAIN detailed models provide the capability to mechanisticalf'* calculate the contain-ment intemal thermalhydrauhc conditions and the amount of re-

i 42 Main Citations and Abstracts dioactive matter that would be released to the environment if nonts are contained in each bettion Systern emphasis la fo-there were a leak from the containment. Note that the C04 cused on ponmeter intrus!on detection and assessment sys-TAIN models can be verified by companng the code calcula-tems. A glossary of video terms is included.

tions to expenmental results. The models desenbed include those to account for tne flows of mass and energy between NUREG/CR 5722: INTERIOR INTRUSION DETECTION SYS-containment compartments, the exchange of energy between TEMS. RODRIOUEZ,J.R.; MATTER.J C Sandia National Lab-the atmosphere and heat structures, the thermodynamic conds.

oratories. 06Y,0. DE, inc. October 1991,105pp 9201060276.

tions, the distnbutions of Leromis, the decay and transport of 0

fission products, the deflagratM of hydrogen and carbon mon-o't is to present technical information oxide, boiling water reactor suppression pool behavior, and on-that should be uneful in NRC licensees in designing interior in-geneored safety features, including a spray, fan coolers, and an trusion detectinn systems. Intenor intrusion sensors are dis-ice condenser. These models are solved with implicit coupling, cussed according to their pnmary applications' boundary.pene.

where appropriate, to obtain a stable and computationally eff,,

tration detection, volumetric detection, and point protection. In-cient solution formation necessary for implementation of an effective interior intrusion detection tystem ta presented, including pnneiples of NUREG/CR 5716: MODEL VAllDATION AT THE LAS CRUOES operaison, per*armanco charactenstics, and guidelines for TRENCH SITE. HILLS,R.G. New Mexico State Univ., Las design, procurement, installation, testing, and maintenance. A Cruces, NM. WlERENGA,P.J Arizona, Univ. of, Tucson, AZ.

glossary of sensor terins is included.

June 1991. 95pp. 9107080234 58307:134.

A senes of dynamic field expenments have been periorrned NUREG/CR 5723: SECURITY SYSTEM SIGNAL SUPERVISCN.

at the Las Cruces Trench site to provide data to test doterminis.

CHRITTON,M.R. BE, Inc. MATTER,J C. Sandia National Labora-tic and stochastic models for water flow and solute transport in tories. Eeptember 1991. 39pp. 9110100264. SAND 910949.

sr "sily variable unsatursted soils. Two expenments were per.

59351:211, formed to provide support for model validation efforts owing The purpose of this report is to present technical informaton Phase 1 of INTRAVAL (an international effort towards validaten that should be useful to NRC licensees for understanding and of geosphere models for trantiport of radtonuchdes) and a third applying hne supervision techniques to security communication expenment is currently underwcy to support the INTRAVAL links A review of security communication links is followed by Phaso 11 efforts. The third experiment utilized different boundary detailed discussions of Ink phy: Weal protection and DC/AC and instral conditions and additional chemical tracers. The data state supervision and riynamic supervision techniques Material from the third expenment along w'th model predictions from 18 also presented on security for atmospheric transmission and several modeling groups will be used to test mode!s for water video line supervision. A gbssary of secunty communication line flow and solute transport dunng inf3ftration and ICistributon.

Supervision terrns is appended.

This report summarizes the Las Cruces Trench Site model vali-datson efforts rd presents the INTRAVAL Phase Il vatidation NUREG/CR 5727: CHLORIDE lON DIFFUSION IN LOW WATER-TO-SOLID CEMENT PASTES. CLIFTON.J.R.; KNAB,LI.;

plans. The Phase il vahdation strategy is discussed in detail.

GARBOCZl,E.Ja et at National Institute of Standards & Tech-HUREG/CR 5717: PACKAGING SUPPLIER INSPECTION GUIDE.

nology (formerfy National Dureau of Standa. June 1991. 31pp.

STROMBERG,H.Ma GREGG.R Ed KIDO,Ca et al. EG&G Idaho, 0107080248. NISTIR 4540. 58308 185 j

!nc. (subs of EG&G, Inc.). May 1991,53pp. 9107010119, EGG-Diffus6on coefficients of 0.3 water to sohda rato (w/s) hydrat-j 2641. 58274:001.

ed portland coment paste specimens were measured using a 4

This document is a guide for conducting quauty assurance in-conventional diffusion cell Specimens were made from both

{

spuctions of transportation packaging suppliers, where suppliers ASTM Type I and Type ll portland cements and blends contain-are defined as designers, fabricators, distnbutors, users, or ing mineral admixtures (fty ash, granulated blastfurnace slag, or owners of transportation packaging. This document can be used silica fume). The average diffuMon coefficient for the portland dunng an inspection to determine regulatory compliance within coment paste specimens was 14x10(13) m(2)/s The diffusion the requirements of 10 Code of Federal Regulations, Part 71, coefficients for.the specimens con'aining mineral admixtures Subpart H (10 CFR 71.101-71.wS) The guidance described in were much more vanable than Inose for the portland cement this document provides a framework for an inspection. It pro.

paste specimons. A probable cause of the variability in the test vides the inspector with the flexibility to adapt the methods and results was the presence of cracks obsorved in the test spec:

concepts presented here to meet the needs of the particular fa.

mens, The effects of the depth of concrete cover over reinfore-cility being inspected The guide was deve!oped to ensure a ing steel and of the chloride ion diffusion coefficient on the structured and consistent approach for inspections. The method service life of reinforced cancrete exposed to chloride ions were treata each activity at a supplier facility as a separate entity (or predicted b? sed on a diffusion model Dased on the model, the functional element), and combines the activities within the effect of the cover was showri to be proportional to the square frarnework of an " inspection tree." The method separates each of the cover depth. A 10-fold decrease in the diffusion coeffi-functonal element into several areas of performance and then cient of concreta was predicted to result in a 10- fold increase identifies guidelirms, based on regulatory requirements, to be in the predicted service life. Based on the results of the present used to qualitatively rate each area. This document was devel-study, it is recommended that a new chloride diffuWty test oped to serve as a field manual to facilitate the worts of inspec-should be deweloped which is applicable to concrete.

t candi-tors.

date test method is proposed.

NUREG/CR 5721: VIDEO SYSTEMS FOR ALARM ASSESS.

NUREG/CR-5728: EXPERIMENTS TO INVESTIGATE THE MENT. GREENWOLL,0.Aa MATTER,J.C. Sandia National Lab-EFFECT OF FLIGHT PATH ON DIRECT CONTAllU 'ENT oratones. EDEL,P.E. BE, Inc. September 1991. 82pp.

HEATING (DCH) IN THE SURTSEY TEST FACILITY,The Limit-9110100260. SAND 91-0947. 53351:132.

ed Flight Path - (LFP) Teos. ALLEN,M.D4 PILCH,M.;

The purpose of this report is to present technictJ information NICHOLS.R.Ta et al Sandia National-Laboratones. October that should be useful to NRC licenwes in designing closed-cir.

1991,110pp. 91111102B2. SAND 91-1105. 59576$57.

cuit television systems for video alarm assessment. There is a The goal of the Umited Flight Path (LFP) test series was to section on each of the major components in a video system:

investigate the effect of reactor subcompartment flight path camera, lens, lighting, transmission, synchronization, switcher, length on direct containment heating (DCH). The tett senes monitor, and recorder. Each section includes information on consisted of eight expenments with nominal flight paths of 1,2, component selection, procurement, installation, test, and main-or 8 m. A thermitically generated mexture of iron, chromium. and tenance. Consideratons for eystem integration of the compo-alumina simulated the corium melt of a severe reactor accident.

i l

Maln Citations and Abstracts 43 After thermite ognition, superheated steam forcibly ejected the A new section,10 CFR 74.33, has been added to the matefi-molten debns into i t1D knear scale model of a dry raactor al control and eccounting (MC&A) requirements of 10 CFR Part cavity. The blowdown steam entrained the molten debnta and R This new section pertains to U.S. Nuclear Regulatory Com-dispersed it into the Surtsey vessel. The vessel pressure, gas mission (NRC) heensed uranium ennchment facihties that are tempeinture, debns temperature, hydrogen produced by steam /

authori.ed to produce and to pnssen more than one effecttve metal reactions, debns velocity, mass dispersed into the Eurtsey kilogram of special nuclear material (SNM) of low strategic sig-vessel, and debos particle size were measured to each experi-nificance. The new section is pattemed after 10 CFR 74.31, ment. The measured peak pressure for each expenment was which pertains to NRC hcensees (other than production or utab normahzed by the total amount of eriergy introduced into the zation facilities licensed pursuant to 10 CFR 4150 and waste Surtsey vessel; the normakzed pressures increased w:th length.

disposal facilities) that are authonzed to possess and use more ened flight path. The dobns temperature at the cavity crit was than one effective kilogram of unencapsulated GNM of low stra-about 2320 K. Gas grab samples Indicated that steam in the legic significance. Because ennchment facilities have the poten-cavity reacied rapidly to form hydrogen. so the dnving gas was tial capabihty of producing SNM of moderate strategic signifi-a mixture of steam and hydrogen. In thess expenments approxi-cance, and also strategic SNM, certain performance objectives mately 70% of the steam dnving gas was converted to hydro-and MC&A system capabilites are required in 10 CFR 74.33 in gen. The k;tal amount of hydrogen produced was a weak func-addition to those contained in 10 CFR 74.31. This document tion of the total debris mass dispersed into the Surtsey vessel, recommends to the NRC information that the licensee or apph-indicating that most of the steam / metal reactions occurred in cant should provide in the fundamental nuclear matenal control the reactor cavity.

plan. This document also describes methods that should be ac-NUREQ/CR 5729; MULTIVARIABLE MODELING OF PRESSURE ceptable for compliance with the general performance objec-VESSEL AND PIPING J-R DATA. EASON.E.D.; WRIGHT,J E.;

tives. While this document is intended to cover various urahium enrichment technologies, the primary focus at this time is gus NEL SON.E.E. Modeling & Computer Services. May 1991, 11Bpp. 9106120180. MCS 910401. 59063 227.

centnfugo and gaseous diffusion.

Mu!tivariable models were developed for predicting J R NUREG/CR 5737: HYDROGEOLOGIC PERFORMANCE AS-curves from available data, such as matenal chemistry, radiation SESSMENT ANALYSIS OF THE COMMERCIAL LOW LEVEL exposure temperature, and Charpy V notch energy. The RADIOACTIVE WAS1E DISPOSAL FACtLITY NEAR WEST present work involved collection of public test data, aoplication VALLEY,NEW YORK.

BERGERON,M P.:

SMOOT,J L:

of advanced pattom recognition tools, and catibration of im.

KEMNER M L; et al Battelle Memonal Instnute, Pacific Arth-proved multivadable models. Separate modeis were fitted for west Lrhoratory. June 1991,110pp. 9107010079. PNL-7688.

different matenal groups. including RPV weids, Linde 80 welds, 58248:196.

RPV base metals, piping welds, piping t)ase metals, and the A hydrogeologic performance assessment of the commercial combined database. Three different types of models were d6' low-level waste site near West Valley, New York, was per-veloped, involving different combinatiuns of vanables that might formed for two pathways: a shallow latoral pathway where be available for applications: a Charpy model, a pretriadiation trench water can.potentially migrate laterally through fractur.d Charpy model, and a copper. fluence model. In gener' the bast and weathered till to nearby streams and a deep vertical pain-resutts were obtained with the preirradiation Charpy tuodel. The way where teachate can migrate downward through unweath-copper fluence model is recommended only if Charpy data are ered till and laterary,offsite in a lacustnne unit. Along the shal-unavailable, and then only for Linde 80 welds. Relatively good low pathway, fittle physical site evidenco is available to indicate fits were obtained, capable of predicting the valuss of J for what the degree of lateral migration can be. Past modeling pressure vessel steels to within a standard doviation oi 13-18%

showed that overflowing trench water would migrate laterally over the range of test data. The models were quahtied for pre-some distance before migrating downward into the unweathered dictive purposes by demonstrating their abihty to predict valida' till Lf water did reach a nearoy stream, calculations show that tion data not used for fitting.

decay, adsorption, and stream dilution would reduce laachate NUREG/CR-5732 DRF FC: IODtNE CHEMICAL FORMS IN LWR concentration to acceptable levels. Within the deep pathway, SEVFRE ACCIDENTS. Draft Report For Comment. BEAHM.E.Ca Mtium and carbon-14 wore the onty radionuchdes released in WEBER,C Fa KRESS,T.S. Oak Ridge National Laboratory. July any significant concentrations. Prodicted tntium leve;a are well 1991,104pp.9107220272 ORNL/TM 11881. 58490.001, below regulatory limits; however, predicted peak C-14 concen-Calculated data from seven severe accident sequences in trations, while meeting tne 25 mrem /yr limit using the drinking-hght water reactor plants were used to assess the chemical water only exposuie scerario, exceed the limit for full garden forms of iodine in containment. In most of the calculations for scenario. Site information on C 14 ruease rates and geochemi-the seven sequences, iodine entenng containment from the re-cat behavior has considerable uncertainty and would need to be actor coolant system was almost enttrely in the form of Csl with more futty Neluated in a keensing situation.

very small contnbutions of I or Hl. The largest fraction of iodine in forms other than Csl was a total of 3 2% as I plus HI Within the containment, the Csl will deposit onto walls and other sur, S

-6 4 M M faces, as well as in water pools, largely in the form of iodide (1.)

REFERENCE DATA. TRUBEY,D.K. Oak Ridge National Labora-The radiation-induced conversion of I-in water poota into l(2) is tory. August 1991,152pp. 9108290255. ORNL/RSIC-49/R1.

strangfy dependent on pH. In systems where the pH was con-trolled above 7, httle additional elemental iodine would be pro-ican Nuclear Society Standards Committee Working duced in the containment atmosphere. When the pH fails below Group, identified as ANS 6.4.3, has developed a set of eva'uht-

, it may be assumed that it is not being controlled arid large ed gamma-ray isotropic point-source buildup factors and attenu-facti s o todme as 1(2) within the containmer" atmosphere ation cnefficients for a standard reference data base. The large ty unpubhshed set of buildup factors calculated with the mo-ments method has been evaluated by recalculating key values NUREG/CR-5734: RECOMMENDATIONS TO THE NRC ON AC-with Monte Carlo, integral transport, and discrete ordinates CEPTABLE STANDARD FORMAT AND CONTENT FOR THE methods. Additional buildup factor data were obtained from FUNDAMENTAL NUCLEAR MATERIAL CONTROL (FNMC)

PALLAS code results. Attention has been given to frequently-PLAN REQUIRED FOR LOW ENRICHED URANIUM ENRICH-neglected processes such as bremsstrahlung and the effect of MFNT FACILITIES. MORAN,8.W.; BELEW W.L. Oak Ridge K 25 introducing a tissue phantom behind the shield. The proposed Site. HAMMOND.G.Aa et al. 21st Century Industnes, Inc. No-draft standard, provided as an appendix, contains data for a vember 1991. 53pp. 9201060264. K/ITP 415. 60201.001.

scurce energy range from 15 kev to 15 MeV and for 22 ele-l I

44 Main Citations and Abstracts ments and 3 mirtures (water. air, and concrete) The buildup of the wall. Anneakng studies It'dicate complete recovery from factor data are also represented as coefficients for the G P fit-embrittlement efter 1 h at 40) degrees C (752 degrees F). Al-ting function. Tables giving correction factors for multiple scat-though the weld metal is significantly tougher than the base tering in tissue are also provided metal, the shifts in CTT are comparable The shifts in CTT for NUREG/CR-5742 V01: FEASIBILITY ASSESSMENT OF A RISK-the Shippingport NST are consistent with the test and Army re-BASED APPROACH TO TECHVCAL actor data for irradiations at <232 degr ss C Ic450 degrees F)

SPECIFICATIONS Executive Summary.

ATEFI,B.,

and show very good agreement with th isults for HFIR A212 GALLAGHER.D W. Science Appocations Imernational Corp. (for B steel irradiated in the Oak Ridge Research Reactor (ORR).

merly Scienco Appheabons. Inc ). May 1991 12pp 9106180006, The ettects of irradiabon temporature, tluence rate, and neutron SAIC-90/1400. 58130:129.

flux spectrum are discussed. The results Indicate that fluence The first phase of the ast*issment concentrates on (1) identi-rate has no effect on radiation embrittlement at rates a3 low as f6 cation of selected nsk-based opproaches for improving current 2 x 10(B) n/cm(2) s and at the low operating temperstares o technical specifications, (2) appraisal of characteristics of each the Shippingport NST. le., 55 degrees C (130 degrees F). This approach, including advantages and disadvantages, and (3) rec-suggesta that the accelerated embrialement of HFIR surveil-omrnendabon of one or more approaches that might result in lance samples IS most likely due to the relatively higher propor-improving current technical specifict. tion requirements. The tion of thermal neutrons in the HFIP spectrum compared to that Second phase of the work concentrates on anaessment of the for the test reactors.

feas4bility of implementation of a pilot program to study detailed NUREQ/CR-5749: TECTONIC DEFORNATION REVEALED IN characteristics of the preferred approach. The real time risk.

BALDCYPRESS TREES AT REELFOOT LAKE. TENNESSEE.

band approach was identified as the preferred appros;h to echnical spsfimor$ fcs controlhng plant operational nsk.

VANARSDALE,R.; STAHLE.D.; CLEAVELAND.M. Arkansas, Ihto do not appear 40 he my toc % cal or institutional obsta-Univ. of, Fayetteville, AR. July 1991. 19pp. 9107220288.

gg4gg g.

cles to pre /ent initiation of a pilot program to assess the char.

1 ana yses of baldcypress (Taxodium distichum) from Tu-s actenshc6 and effect+ern ht su.h en approach.

Reelfoot Lake, Tennessee, supp;t histoncal accounts that the NUREC/CR-5742 V0t FEASIBluTY ASSESSMENT OF A RISK-lake formed dunng the great New Madnd carthquakes in 181b BASED APPROACH TO TECHN!CAi, SPECIFICATIONS 1tain 1812. Due to ground subsidence and permanent flooding, all of Report. ATEFIA; GALLAGHETOW Science Apphcatons the bottomland hardwood trees within the impounded area were Intemational Corp. (formerly Science Apphcatiors Inc.) May killed. However, many water tolerant baldcypress survived, and 1991,84pp. 9106180007. SAIC 90"400. 58130 043.

hundreds of 200 to 800 years old baldcypress outhne the posi-See NUREG/CR 5742,V01 abstract.

tions of former stream channels drowned by the subsidence, NUREQ/CR-5743: APPROACHES TO LARGE SCALE UNSATU.

Dendrochronological analyses of multiple cores from 21 baldcy-RATED FLOW IN HETEROGENEOUS, STRATIFIED, AND

' press in the taxe reveal several pronounced growth responses FRACTURED GEOLOGC MEDIA, ABABOU,R. Center for Nu.

to the 1811 1812 earthquakes. These responses include a great clear Waste Regulatory Analyses. August 199i 160pp surge in radial growth during the decade following the earth-9110090320. 59332:045, quakes and a permanent reduction in wood density beginning in This report develops a broad review and assessment of quan.

1812. These anr1 other growth responses to the 1811-1812 titative modehng approaches and data requirements for large.

earthquakes may allow us to determine if there have been other scale sub"urface flow in a radioactive waste geologic repository large earthquakes in the Reetfoot basin during the late Holo-The data review includes discussions of controlled field experi.

cene and may help date the formation of other suspected sunk ments, existing contamination sites, and site. spec!!ic hydrogoo-lands in the New Madrid seismic zone.

logic conditions at Licca Mountain. Local-scale constitutive models for the unsaturated hydrodynamic prrioerties of geolog,,

NUREG/CR 5757: VERIFICATION OF PIPING RESPONSE CAL-media are analyzed, with particular emphasis on the effect of CULATION OF SMACS CODE WITH DATA FROM SEISMIC structural charactenstics of the medium. The report further re, TESTING OF

.AN IN-PLANT PIPING SYSTEM.

views and analyzes larDe-scale hydrogeologic spatial variabihty SRINIVASAN,M.G.; KOT,C.A_; HSIEH B.J. Argonne Nation (

from aquifer data, unsaturated soil data, and fracture network Laboratory. September 1991. 207pp. 9110090275. ANL-91/25.

data gathered from the hierature. Finally, various modeling strat-233MOE egies toward targe-scale flow simulatons are assessed, includ-The objective of this effort was to evaluate the poing andysis ing direct high-resolution simulation, and coarse-scale simulahon part of the SMACS code for estmahng the response of reahstic based on auxihary hydrodynamic models such as singie equiva, piping systems subjected to multplo independent support accel-lent continuum end dual-porosity continuum. The roles of anisot-erations. Test data from the expenments on an 6n-plant piping ropy, fractunng, and broad bsod spatial variability are empha.

system were usad for this purpose. Two support configurations sized.

were selected 'or the sva!uation: one a ' stiff' configuration con-taining both t'tr.its and snubbers, and the other,1 more flexible NUREG/CR-5748: RADIATION EMBRITTLEMENT OF THE NEU-configuration we no snubbers. Desenbed are the analytical TRON SHIELD TANK FROM THE SHIPPINGPORT REACTOR.

modehng, calcuiatus, and resuts of the posttest simulation of CHOPRA,0? ' SHACK,W.J. Argonne National Laboratory.

two tests each for both support configurations. Almost all the ROSINSKI.5 Sandia 'Nabonal Laboratories October 1991.

calculated peak response quantities were smaller than the cor-47pp. 9111070090. ANL-91/23. 59549:025.

responding test measurements. Howeveri pipe displacements Tiie irradiation embnttlement of Shipp;ngport neutron shield end bending s'resses were better estimated than the pipe ac-tank (NST) matenal (A212 0) has been charactenzed. Irradiation celerations and suppc,t forces. The discrepancies are mainty at-increases the Charpy transition temperature (CTT) by 23-28 de-tnbutable to the inabihty of the linear analysis to model 'he non-grees C (4150 degrees F) and decreases the upper. shelf hnear behavior of the piping system.

energy. The shift in CTT is not as severe as that observed in high-flux isotope reactor (HFIR) surveillance samples. However -

NUREG/CR-5758 V01: FITNESS FOR DUTY IN THE NUCLEAR the actual value of the CTT is higher than that for the HFIR POWER INDUSTRY. Annual Summary Of Program Performance data. The increase in yield stress is 51 MPa (7,4 ksi), which is Reports,CY 1990. DURBIN,N.; MURPHY,S : FLEMING,T ; et al.

comparable to HFIR data. The NST matenal is weaker in the Battelle Human Affairs Research Centers August 1991, 67pp, transverse than in the long:tudinal onentation. Some effects of 9109050292. PNL-7736. 58988 ?30.

position across t*ie thickness of the wall are also observed; the This report summarizes the data from the semiarcual reports CTT shift is shghtly greater for specimens from the inner region on fitness-for duty pre grams submitted to the NRC by 54 utilKus l

l I

Main Citations and Abstracts 45 for two reporting penods: Anuary 3,1990. to June 30, 1990, the AFW syuem at the selectec' olants Callaway w: selected and from July 1,1990, to December 31,1990. Dunr:g CY 1990 as the eleventh plant for *tudy 1ht' product of this effort is a licensees reported that they conducted 278.209 tests for the f riontizet.i sitting of AFW failures which have occuned at the presence of illegal drugs and alcohol. Of these tests, 2,409 plant and at other PWRs. This listing is intended for use by 187%) were postive. Positive test resetts varied by category of NRC inspectors in the preparation of inspection plans address-test and category of worker. The majonty of positive test results ing AFW risk-important components at the Callaway plant.

(1.548) were obtained through pre access testing Of tests con-ducted on workers having access to the protected area, thore NURf.0/CR-5764: AUXILIARY FEEDWATER SYSTEM RISK-were 550 positwa tests from ranuom testing and 214 positrve BASED INSPECTION GUIDE FOR THE GINNA NUCLEAR tests from for-cause testirg Followup testing of workers who POWER PLANT. PUGH.R.; GORE,0.F.; VO T.V.: et al. Battelle had previously tested positive respited in 65 positive tests. Posi.

Memonal instituto, Pacvic Northwest Laboratory. September tive test results also varied by category of worker. Overall, 1991. 36pp. 91101002v 'NL-7594. 59336:307.

shott term and long-term contractor pert.onnel had the highest in a study sNnsored by the U S. Nuclear Regulatory Com-rates of positive tests. Licensee employees had lower rates of mission (NRC), Pacific Northwest Laboratory has developed and positNs test results.

applied a methodoiogy for deriving plan %pecific nsk based in-spection guidance for the auxiltary feertwater (AFW) system at NUREG/CR-5760: REPORT ON ANNEALING OF THE NOVO-pressu zed water reactors that have not undergone probabilistic e

VORONEZH UNIT 3 REACTOR VESSEL IN THE USSR.

nsk asoessment (PRA). This methodology uses ewing PRA re-COLE.N M ; FRIDERICHS,T, MPR Associates, Inc. Jufy 1991.

sults and plant oporating expenence information. Existing PRA-7Bpp. 9108130307. MPR 1230. 58765.308-based inspection guidance information recentty developed for A U S delegation attended the thermal annealirvj operation of the NRC for various plants was used to identify generic compo-the Novovoronezh Unit 3 reactor vessel in the USSR to evalu-nent failuie modes. This information was then combined with ato the Soviet reactor vessel snnealing technology and to deter-plant-specific and industry-wide component information and fail-mine its applicabihty to PWR reactors in the U.S. Operations ob-ure data to identify failure modes and failure mechanisms for served and described in this report include reactor vessel the AFW system at the selected plants. Ginna was selected as sample cuiting, piparations for annealing, installation of an-the eighth plant for study. The product of this effort is a piori-nealing apparaius. and initial heatup of the reactor vessot. The tizoo listirig of AFW failures which have occurred at the plant anneahng operation witnesced has been developed to a routine arid at other PWRs. This listing is intended for use by NRC in-operation and appears applicable to U.S PWRs. Key a'eas re-spectors in the preparation of inspection plans addressing AFW quinng further work to confirm applicabilRy to U.S reactors are nek important components at the Ginna plant.

discussM NUREG/CR-5761: AUXlLIARY FEEDWATER SYSTEM RISK, NUREG/CR 5765: SPARC-90. A CODfi FOR CALCULATING FIS.

BASED INSPECTION GUIDE FOR THE SALEM NUCLEAR SiON PRODUCT CAPTURE IN SUPPRESSION r'OOLS.

POWER PLANT. PUGH.R4 GORE,B,Fa VO,T.V. Battello Memo.

OWC 2ARSKI,P.C.; BURK,K W. Batte!!e Memorial Institute, Pa-rial Insttute. Pacific Northwest Lab statory. August 1991. 34pp.

cific Northwest Laboratory. October 1991. 04pp. 920106000A 9109050280. PNL-7518. 58088:336.

PNL-7723. 60197:00 t in a study sponsored by the U.S. Nuclear Regulatory Com, This report desenbes the technical bases and use of two, up-mission (NRC), Pacific Northwest Laboratory has dueloped and dated versions of a compute, code initially developed to serve applied a methodoingy for denving plant-specific nsk-based in.

as a tool for calculating aerosol particle retention in boiling spection guidarce for the auxiliary feedwater (AFW) system at water reactor pressure suppression pools during severe acci-pressunzed water reactors that have not undergone probabilistic dents. SPARC-87 and SPARC-90. The most recent version.t risk assessmunt (PRA). This methodology uses ersting PRA re-SPARC 90. The initial or prototype version (Owczarskl Postma, suits and plant operating axpenence information. Existing PRA.

and Schreck 1%) was improved to include the following: rigor-based inspection guidance information recently developed for ous treatment of local particle deposition velocities on the sur-the NRC for vanous plants was Jsed to identify genenc compo, face of oblate spherical bubbles, new correlahons for hydrody.

nent failure rr, odes. This information was then combined with namic behavior of bubble swarms, models for derosol partich plant specific and industry-wide component information and sail-growth, both mechanistic and empirical models foi vent ent ute data to identify failure modes and failure mechanisms for region scrubbing, specific models for hydrodynamics of bubble the AFW system at the selected plants Salem was selected as breakup at vanous vent types, and models br capture of vapor the fifth plant for study. The product of this effort is a prioritized lodine species. A complete user's pmde is provided for SPARC-listing of AFW failures which have occurred at the plant and at 90 (along with SPARC-87). A code description, code operating other PWRs. This fisting is intended for use by NRC inspectors instructions, partial code listing, examples of the use of SPARC-in the preparation of inspection plans addressing AFW nsk-im.

90, and summanes of expenmenisi data comparison studies portant components at the Salem plant.

also support the use of SPARC 90.

NUREG/CR 5763: AUXILIARY FEEDWATER SYS TEM RISK.

NUREG/CR-5767: THE BEHAVIOR OF SHALLOW FLAWS IN BASED INSPECTION GUIDE FOR THE CALLAWAY NUCLEAR REACTOR PRESSURE VESSELSc ROLFE S.T. Kansas, Univ.

POWER PLANT. MOFFITTftE.; GORE BJ.; VO,T.V. Battelle of, Lawrence. KS.

• Oak Ridge National Laboratory. November Memorial 'nstitute, Pacific Northwest t.aboratory. August 1991.

1991.35pp.9201060092, ORNLSUB90SH6401. 60197:084.

34pp. 9109050285. PNL-7725 $8988:300.

The objective of this report is to recommend those research in a study spot'sored by the U.S. Nuc' ear Re0ulatory Com.

Investigations that are necessary to unt.:erstand the phenome-mission (NRC), Pacific Northwest Laboratory has developed and non of saallow behavior e s it affects fracture toughness so that applied a methodology for deriving plant specific risk based in-the results can be used properly in the structural margin assess-spection guidance for the auxilia'y feedwater (AFW) system at ment of reactor pressure vessels (RPVs) with flaws. Prelim. nary pressurized water reactors that have not undergone probabilistic test results of A 533 B steel show an elevated crack-tip opening nsk assessment (PRA). This methodology uses existing PRA re-displacement toughness similar to that observed for structural suits and plant operating experience information. Existing PRA-steels tested at the University of Kansas. Thus, the inherent re-based inspection guidance information recently developed for sistance to fracture initiation of A 533 B steel with shallow flaws the NRC for various plants was used to identify genenc compo-appears to be higher than that used in tha current Amencan So-nent failure medes. This information was then com"ned with ciety of Mechanical Engineers design curves based on testing plant 4pecific and industry wide component information and fail.

fracture-mechanics specimens with deeo flaws. If this higher ure data to identhy failure modes and failure mechanisms for toughness of laboratory specimens with shallow flaws can be l

46 Main Citations and Abstracts l

transferred to a higher resistance to failure in RPV design of nistic representation of radionaclide release from a dispose fa-analysis, then the actual margin of safety in nuclear vessels cihty. Typbally, a number of assumptions, based on knowledge with shallow flaws would be greater than is currentiv assumed of the disposal system, are used to simplify the problem. This on the basis of deep flaw test results. This report reviews those document pravides a bnet overview of disposal practices and factors and makes recommendabons of studies that are needed reviet s existing source term models as background for select-to assess the transferability of shallow-flaw toughness test re-ing appropna'e models for estimating the source term The se-suits to the structural margin assessment of RPV with shallow lection rationale and the mathematical details of the mcdels are flaws.

presented Finalty, guidance is presented for combertino the in-

i WUREG/CR-5768: ICE CONDENSER AEROSOL TESTS.

ventory data with appropnate rnechanisms describing release LIGOlKE.M.W; ESCH8ACH E.J.; WINEGARDNER,W. Battelle fr m the disposal facility.

Memonal Institute, Pacifc Northwest Laboratory. September NUREG/CR 5777; GLOBAL POSITIONING SYSTEM MEASt>RE-1991, 390pp. 9110100238. PNL 7765. 59334:117.

MENTS OVER A STRAIN MONITORING NETWORK IN THE This report presents the results of an expenmental inveshga.

EASTERN TWO-THIROS OF THE UNITED STATES.

tion of aerosol part;cto transport and capture using a full-scale STRANGE.WE Commerce, Dept. of, flatmnal Oceanic & At.

height and veduced scale cross section test facility based on mospheric Administration. September 1991, 34pp. 9110000418.

the design of the ice compartment of a pressunzed water reac 59313.310.

for (PWR) ice-condenser containment system. Results of 38 A 45 station geodetic network was esteblished in 1967 using tests included thermal-hydrauhc as well as aerosol particle data ~

global positionhg system (GPS) technology to provide a means Particle retontion in the test section was greatty influenced by of monitonng strain and deformation in the contal and eastern thermal-hydrauhc and aerosol test parameters. Test-ever3ge de-United States. Fsaduction of the initial epoch data showed thet contamination factor (DF) ranged between 10 and 36 (reten-tions between NO and 97,2%UThe treasured test. average parti-accuracies of 1 to 3 cm can be achievea for honzontal position, provided sufficient observations are available and there are four cle retentions for tests without and with ice and steam ranged between DF = 1.0 and 2.2 and DF = 2.4 and 36, respectively.

or more fiducial stations whose positions are known.a pnori, for in order of apparent importance, parameters that caused part" example from Very Long Base!ine interferometry measure-cle setention in the test section in the presence of ice were ments. Accuracies obtained provide the abit,ty to determine steam mole fraction (SMF), noncondensible gas flow rate (resi-

2. train at the 1:10(7) to 1:10(8) levet Vertical positions arer less dence time), particle solubdity, and inlot particlo size. Ice-basket accurate bec ause of problems in modeling refraction and are section normondensible flows greater than 03 m(3)/s resulted determined at tho 5 to 7 cm level it is planned to remeasure m stable thermal stratificaten whereas flows less than 0.1 m(3)/

W neMM at reg'Aar intervals In the coming years to place a resulted in thermal behavior termed meandering with frequent bounds on the strain occurring in the central and eastern United temperature t'rossovers bet'seen flow channels.

States. This network is also expected to serve as a reference network for more detailed monitoring networks in areas of high NUREG/CR 5771: PROBABILITY AND CONSEQUENCES OF nsk such as the New Madnd area. Future measurements are MISLOADING FUEL IN A PWR. DIAMCND D.J4 HSU,C,J.;

expected to provide more accurate results because of in-MUBAYI,V. Brookhavon National Laboratory. August 1991.

creased numbers of GPS satellites available and improved com-74pp.9110090313. BNL-NUREG-52294, 59331:331, putahon software The improved software will also allow future This report documents the results of a study Into the frequen..

upgrading of the accuracy of the 1987 observations.

cy and consequences of mistoading fresh fuel assemMies dunng the reloadino of a pressurized water reactor. The conse.

. NUREG/CR-5778 V01: NEW YORK /NEW JERSEY REGIONAL quences that were considered included. (i) loss of required shut, SEISMIC NETWORK. Annual Report For April 1989 - March down margin, (ii) inadvertent criticahty, and (iii) worker exposure 1990. SEEBER.L; SIMPSON,D.; JOHNSON,D.; et al. Lamont-within the plant given knaivertant criticahty. Neutronic calcula-Doherty Guogical Observatory. September-1991. (3pp.

tions were parformed for different patterns of fresh fuel clus.

9110080413. 59311 213.

tered together In a Combustion Engineering reactor. The fresh Lamont-Doherty Geological Observatory (L DGO) continued fuel considered had a high U-235 content and was assumed to operating a 314tation sersmic network covering parts of New be loaded without control element assemblies. The frequencies York and New Jersey. The network is being transformed into of.ntsloading fresh ftet assembhes into these clustered pat, sub-networks with stations radio telemetered to " smart" record-terns were calculated taking into account operator errors and ing stations. The sub-network approach is capable of providing equipment malfunctions that could occur during an offload /

improved data at reduced cost. The maior research effort during reload sequence The study has improved our underbtanding of the period of th4 report was centered about the Saguenay how difficult it is to misioad fuel and has quantified the loss of earthouake sequence in Quebec, L DGO cullaborated with the shutdown margin and the frequencv of occurrence for specific Canadian Geologic Survey in monitonng aftershocks whh tem-mistoadings as well as the doses that might result from an inad.

porary local stations. Analysis of data from the 1985 Ardsley vertent enticahty.

earthquake in Westchester county continued with a Green's function deconvolution approach to resolve the dimensions of NUGEG/CR 5773: SELECTION OF MODELS TO CALCULATE the rupture of the main shock (Mb=4.0) and of the largest THE LLW SOURCE TERM. SULLIV AN,T.M. Brookhaven Nation-aftershock (Mb=3.0). The results corroborate the 1/2-1 km di-at Laboratory. October 1991, 81pp. 9111070095. BNL NUREG-52?95, 59549.073-ameter interred for the rupture and suggest that the segmenta-tion of the Dobbs Ferry fault and of similar faults in the Manhat-Fertormance assessnwnt of a LLW disposal facihty begins tan Prong may be controthng the size of historic earthquakes in with an estimation of the rate at which radionuclides migrate out the New York City regiort Finalty, a portable seismograph of the facility (i.e., source term). The focus of his work is to de*

survey was camed out in Palco, Kansas, which showed clearly volco a methodology for calculating the source term. In general, that seismicity at Palco was induced. -

the source term is in luenced by the radionuclide inventory, the -

wastetorms and containers used to dispose of the inventory, NUREG/CR 6780:

SUMMARY

OF A WORKSHOP ON SEVERE and the physical processes that lead to release from the facihty ACCIDENT MANA'3EMENT FOR BWRS. KASTENBERG.WI; (fluid flow, container degradation, wasteform leaching, and raft APOSTOLAKIS,G4 JAE.M.: et al. Califomia. Univ. of, Los Ange-onuclide transport). In turn, many of these physical processes les< CA. November 1991. 62pp. 9201060094. 60197;121.

are influenced by the design of the disposal facihty (e.g., intittra-Severe accident management can be defined as the use of tion of water) The complexity of the problem and the absence existing and/or alternative resources, systems and actions to of appropnate data prevent development of an entirely mecha-prevent or mitigate a core-melt accident For each accident se-I

i Main Citabons and Abstracts 47 quence and each combination of strategies there may be sever.

ed that for wastes buried below the fractured b!I Zone, no signift-a; options available to the operator; and each invnives phenom-cant migration would occur. However, under the assumed con-enological and operational considerations regarding uncertainty, ditions, significant latera! migration could occur for radionuclides Operatonal uncertainties include operator, system and instru-present in the upper, fractured till zone.

ment behavior dunng an accidert. Durity; the penod September 26-28. 1990, a workshop was held at the University of Califor.

NUREG/CR-5795: VALIDATION AND TESTING OF THE VAM2D t'a. Los Angeles, to address these uncertaintics for Boshng COMPUTER CODE. KOOLJ B.; WU,Y.S. HydroGerLogic, Inc.

Water Reactors This report contains a summary of the work-October 1991,120pp. 9201060183. 60207:315.

shop proceedings.

VAM2D is a two-oimensional, varably saturated flow and

[

NUREG/CR-5781:

SUMMARY

OF A WORKSHOP ON SEVERE w e ds sal s d es t ed in re i

ACCIDENT MANAGEMENT FOR PWRS, KASTENBERG,W E.;

volve application of the VAM2D code to two diverse subsurface APOSTOLAKIS.G.; JAE.M., et al. California, Univ. of. Los Ange' modehng problems. The first one involves modeling of infJua-les, CA. November 1991.61pp.9201060242.60195:168-tion and redistribution of water and solutes in an initiauy dry, Sevare accident management can be defined as the use of heterogeneous field soil. This apphcation invdves detailed mod-exishng and/or alternative resources, systems and actions to eling over a relatively short. 9-month period. The second prob-prevent or mitigate a core-melt accident. For each accident se-lem pertahs to the apf'lication of VAM20 to the modehng of a quence and each combination of strategy, there may be several waste disposal facihtv in a fracture 6 clay, over much larger options available to the operator; and each involves phenome-space and time scales and with particular emphasis on the ap-nological and operational considerations regarding uncertainty, phcabihty and rehabihty of using the equivalent porous medium f

Ooerahonal uncertainty includes operator, system and instru-approach for simulahng flow and transport in fractured geologic ment behavior dunng severe uccidents Dunng the period May media' 15-17, 1990, a workshop was held at the tiniversity of Cahfor.

nia, Los Angeles, to address these uncertaintres for pressunzed NUREG/CR-5796:

STEAM GENERATOR OPERATING water reactors. Tnis report contains a summary of the workshop EXPERIENCE. UPDATE FOR 1989-1990. FRANK,L Viking Sys-proceedings-tems international. December 1991, 124pp. 9201060109, NUREG/CR-5784: FITNESS FOR DUTY IN THE NUCLEAR 60198:146.

POWER INDt'STRY.A Review Of The First Year Of Program This report summenzes operational events and degrg"fation Performance And An Update Of The Techrucal issues.

mechanisms affecting pressurized water reactor stearn genera-DURBIN,N.; MOORE,C.; GRANT,T.; et at Battelle Human Af-tot integnty, it provides: (1) results of 1989 and 1990 steam fairs Research Centers. September 1991.199pp. 9110100248.

generatot Wections; (2) highhghts prevalent problem areas; PNL-7795. 59335:239.

(3) improvements tiet have been mado in nondestructive test.

This report presents an overview of the NRC heensees' im-ing methods; (4) prevents measures; (5) repair techniques; piementation of the FFD program dunng the first full year of the and (6) replacemert procedures. :t desenbes the equipment of program's operation and provides new information on a variety the three (3) major suppliers and discues recent examinations of FFD technical issues. The purpose of this document is to of 76 plants. Major areas of concem tire tre steam generator contnbute to appr pnate changes to the rule, to the inspecbon degradation mechanisms that affect tube integrity w aause tube process, and to other NRC actmties. It desenbes the charactor, leakage and tube failure. These include: (1) intergranular Mck; istics of heensee programs, discusses the results of NRC in.

(2) lotergranular stress corrosion cracking; (3) pnmary watei spectons, updates technical information covered in previous re Stress corrosion cracking; (4) pitting; and (5) vibrational wear ports, and identifies lessons tearned during the first year. Over, and fat gue. Also discussed are plugging, sloeving, heat treat-all, the experience of the first full year of licensees' FFD pro, mert, peening, chemical cleanirg and steem generator replace, gram operations indicates that licensees have funcboning fit, ments. The current status of regulatory instruments and inspec-ness-for-duty programs devoted to the NRC rute's performance tion guidelines for ensuring the steam generator integnty, is dis-objectives of achieving drug *ee workplaces.n which nuclear cussed with the rwghlights of steam generator research. New power plant personnel are not impaired as they perform ineir potential safety issAs such as circumferential cracking and duties.

tube plug cracking are also discussed.

NUREG/CR-5794: GROUND-WATER FLOW AND TRANSPORT NUREG/CR-5798: PILOT PF7 GRAM TO ASSESS PROPOSED MODELING OF THE NRC-LICENSED WASTE DISPOSAL FA-BASIC OUALITY ASSURANCE REOulREMENTS IN THE MED-CILITY, WEST VALLEY, NEW YORK. KOOL,J.B.; WU,Y.S. Hy-l CAL USE OF BYPRODUCT - MATERIAL KAPLAN,E.;

droGeologic, Inc. October 1991.

128pp. 0201060238.

NELSON,K.; MEINHOLD C.B. Brockhaven National Laboratory.

60194:294.

October 1991. 73pp. 9110230323. ' BNL-NUREG-52303.

This report dosenbes a simulation study of groundwater flow 59455:273.

and radionuclide transport from disposal pits at Me NRC li.

In January 1990, the Nuclear Regulatory Commission (NRC) censed waste disposal facihty in West Valley, New Yoric A tran-proposed amendments to 10 CFR Part 35 that would require sient, precipitation dnven, flow model of the near surface trac.

medical licensees using byproduct material to estabhsh and im-tured bli layer and undertying unweathered till was developed piernent a basic quality acsurance program. A 60-day real-world and calibrated agninst observed inflow data into a recently con--

trial of the proposed rules was initiated to obtain information structed interceptor trench for the period March May,1990.

beyond that generally found through standard public comment The results suggest that lateral flow through the upper, frac-procedures. Volunteers from randomly selected institutions had tured till layer may be more significant than indicated by previ-opportunities to review the tjetails of the proposed t4 ations t

ous, steady state flow modeling studies. A conclusive assess-and to implement these rules on a daily basis dunng the trial, ment of the actual magnitude of lateral flow through the trac-The participating institutions were then asked to evaluate the tured til could, however, not be made. A primary factor contnb-proposed regulations based on their personal experiences. The utng to this uncertainty is the unknown contnbution of vertical pilot project sought to determine whether medical institutions infiltration through the interceptor trench cap to the total trench could develop written quality assurance programs that would inflow. The second part of the investigation involved simulation meet the eight performance-based objectives of proposed Sec-of the migrat:on of Sr-90, Cs 137 and Pu-219 from the one of tion 35.35. It was found that hcensees could develop accepta-the fuel hull disposal pits. A first order radionuclide leach rate ble OA programs under a performance-based approach, that with rate coehent c? 10( 6)/ day was assumed to describe re-most heensee programs did meet the proposed objectives, and dionuclide release into the disposal pit. The simulations indicat-that most wntten OA plans would require consultattons with

48 Main Citations and Abstracts NRC or A 'oement State personnet before they would fully temperature range The major vanables investigw.ed included 0

meet ail ablect;ves of proposed Section 35 35 This report de-(1) heating rate; (2) peak temperature, (1) holding time at peak senbes the overall pilot program. The methodology used to temperature; and g4) cooling rate Chango in sensitization was wicct and assemtJe the group of participating hcensees is pre-tracmed using the electrochemical potenokinetic reactivaton sented.

(EPR) test. Continuous heating / cooling cycles were performed NUREG/CR 5608: CALCULATION OF ABSORBED DOSES TO using a ace or usmg a thermal cyde sWaton n'amne WATER POOLS IN SEVERE ACCIDENT SEQUENCES.

(Gleeble) Sonsitization was found to increase with increasing WEBEP,CE Oak Ridge National Laboratory. December 1991.

peak temperature until a "cnticar peak temperature was 49pp OC01090205. ORNL/TM-11970. 60243.266.

renched Sensitization was very low for all samples heated A nuthodology is presented for calculating the radiation dote above this entical peak temperature. The entical peak tempera-3 in that pool Motivated by the rad to accurately model radioly.

to a water pool from the decay of uniformly distnbuted nuchdes ture was 900 degreet C for high-carbon (0 06 wt%) 304 and vaned from 950 to 1000 degrees C for hsgh carbon (0 06 wt%)

sis reactions of iodine, direct apphcation is rime to fission prod, 316 SS. Sarmt ation increased with decreasing cooling rate uct sources dissolved or suspended in containment sumps or and appeared to decrease with increasing heating rate. The pools dunng a severe nuclear reactor accident. Two methods cf slowest heating rete used was equal to the fastest cooling rate calculating gamma absorption are discussed one based on tested. Results are discussed in terms of grain boundary chro-r' nt-kernel integration and tho other based on Monte Carlo mium carb@ nucleaton and precipitaten, and chromiuni deple-

'echalques. Using least-squares min nization, the cornputed re.

sults are used to obtain a correlation that relates absoted dose NUREu/GR-0003: EFFECT OF PRIOR DEFORMATION ON SEN-to source energy and sudace to-volume ratio ci the pool. This SI'lTATION CEVELOPMENT IN STAINLESS STEEL DURING correlation is appbed to most relevant fission product nuclides CONTINUOUS COOLING. SIMMONS.J W.; ATTERIDGE,0.G.;

and used to actually calculate transient sump dose rate in a BRUEMMER.S.M. Oregon Graduate Inst 4tute of Science &

pressunzed-water-reactor severe accident sequence =

Technology, Beaverton, OR.

September 1991. 109pp.

NUREG/CR 5809 DRF FC: AN INTEGRATED STRUCTURE AND 9110150279.59362:172.

SCALING METHODOLOGY FOR SEVERE ACC) DENT TECHNI.

Hig4 carbon Type 316 stainless steel (SS) specimens wero CAL ISSUE RESOLUTION Draft Report For Comment.

subjected to knear continuous cookng in a comger controlled DOYACK,B E.; HENRY,P.E.; MOODY,F.J.; et al. EG&G Idaho, Gleeble thermal simu4 tor. The degree of sensitization (DOS)

Inc (subs. M EG&G, inC L November 1991. 678pp.

was quantitatively rneasured using the electrochemical potentio-9201060161. EGG-26H. 60205:117.

kinetic reactivation (EPR) test. Sensitization values for the ther.

Recognizing the ce%al importance of severe accident scal.

mal cycles employed in the investigation were predicted using ing issues, the Unned States N41 ear Regulatory Commission Bruemmer's SSDOS sensitization prediction model Prior defor-implemented a Severe Accident Scaling Methodology develop.

mation significantty enhanced the rate of DOS development in ment program involving a lead laboratory contractor and a the Type 316 SS material. The DOS increased with increasing Technical Program Group tn guide the development and to amounts of prior strain and decreasing cooling rates. Sensitira-domonstrate its practicahty via a challenging application. The tion response was also sensitive to peak cycle temperatures Technical r m Group recognized that the Severe Accident Continuous cooling sensituation development occurred pnmarily Ecahng Met +.Jogy was an integrai part of a larger structure

'n the critical temperature range between about 900 and 750 for technical usue resolution and, therefore, found the need to degrees C. Peak cycle temperatures above 1000 retarded sen-define and docutnent this larger structure. The Integrated Strue.

sitization development dunng subsequent continuous cooling.

ture for Technical issue Resolution objectives at a process are Strain recovery at elevated temperatures played en important descnbed in this document. The objectwes of the Severe Acci.

role in reducing the effect:veness of prior deformation in accel-dent Scaling Methodology are to (a) provide a scaling methodot.

erating sensitization kinetics. Due to the effects of recovery, in ogy that is systematic and practical, auditable and traceable, (b) _

certain cases, pnor strain values of 20% were only as effective provide the scahng rationale and similanty enteria, (c) provide a as 10% in increasing the rate of sensit:2ation development Lim-procedure for conducting comprehensive reviews of facihty ited transgranutar caNde precipitation was observed in 20%

design, test condmons, and results, (d) ensure the prototypica.

pnor strain samples but was not a significant factor in the lity of the experimental data, and (e) quantify biases due to present work. The SSDOS model consistently over predicted scale distortions or due to non-prototypical test condit;ons. The DOS development regardless of matenal condition.

ab4hty to provide similanty entena thai combine the system (top-down) arid process (bottom-up) view points, is a key feature of NUREGIGR-0006 DRF FC: DEPOSITION: SOFTWARE TO CAL.

the Severe Accident Scaling Methodology. This hierarchical, CULATE PARTICLE PENETRATION THROUGH AEROSOL two-hered scahng (H2TS) approach provides both sufficiency TRANSPORT LINES Draft Report For Comment. ANAND.N.K.;

and efficiency. The Integrated Structure for Technical issue MCFARLAND,A.R. Texas A&M Univ., College Station, TX. Octo-Resolution and the Severe Accident Scahng Methodology have e

e ee for calculating aerosol been tested and demonstrated, by their appbcation to a postu-lated rect containment heating scenario. The Technical Pro-particle penetration tt rough straight tubes of arbitrary onenta-a e

is demonstrate that the methodol.

tion, inlets, and elbows An expression to calculate effective y at depositional velocities of particles on tube walls rs derived. The concept of " maximum penetration" is introduced, which is the NUREG/GR-0002: CONTINUOUS COOLING THERMAL. CYCLE maximum possible penetration through a sarnphg line connect-EFFECTS ON SENSIT'ZATION IN STAINLESS STEEL ing any two points in a three dimensional spao. A procedure to ATTE9tDGE,D.tt CEDENO.C.A. Oregon Graduate institute of predict opt: mum tube fameter for an visting transport line is Science & Technology. Beaverton, OR. September 1991.70pp.

develeped. An interactive menu dnven software entitled DEPO-9110110188. 5935t254.

SiTION has been developed to perform abovn said tasks. This Work for this study was directed towards quantifying sensi-code can either be used on a PC or on a rnainfranie. The use tization development (defined as grain boundary chromium de-and illustration of the software is described in Appendix A of i

pletion) in high caroon Type 304 and 316 stainless steel (SS) this report. A copy of the DEPOSITION software can be ob-subjected to anoar heating to a given perA tempuature 101-tarned from the Departmont of Energy's Energy Science and lowed by linear cooMg through the sensitization development Technology Software Center Oak Ridge, TN 37831 1020.

l l

l Secondary Report Number Index This index lists, in alphabetical crder, 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.

a SECONDARY REPORT WMDER REPORT NUMBER SECONDARY REPORT NUMDER REPORT NUMBER ANL-90/42 NUREG/CR-4513 LA-UR 90-732 HUREG/CR-5550 ANL-90/44 NUREG/CR4744 V04 N1 LMF 132 NUREG/C44214 R1P2A1 ANL 90/48 NUREG/CR4667 V09 MCS 910401 NUREG/C45729 ANL 90/49 NUREG/CR 4744 V04 N2 MPR 1230 NUREG/C45760 ANL 91/10 NUREG/C44744 V05 N2 MTR 90 WOO 467 NUREG/C45382 ANL 91/23 NUREG/C45/48 NISTlR 4327 NUREG/CR4235 ANL41/24 NUREG/CR 4667 V12 NISTIR 4405 NUREG/CR 4209 ANL 91/25 NUREG/CR-5757 NISTIR 4549 NUREG/CR 5727 ANL 91/5 NUREG/CR4667 V10 ORNL 6193 NUREG/CR-1302 V02 ANL41/6 NUREG/CR 5456 ORNL-6671 SUREG/CR 5706 ANL 31/7 NUREG/CR-4744 VOS N1 ORNL/NOAG232 NUREG/CR4674 V13 ANL 91/9 NUREG/C44%7 v11 ORNL/NOAC-232 NUREG/CR4674 V14 BAW 2023 NUREG/CR 5395 V01 ORNL/NSIC-200 NUREG/C42000 V09N12 BHARC700/90/03J NUREG/CR-49 61 ORNL/NSIC-200 NUREG/CR-2000 V10 N1 BHARC700/91/014 NUREG/CR 5758 V01 ORNLINSIC-?0O NUREG/CR-2000 VIO N2 BHARC700/91/025 NUREG/CR-5784 ORNL/NSIC-200 NUREG/CR-2000 V10 N3 BMI-2164 NUREG/CR-5128 ORNL/N9G200 NUREG/CR-2000 V10 N4 BMI-2173 NUREG/CR-4599 V01 N1 ORNL/NSIC 200 NUREG/CR-2000 V10 N5 BNL-NUREG 51581 NUREG/CR-2907 V09 ORNL/NSIC-200 NUREG/C42000 V10 N6 BNL NUREG-51699 NUREG/CR 3444 V08 ORNL/NSIC 200 NUREG/CR 2000 V10 N7 BNL-NUREG-51708 NUREG/CR-3469 V06 ORNL/NSIC-200 NURES/CR-2000 V10 N8 BNL-NUREG-52007 NUREG/CR 4659 V04 ORNL/NSIG200 NUREG/CR-2000 V10 N3 BNL-NUREG-52181 NUREG/C45282 ORNL/NslO 200 NUREG/CR-2000 V10N10 BNL-NUREG-52225 NUREGICR 5526 ORNL/NSIC-200 NUREG/C42000 V10N11 BNL NUREC-52232 NUREG/CR-5555 ORNL/RSIC-49/R1 NUREG/CR-5740 BNL NUREG-52240 NUREG/CR-5585 ORNl /TM-10328 NUREG/CR4816 Rot BNL NUREG-52251 NUREGICR-5611 ORNL/TM-11400 NUREG/CR-548 ?

BNL NUREG 52252 NUREG/CR 5612 ORNL/TM-11548 NUREG/CR-5565 BNL NUREG-52259 NUREG/C45634 ORNL/TM-11549 NUREG/CR 5571 BNL-NUREG-52261 NUREG/C45641 ORNL/TM-1

• 581 NUREG/CR-5592 BNL-NUREG-52271 NUREG/CR5662 ORNL/TM-11644 NUREG/C45623 BNL NUREG-52275 NOREG/C44444 ORNL/TM 11685 NUREG/CR-5647 BNL NUREG-52277 NUREG/CR4867 ORNL/TM 11686 NUREG/CR-5648 BNL NUREG-52278 NUREG/CR 5139 ORNL/TM-11692 NUREGIC45651 BNL-NUREG-52280 NUREG/CR Sf 91 ORNL/TM-11743 NUREG/CR-5668 BNL NUREG-52282 NUREG/C45692 ORNL/TM-11804 NUREG/CR 5696 BNL NUREG42288 NUREG/CR-5707 ORNL/TM 11823 NUHEG/CR-5712 BNL NUREG-b2294 NUREG/CR-5771 ORNL/TM 'i1861 NUREG/C45732 DRF FC BNL-NUREG 52295 NUREG/CR-5773 ORNL/TM 11970 NUREG/C45808 ONL NUPEG-52297 NUREG/CR-5620 ORNL/TM-9593 NUREG/CR 4219 V07 N1 BNL NUREG-52301 NUREG/C45530 V01 CANL/TM 9593 NUREG!CR4219 V07 N2 BNL NUREG 52303 NUREG/CR-5798 ORNLSUB797778/5 dVREG/CR 5697 C90-01 NUREG-1275 V06 ORNLSUB7977 /8/7 NUREG/CR-57%)

CNWRA89-001 NUREG/CR-5440 ORNLSUB90SH6401 NUREG/CR-5767 CONF 900813 NUREG/CP 0116 V01 PARAMETER IE163 NUREG/CB-4666 CONF-900813 NURbG/CP-0116 V02 PARAMETER IE164 NUREG/Cet-5288 EGG 2594 NUREG/CA-5529 PARAMETER IE176 NUREG/CR 5285 EGG-2595 NUREG/C45543 PARAMETER IE200 NUREG/C45309 EGG-2600 NUREG/CR-5558 PNL 5711 NUREG/CR-4469 V11 EGG 2605 NUREG/CR 5601 PNL 6806 NUREG/C45343 EGG 2613 NUREG/CR-5300 V01 PNL-7108 NUREG/CR5467 EGG-2614 NUREG/CR-5614 PNL-7479 NUREG/CR-5645 ~

EGG-2630 NUREG/C45520 PNL-74 92 NUREG/CR4427 EGG-2632 NUREG/C45654 PNL 7510 NUREG/CR 5656 EGG 4633 NUREG/CR 5663 Ptn.In13 NUREG/CR 5658 EGG-2634 NUREG/CR 5667 PNL 7518 NUREG/C45761 EGG-2635 NUREG/CR 5672 V01 PNL-7522 NUREG/CRfA69 EGG-2636 NUREG/CR4063 PNL 7502 NUREG/C44670 EG 4-2638 NUREG/CR-5601 PNL 7594 NUREG/C45764 EGG-2639 NUREG /CR-5702 PNL-7596 N'JAEG/CR-4911 EGG-2641 NUREG/CR-5717 PNL 7597 NUREG/CR4757 EGG-2859 NUREG/CR 5809 DRF FC PNL 7621 NUREG/CR-5713 FPRI/NP-6400 NUREG/CR-5395 V01 PN1 -7633 NUREG/CR5714 EPRl/NP-7165 NUREG/CR-5670 PNL 7688 NUREG/CR 5737 FEMA-REP 16 NUREG-1441 PNt-7723 NUREG/CR-5765 FEMA-REP 17 NUREG-1442 PNL 7725 NUREG/C45763 IEB 79-13 NUREG/CR-5285 PNL 7736 NUREG/CR-5758 V01 lEB-80-06 NUREG/CR-5288 PNL-7765 NUREG/C45768 IEB-83427 NUREG/CR-5309 PNL-7795 NUREG/CR-5784 IEB-84 02 NUREG/CR4666 SAIC-90/1393 NUREG/CR4690 V01 R1 IEB 88f04 NUREGICR-5706 SAIC-90/1400 NUREG/CR-5742 V01 K/ITP415 NUREG/C45734 SAIG90/1400 NUREG/09 5742 V02 LA 11992-MS NUREG/CR 5660 SAND 841351 NUREG/CR-3910 49 i

l l

l 50 Secondary Report Number Index SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER SAND 841531 NUREG/CR-3916 SAND 90-2121 NURE G 'CR-% t 9 SAND 86 019H NUREG/CR 3964 V02 SAND 90-2339 NURE G/CR-6630 SAND 861309 NUREG/CR-4551 V2 RIP 2 SAND 90-2629 NUREC CR 5655 SANDB8 3324 NUFIEG/CR4312 I^g$D ugg,]3g SAND 89-0072 NUREG/CR-5331 SAND 90 7020 NUREGICR 5561 SANDe9 0308 NUREG/CR 5345 SAND 90-7116 NUREG/CR 5304 SAND 89-2396 NUREG/CR-5525 SAND 910539 NUREG/CR 5?O1 SAND 642965 NUREG/CR-5495 SAND 910835 NUREG/CR 5715 SAND 90-0011 NUREG/CR 5518 SAND 910947 NUREG,CR-5 721 SAND 30 0128 NUREG/CR-5522 SAND 914948 NUREG/CR 5722 SAND 904364 NURE G/CR-553 g S AND910949 NUREG/CR 5723 SAN 990-0675 NUREG /CR-5537 h

hh h

SAND 900505 HUREG/C44539 SQE 42-89 NUREGICR-4893 SAND 9046%

NURE G/CR-5546 SCIE NRC-00'. 90 NUREG/CR 5167 SAND 901970 NURE G /CR-5606 SEAB9-461 11 Al NUREG/CR 5595 SAND 942009 NUREGICR-5618 Si-14940000-1 NUREG/CR-5665

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

?

ABABOU.R.

ANAND,N.K.

NUREG/CR-5743 APPROACHES TO LARGE SCALE UNSATURATED NUREG/GR 0006 DAF FC: DEPOSITION SOFTWARE 10 CALCULATE FLOW IN HETEROGENEOU% STRATIFIED. AND FRACTURED GEO.

PARTICLE PENETRATION TH3OUGH AEROSOL TRANSPORT LOGir MEDIA.

LINES Draf' Roport For Comment.

ABOUGHANTOUS.C.

APOSTOLAKIS,0.

NURE G 'CR-5649: TRANSPORT CALCVLATIONS OF NEUTHON NUREG/CR 3964 V02 TECHNIOUES FOR DETERM!NING PROBABIL.

TRANSMISSION THROUGH STEEL US:NG ENDF/B V, REVISED ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-ENDF/B-V,AND ENOF/B-VI 1RON EVALUATIONS ANCE LA GEOLOGIC REPOSITORIES Suggested Approaches.

NUREG/CR 5780:

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-AIRAHAMSON,S.

DENT MANAGEMENT FOR BWRS.

NUREG/CR-4214 RIPPA1; HEALTH EFFECTS MODELS FOR NUCLE, NUREG/CR-5781:

SUMMARY

OF A WLAKSHOP ON SEVERE ACCI-AR POWER PLANT ACCIDENT C04 SEQUENCE-DENT MANAGEMENT FOR PWRS.

ANALYSIS Mod 6 cations 01 Mod 91s Resulting From Resent Reports On

'He I s 01 lonmng Radiaton. Low LET RM rinPert it Soent,f.

~

NR 5691: INSTRUMENTf. TION AVAILABILITY FOR A PRES SUROt.D WATEH REACTOR W11H A LARGE DRY CONTAINMENT ABRA MSON.L.R.

DURING SEVERE ACCIDENTS NUREGJC45639. UNCLRTAINTY EVALUATION METHODS FOR ARMBRUSTER,J WASTE PACKAGE PERFORMANCF. ASSESSMENT.

NUREG/CR 5f78 V01: NEW YORK /NEW JERSEY REGIONAL SEISMIC AHMAD,J.

NUREG/CR 4s V01 N1: SHORT CRACKS IN PIPING AND PIPING ARZINO,P.A.

WELDESema.nual Report. March September 1990.

NUREG/CR 5689 MEDICAL SCREENING REFERENCE MANUAL FOR NUREGICR4128. EVALMTON AND REFINEMENT OF LEAK RATE SECURITY FORCE PERSONNEL AT FUEL CYCLE FACIUTIES POS.

ESTIMATON MODELS.

SESS,NG FORMULA OUANTITIES OF SPECIAL NUCLEAR VATERI-AM E RS,D,W.

ALS NUREG'CR-5690: PHYSICAL FITNESS TRAINING REFERENCE NUREGICR 5601. EFFECTS OF PH ON THE RELEASE OF '*A slONU-MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE FA.

CUDES AND CHELATING AGENTS FROM CEMEOSOuDIFIED DE-CluTIES POSSESSING FORMULA QUANTITIES OF SPECIAL NU-CONT AMINATION ION-EXCHANGE RESINS COLLECTED FROM OP-CLEAR MATERIALS ERATING NUCLEAR POWER STFIONS NUREG/CR 5672 V01 CHARACTERd I i V LOW-LEVEL RADIOAC-ASGARI.M.

TIVE WASTE. Decontaminahon Waste. Annual Report For Fiscal Year NUREG/CR 5648: TRANSPORT CALCULATIONS OF NEUTRON 1990 TRANSVISSON THROUGH STEEL U$ LNG ENOFi4V REVISED ENOF/B-V,ANO ENDF/B-VI 1RON EVALUATONS.

NUREG/CR 4295: BOC,MRENGTH OF CEMENTITIOUS BOREHOLE ATEFI,0.

PLUGS IN WELDED TUFF NU9EGICR 5742 V01: FEASIBILITY ASSESSMENT OF A R!SK-BASED APPROAC't TO TECHNICAL SPECIFICATIONS Esecutive Summary ALEXANDER.S.S.

NUREG/CR-5742 V02. FEASIBILITY ASSESSMENT OF A RISK-BASEO NUREG/CR 5628 PENNSYLVANIA SEISM'C MONITORING NETWORK APPROACH TO TECHN) CAL SPECIFICATIONS Man Report.

AND RELATED TECTONIC STijDIES Final Report.

ALLE N,M.D.

NUREG/GR 0002: CONTINUOUS COOUNG THERMAL CYCLE EF.

NUREG/CH-5345 FISSON PRODUCT RELEASE AND FUEL BEHAV-FECTS ON SENSITl?ATION IN STAINLESS STEEL IOR OF IRRADIATED UGHT WATER REACTJ:

EL UNDER NUREG/GR-0003; EFFECT OF PRIOR DEFORMATION ON SENSITIZA.

SEVERE ACCIPENT CONDITIONS. The ACRR ST-1 ugenment TION DEVELOPMENT IN STAINLESS STEEL DURING CONTINUOUS NUREG/CR4728 EVPERIMENTS TO INVESTIGATE THE EFFECT Op COOUNG.

FUGHT PATH ON DIRECT CONTA!NMENT HEATING (DCH) IN THE SURTSEY TES1 F ACluTY.The Lmted Fbght Path (LFP) Testa BAKER K NURdG/CR-4911: INCENTIVE REGULATON OF NUCLEAR POWER ALLENSPACHf.

PLANE BY STATE REGULATORS.

NUREG-1214 R07. HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT' BAKER W

• IC ASSESSMENT OF UCENSEE PERTORMANCE-NURNGkR-5660: STATIC AND SIMULATED SEISMIC TESTING OF NUREG-1214 RO8. HISTORICN. DATA

SUMMARY

OF THE SYSTEMAT*

IC ASSESSMENT CF UCE'NSEE PERFORMANCE.

THE TRG-7 THROUGH -16 SHEAR WALL STRUCTURES.

AMARASOORIVA,W.

B ALL.S.J.

NUREGICR-5712: MORECA: A COMPUTER CODE FOR SIMULATING NUREG/CR 5423 THE PROBABluTY OF UNER FAILURI IN A MARK 4 CONTAINMENT.

MODOLAR HOH TEMPERATURE GAS-COOLED REACTOR CORE HEATUP ACCIDCNTS.

AMOS,C.N-BANDYOPADHYAY NUREG/CR-4551 V2R192: EVALUAT:CN OF SEVERE ACCOENT NUREG/CR-4659 V04 SEISMIC FRAGILITY OF NUCLEAR POWER RISKS: OUANTIFICATION OF MAJOR INPUT PARAMETERS Experts' PLANT COMPONENTS (PHASE II).A Fragthty Handbr'ok On Eign'ot n Deterrmna%n Of Contamment Leeds And Molten Core Containment Crmponents Interacton Issues.

NUREG/CR 4867; RELAY TEST PROGRAM Senes i Vibration Tests.

51 l

52 Personal Author index B ARB E R,0.E.

NUREG/CR-5714. HYDROGEOLOGIC PERFOAMANCE ASSESSMENT NUREG/CR 4444 PADIATION SAFETY ISSUES RELATED TO RADO-ANALYSIS OF THE LOW-LEVEL RADCACTIVE WASTE DISPOSAL LABELED ANTIBCDIES FACILITY NEAR SHEFFIELD. ILLINOIS NUREG/CR 5737; HYDROGEOLOGIC PERFORMANCE ASSESSMENT DASDEIL AS.D-ANALYSIS - OF THE COMMERCIAL LOW-LEVEL RADCACTIVE NUREG 1420 REGULATORY ANALYSIS FOR THE RESC

'ON OF WASTE DISPOSAL FACILITY NEAR WEST VALLEY.NEW YORK.

GENERIC ISSUE 130 ESSENTIAL SERVICE WATER Sh

. F All.

~

URES AT MULTIUNIT SITES BEROGREmR.G.

NUREG/CR-5696: IRRADIATION EFFECTS ON CHARPY IMPACT AND U E'C/CR-5592; ANALYTICAL STUOlES OF TRANSVERSE STRAIN SER S2AD EFFECTS ON FRACTUHE TOUGHNESS FOR CIRCUMFERENTIALLY ORIENTED CRACKS-BILLUPS,S.C.

NUREG/CR.5650 AN INVESTOATON OF CRACK.TiP STRESS FIELD NUREG/CR 5715. REFERENCE MANUAL FOR THE CONTAIN 1.1 CRITERIA FOR PREDICTiu CLEAVAGE CRACK INr T1ATION CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS BATES.G.

NUREG 1441; LESSONS LEARNED FROM THE POST. EMERGENCY BITTNER'R' TABLETOP EXERCISE IN BATON ROUGEsLOUISlANA.ON AUGUST NUREG/CR-5784. FITNESS FOR DUTY IN THE NUCLEAR POWER S

A Rh O W hat War O Wam % man And 23 AND SEPTEMBER 18.1990.

NUREG-1442:

POST-EMERGENCY

RESPONSE

RESOURCES An Update Of The Technical issues.

GUIDE. Based On The Post Er. *gency TABLETOP Exercise in Baton BLACKMAN H.S.

Rouge.Lourmana.On August 28 and September 18.1990 NUREG/CF 5543. A SYSTEMATIC PROCESS FOR DEVELOPING AND BAUM4W.

ASSESSING ACCIDENT MANAGEMENT PL ANS.

NUREG/CH-3469 V06 OCCUPATIONAL DCSE REDUCTION AT NU.

CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SELECT, BLUHM.D.

ED READINGS IN RADIATION PROTECTION AND At ARA.

NUREG/CR-656t ANALYSIS OF BELLOWS EXPANSION JOINTS IN NUREG'CR-4444: RADIATION SAFETY ISSUES RELATFD TO RADIO.

THE SEQUOYAH CONTAINMENT.

LMELED ANTIBODIES.

9eG/CR-5139 DOSE. REDUCTION TECHN!OUES FOR HIGH-DOSE BOARDMANAR.

RKER GROUPS IN NUCLEAR POWER PLANTS, NUREG-1022 RO1 DR FC: EVENT REPORTING SYSTEMS 10 CFR 50.72 AND 50.73 Clarificaten Of NRC Systems And Guidelines for BEAHM.E.C, Reporting Draft Report For Comnent NUREG/CA.5732 DRF FC: ODINE CHEMICAL FORMS IN LWFt SEVERE ACCIDENTS. Draft Report For Comment BOBE,P.E.-

NUREG-1022 R01 DR FC: EVENT REPORTING SYSTEMS 10 CFR NUREG/CR 5598: IMMERSON STUDIES ON CANDIDATE CON"lNER rt a e ALLOYS FOR THE TUFF REPOSITORY.

BOECKER,B.B.

EG 1 75 PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDh [R ER A DENT N

NC -

VIDUAL PLANT EXAMINATON OF EXTE_RNAL EVENTS (IPEEE) FOR SEVERE ACCIDENT VULNERABit.lTIElainal Report.

ANALYSi$ Mod ticatons Of Modela Resulting From Rece* Reports On Hee % Ettects Of loreng Radiatiortlow LET Radiation 11: Scientif.

BELEW.WL ic Bases For Healtti...

NUREG/CR-5734 RECOMMENDATONS TO THE NRC ON ACCEPTA.

BLE STANDARD FORMAT AND CONTENT FOR THE FUNDAMEN-

"U TAL NUCLEAR MATERIAL CONTROL (FNMC) PLAN REQUIRED FOR NUREG'CR.57'03-LOWER-BOUND INITIATION TOUGHNESS WITH A LOW-ENRICHED URAN 10M ENR!CHMENT FACILITIES MODIFIED-CHARPY SPECIMEN BENDER,MA.

BOUCHERON,E.A.

NUREG/CH-4214 RIP 2At HEALTH EFFECTS MODELS FOR NUCLE.

NUREG/CR 553t MELCOR t.8 0 A COMPUTER CODE FOR NUCLEAR AR POWER PLANT ACCIDENT CONSEQVENCE REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS.

ANALYSIS Modifications Of Models Resulting From Recent Reoorts On

. MENT ANALYSES, Hoatth Effects Of ioniang Radiation Low LET Radiation.Part II: Scientf-BOYACK B E NUREG/Cb-5809 DRF FC: AN INTEGRATED STRUCTURE AND SCAL.

DENEDICK,W.B.

ING METHODOLOGY FOR SEVERE ACC! DENT TECHNICAL ISSUE NUREGICR-5525 HYDROGEN. AIR DILUENT DETONAitON STUDY RESOLUTON Draft Report For Comment.

FOR NUCLEAR REACTOR SAFETY ANALYSES

- BOYLE.C.D.

BENNETT,R.D.

NUREG/CR-5717. PACKAGING SUPPLIER INSPECTION GUIDE.

NUREG/CR 5432 V00 RECOMMENDATIONS TO THE NRC FOR SOIL COVER SYSTEMS OVER URANIUM MILL TAILINGS AND LOW-BR ADY,B.H.G.

LEVEL RADCACTIVE WASTES. Identificat!on And Ranbng Of Soils Nu9EG/CR-5440 CRmc gl ASSESSMENT OF SEISMIC AND GEOME-Fo. Osposal facility Covers _

CHANICS LITERATUFe RELATED TO A HIGH-LEVEL NUCLEAR NUREG/CR.5432 V02: RECOMMENDATIONS TO THE NRC FOR SOIL WASTE UNDERGROUND REPOSITORY.

COVER SYSTEMS OVER URANIUM MILL TAILINGS AND LOW.

LEVEt FIADtOACTIVE WASTES, Laboratory And Field Tests For Soil BRAMWELL,A.

Covers NUREG/CR-5784:.. FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-5432 V03. RECOMMENDATIONS TO THE NRC FOR SOIL INDUSTRY.A Review Of The Frst Year Of Program Performance And COVER SYSTEMS OVER URANIUM MILL 'AILINGS AND LOW.

An Update Of The Technicalissues.

LEVEL RADIOACTIVE WASTES. Construction Methods And Guidance For Seakng Penetratons in Soil Covers.

BRAS R. -

BERGERON.K.D.

ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM.

NUREG/CR-5518: CUALITY ASSURANCE P'tOCEDURES FOR THE ACE OF GEOLOGIC REPOSITORIES Suggested Approaches--

CONTAIN SEVERE RE ACTOR ACCIDENT C1APUTER CODE.

BREEDlHG.R.J.

BERGERON.M.P.

NUREG/CR-4551 V2 RIP 2: EVALUATION OF SEVERE %CCIDENT NUREG/CR 5713. A REVIEW OF ENVIRONMENTAL CONDt* ONS AND RISKS QUANTIFICATION OF MAJOR INPUT PARAMETERS Experts' PERFORMANCE OF THE COMMERCIAL LOW-LEVEL RADIOACTIVE Dewminaten Of Containment Loads And Moiten Core Containment WASTE DISPOSAL FACILITY NEAR SHEFFIELD.lLLINOIS.

Interaction issues,

Personal Author index 53 BRENNERLM.

CEDE NO.C.A.

NUREG/CR 5734 RECOMMENDATIONS TO THE NRC ON ACCEPTA-NUREG/GR-0002: CONTINUOUS COOUNG THERMAL CYCLE EF.

BLE STANDARD FORMAT AND CONTENT FOR THE FUNDAMEN-FECTS ON SENSITIZATION IN STAINLESS STEEL TAL NUCLEAR MATERIAL CONTROt, (FNMC) PLAN REQUIRED FOR LOW. ENRICHED URANIUM EN9ICHMENT FACtLITIES.

CHANO,T.Y.

NUREG-1445: REGULATORY ANALYSIS FOR THE RESOLUTION OF fN N U

0430 V10 UCENSED FUEL FACluTY STATUS EAR P NTS REPORT. inventory Deerence Data. July 1989 - June 1990.(Gray Book UI CHE N,J.T.

EROWN C.H.

NUREG 1407: PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDI, NUREG/CR 5689 MEDICAL SCREENING REFERENCE MANUAL FOR VOUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IFEEE) FOR s

SECURITY FORCE PERSONNEL AT FUEL CYCLE FACILITIES POS-SEVERE ACCOENT VULNERADILITIES. Final Report SESSING FORMULA OUANTITIES OF SPECIAL NUCLEAR MATERl-ALS.

CHEN,Y.S.

NUREG/CR-4063. AN INVESTIGATION OF CORE UOUO LEVEL DE-8ROWN,T.D.

PRESSION IN SMALL BREAK LOSS-OF COOLANT ACCIDENTS NUREG/C44551 V2R1P2: EVALUATON OF SEVERE ACCOENT RISKS OVANTIFICATON OF MAJOR INPUT PARAMETERS Exwrts' CHIEN.D.N.

Determnation Of Containment Loads And Motten Core Containment NUREG/CR-5702. ACCIDENT MANAGEMENT INFORMATION NEEDS interaction issues FOR A BWR WITH A MARK 1 CONTAINMENT.

ERUE M MER.E.M-CHOKSHI,N.

NUREG/GR.0003. EFFECT OF PRIOR DEFORMATICN ON SENSITl2A-NUREG-0675 S34-SAFETY EVALUATION REPORT RELATED TO THE TION DEVELOPMENT IN STAINLESS STEEL DUR!NG CONTINUOUS OPERATION OF DIABLO CANYON NUCLEAR POWER PLANT,UN'TS COOUNG 1 AND 2 Docket Nos. 54275 And $0-323(Pacinc Gas And Electne CRUST,F.

Company)

NUREG/CR-4599 V01 N1: SHORT CPACKS IN PIP'NG AND PIPING CHO WELDb Semannual Report March. September 1990 Oh: PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDI-NU EUNTING,J.

VIDUAL PLANT EXAMINATIP OF EXTERNAL EVENTS (IPEEE) FOR NUREG 1439 STAFF TECHNICAL POSITION ON REGULATORY CON-SEVERE ACCOENT VULNEFL h tTIES Final Report.

SOERATIONS IN THE DESIGN AND CONSTRUCTION OF THE EX-PLORAiORY SHAFT FACIUTY.

CHOPRA.O.K.

NUREGIC44513: ESTIMATION OF FRACTURE TOUGHNESS OF NUFk G k':R 5658. FPFP 2: A CODE FOR FOLLOWING AIRBORNE FIS-3 N EG/C 7 SA CO A

L L IN I SiON PRODUCT CAPTURE IN SUPPRESSION POOLS.

OUPLEX STAlulESS STEELS IN LWR SYSTEMS Semannual Report. October 1988 - March 1989.

BUSH.LY, NUREG/CR.4744 VD4 N2: LONG-TERM EMBRITTIEMENT OF CAST NUREG/C44744 V04 N2: LONG TERM FitBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Semannual DUPLEX STAINLESS STEELS IN LWR SYSfEMS.Semannual ReportAprl;Gy mber 1989 Report.Aont-September 1989 NUREG/CR-4744 VOS N1: LLsNG-TERM EMBRITTLEMENT OF CAST NUREG/CA-4744 V05 N1: LONG-TERM EMBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Semannual DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual Report. October 1989 March 1990.

Report,0ctober 1989. March 1990.

NUREG/C44744 V05 N2 LONG4ERM EMBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYPEMS. Semiannual CAMPBELL.J.E, Report,Apnt September 1990.

NUREG/C45539: A SELF-TEACHING CURRICULUM FOR THE NRC/

NUREG/C45748 RADIATION EMORITTLEMENT OF THE NEUTRON SNL LOW 4EVEL WASTE PERFORMANCE ASSESSMENT METHOD-SHIELD TANK FROM THE SHIPPINGPORT REACTOR.

OLOGY, NUREGICR-5618-t!SER S MANUAL FOR THE NEFTRAN 11 COMPUT' CHRISTENSEN,J.

NUREG/C45758 V0t FITNESS FOR DUTY IN THE NUCLEAR POWER C AMPBE LL,R.M.

INDUSTRY. Annual Summary Of Program Performance Reports,CY

=

NUREG/CR4670: RADIONUCUDE DISTRIBUTIONS AND MIG 9ALON 1990.

MECHANISMS AT SHALLOW LAND BURIAL SITEb Final Remrt C*

PNI, Research investigations On The Distnbuteon, Migrate, And Con.

CHRITTON,M.R.

tainment Of Radionuchdes At Maxey Flats, Kentucky.

NUREG/C45723. SECURITY SYSTEM SIGNAL SUPERVISION.

CAPLAN,C.S.

CHU,M.5,Y NUREGICR-5690: PHYSICAL FITNESS TRAINING REFERENCE NUREG/CR-5539: A SELF-TEACHING CURRfCULUM FOR THE NRC/

MANUAL FOR SECURITY FORCE FERSONNEL AT FUEL CYCLE FA.

SNL LOW LEVEL WASTE PERFORMANCE ASSESSMENT MEfMOO-CILITIES POSSESSING FORMULA QUANTITIES OF SPECIAL NU-OLOGY.

CLEAR MATER;ALS.

CHUNG,D,T.

CARMEL.M.K.

NUREG/C45682: SPECIFIC TOPICS IN SEVERE ACCIDENT MANAGE-NUREG/C45331: MELCOR ANALYSES FOR ACCOENT PROGRES-MENT.

SION ISSUES.

NUREG/CR-5531: MELCOR 1.8.0: A COMPUTER CODE FOR NUCLEAR CHUNG,H.M.

r4EACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS-NUREG/C44607 V.0: ENYIRONMENTALLY ASSISTED CRACKING IN MENT ANALYSES.

LIGHT WATER REACTORS. Semannual Reg. ort,0ctober 1989 + March 1990.

CARROLL.D.E[5518. QUAUTY ASSURANCE PROCEDURES FOR ' THE NUREG/CR NUREG/CR-4667 V11: ENVIRONMENTALLY ASSISTED CRACKING IN CONTAIN SEVERE REACTOR ACCIDENT COMPUTER CODE

. UGHT WATER REACTORS. Semannual Report.Apni-September 1990.

NUREG/CR-5715: REFERENCE MANUAL FOR THE CONTAIN 1.1 NUREG/CR4667 V12: ENVlHONMENTAU.Y ASSibTED CRACKING IN CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS.

UGHT WATER HEACTORS. Semiannual ReportOctober 1990 - March 1991.

CASADA,0.A.

NUREG/C44744 V04 N1: LONG TERM OMBRITTLCMENT OF CAST NUREG/CR-5706 POTENTIAL SAFETY-RELATED PUMP LOSS: AN AS-DUPLEX STAINLESS STEELS IN LWR SYSTEMS. Semiannual SESSMENT OF INDUSTRY DATA.NRC Bulletin 88-04, Report,0ctober 1988 Ma/ch 1999 l

.J

l l

54 Personal Author inder CHUNGJ.

DAEMENJJ K.

NUREG/CR 5692. GENERIC RISK INSIGHTS FOR GENERAL ELEC-NUREGICR 4295: BONO STRENGTH OF CEMENTITOUS BOREHOLE THIC DOtuNG WATER REACTORS PLUGS IN WELDED TUFF.

CLEAVELAND,M.

NUREG/C45683 LABORATORY TESTING OF CEMENT GROUTING OF FRACTURES IN WELDED TUFF NUREG/C45749 TECTONIC DEFORMATON REVEALED IN BALDCY-NUREG/CR 8604: ANALYSES AND FIELD TESTS OF THE NYDRAULIC PRESS TREES AT REELFOOT LAKE. TENNESSEE-PFRFORMANCE OF CEMENT GROUT BORD 40LE SEALS.

CLETCHERJ.W-NUREG/CR-5688 E; FECTIVENESS OF FRACTURE SEALING WITH BENTONtTE GROUTING NUREG/C44674 V13 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/C45688-MECHANICAL CHARACTEnt2ATION OF DENSELY DAMAGE ACCIDENTS.163 A STATUS REPORT. Main Report And Ap*

VIELDEO APACHE LEAP TUFF.

perdx A.

HVHEG/CR 4674 V14 PRECURSORS TO POTENTIAL SEVERE CORU DALLMAN.R.J.

DAMAGE ACCIDENTS 1990 A STATUS REPORT Appendrues B And NUREG/CR-5529 AN ASSESSMENT OF BWh MARK 111 CONTAIN-C MENT CHALLENGES FAILURE IwCOrs. A 9 POTENTIAL IMPROVE.

CLIFTON.J.R.

NUREG/CR-4235 $2t ECTION 08 NU"EOUS AGGREGATE FOR DALLY,J.W.

NU EG CR 69 MODELS OF TRANSPURT PROCESSES IN CON-CRETE.

MD D RPY SP E

NUREG/CR.5727. CHLORCE ION DIFFUSON IN LOW WATER.TO-SOLID CEMENT PASTES' DAP3YJL NUREG/CR 5606 A REVIEW OF THE SOUTH TEXAS PROJECT PROD-COLE,N.M.

ABtUSTIC SAFETY ANALYSIS FOR ACCIDENT FREQUENCY ESTI-NUREGIC45760 REPORT ON ANNEAUNG OF THE NOVOVORON.

MATES ANO CONTAINMENT BINNING.

E2H UNIT 3 REACTOR VESSEL IN THE USSR' DAVIS,P.A.

COLE.R.K.

NUREG/CR 5522: A COMPARISON OF PARAVETER ESilMATION NUREG/CR-553t MELCOR 110: A COMPUTER CODE FOR NUCLEAR AND SENSITIVITY ANALYSIS TECHNIQUES AND THEIR IMPACT ON REACTOR SEVERE ACCOENT SOURCE TERM AND RISK ASSESS.

THE UNCERTAINTY IN GROUND WATER FLOW MODEL PREDIC-MENT ANALYSES TIONS.

NUREG/C45537. APPROACHES FOR THE VAUDATION OF MODELS COLLINSJ.L USD FOR PERFORMANCE ASSESSMENT OF HiGH LFVEL NUCLE.

NUR5G/CR 5481: DATA

SUMMARY

REPORT FOR FISSION PRODUCT AR WASTE REPOSITORIES, RELE ASE TEST VI 4.

NUREG/C45668 OATA 3UbMARY REPORT FOR FiSSON PRODUCT DAWSONJf.

HELEASE TEST V1-5 NUREG/C45645. ACOHSTIC EMIFSION/ FLAW HELATIONSHIPS FOR INSEHVICE MONITORING OF LWRS.

C NOREG/C45620. THATCH: A COMPUTER CODE FOR MODELUNG DEAN,R S.

(

THERMAL NETWORm.S OF HIG4 TEMPERATURE GAS-COOLED NU-NUREG/CR 4666-CLOSEOUT OF IE BULLETIN 84 02: FAILURES OF CLEAR REACTORS.

GENERAL ELECTR!C TYPE HFA RELAYS IN USE IN CLASS 1E CONGEMlJ.

SAFETY SYSTEM 3 NUREG/C45285: CLOSEOUT OF tE BULLETIN 7913: CRACKING IN NUREG/CR 2907 V09: RADIOACTIVE MATER ALS RELEASED FROM FEEDWATER SYSTEM PiPtNG.

NUCLEAR POWER PLANTS. Annual Report 1908-NUREG/CR 5268: CLOSEOUT OF IE BULLETIN 80-06. ENGINEERED COOO'A.

SAFETY FEATURE (ESF) RESET CONTROLS.

NUREG-1446: STANDARDS FOR PROTECTION AGAINST RADIATION -

NUREG/CR-5309: CLOSEOUT OF IE BULLETIN 8347: APPARENTLY 10 CFR PART 20 A Compenson Of The Exsting And Remed Rules FRAVOULENT PRODUCTS SOLD BY RAY MILLER.INC.

COOPER,S.E DEWALL,K.G.

NUREG/CR-5695: A PROCESS FOR RISK FOCUSED MA!NTENANCE' EG/C45558. GENERIC ISSUE 87: FLEXIBLE WEDGE GATE VALVE TEST PROGRAM, Phsse il Results And Analysis-COPINGER,0.A.

NUREG/CR4674 V13: PRECURSORS TC r OTENTIAL SEVERE CORE 2

DAMAGE ACCIDENTS 1990 A STATUS REPORT Main R'put And 4 NUREG/C45780:

SUMMARY

OF A WORKSHOP ON SEVEPE ACCI-pendix A DENT MANAGEMENT FOR BWRS, NUREG/CR-4674 V14: PRECURSORS TO POTENTIAL SEVERE CORE NUREGIC45781:

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-DAMAGE ACCIDENTS 1990 A STATUS REPORT. Appendixes B And DENT MANAGEMENT FOR PWRS.

DIAMOND,D.J.

COTTER B.P.

NUREG/CR-5771: PROBABluTY AND CONSEQUENCES OF MISLOAD-NUREG 1363 V03 ATOMIC SAFETY AND UCENSING BOARD PANEL ING FUEL IN A PWR.

ANN JAL REPORT. Fiscal Year 1990.

gg CRONIN.W.E.

NUREG/CR-5331: MELCOR ANALYSES FOR ACCIDENT PROGRES-NUREG/CR 5737: HYDROGEOLOGIC PERFORMANCE ASSESSMENT SiON ISSUES, ANALYSIS OF THE COMMERCIAL LOW LEVEL RADtOACTIVE NUREG/C45531: MELCOR 1.8 0: A COMPUTER CODE FOR NUCLEAR WASTE DISPOSAL FACIUTY NEAR WEST VALLEY,NEW YORK.

REACTOR SEVERE ACCIDENT SOURCE TERM AND R!SK ASSESS-MENT ANALYSES.

CROOKS.J.L NUREG 1022 R01 DR FC' EVENT REPORTING SYSTEMS 10 CFR DIONNE,B.J.

50.72 AND 50.73 Clanfication Of NRC Systems And Guidelines for NUREG/C45139: DOSE REDUCTION TECHNIQUES FOR HIGH-DOSE Reporting Draft Report For Comment WORKER GROUPS IN NUCLEAR POWER PLANTS.

CROUCH,0.A.

DOBSE.C.A.

NUREG/CR 5538 V01: INFLUENCE OF ORGAN 12 ATONAL FACTORS NUREG/C45667; INEL PERSONAL COMPUTER VERSION OF MACCS ON PERFORMANCE REUAaluTY. Overview And Detailed Methodo.

1.5.

logical Develeprnent DOCTOR.S.R.

CURRERI.J.R.

NUREG/CR 4469 Vit NONDESTRUCTIVE EXAM 1N ATON WDE) REU-NUAEG/CR 5585. THE HIGH LEVEL VIBRATION TEST PROGRAM. Final ABluTY FOR INSERVICE INSFECTION OF LIGHT WATER Report REACTORS.SembAnnual Report, Apnl.Septernter 1989

Personal Author index 55 DOLAN.B.W.

F ARR AR.C.R.

NUHEG/CR 4674 V13 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 56M STATIC AND S!MULATED SEISMIC TESTING OF DAMAGE ACCIDENTS 1990 A 51 ATUS REPORT. Main Report And Ap-THE TRG-7 THROUGH.16 SHE AR WALL STRUCTURES penda A NUREG/CR-4674 V14. PRECURSORS TO POTENTIAL SEVERE CORE FIRST.M.W.

DAMAGE ACCIDENTS 1990 A STATUS REPORT.Appendmes B And NUREG/CP 0116 V01: PROCEEDINGS OF THE 21ST DOS /NRC NU-C CLEAR AIR CLEANING CONFERENCE Sessons 1 8 Held in San DOVE.R C.

Omgo. Cattforn.a. August 13-16.1990.

NUREG/CR-5660 STATIC AND SIMULATED EEISMIC TESTING OF NUREG/CP.0116 V02 PROUEEDINGS OF THE 21ST dot'/NRC NU-THE TRG-7 THROUGH.16 SHEAR W ALL STRUCTURES CLEAR AIR CLEANING CCNFERENCE SESSONS 9 16 Held in San Diego, Cantornia. August 13-16.1990.

DRY,B.

NUREG/C45722 INTERIOR INTRUSf0N CETECTION SYSTEMS.

IISK W DUKELOW,.l.S.

IOR OF IRRADtATED LIGHT WATER REACTOR FUEL UNDER NUREG/CR 5467 RISK. BASED INSPECTION GUIDE FOR CRYSTAL SEVERE ACCIDENT CONDITIONS The ACAR ST-1 Espenment RIVER UNIT 3 NUCLEAR POWER PLANT.

FITZPATRICK,G.

DUKLE R,A.E.

NUREG/CR-5551: TWO NEW NDT TECHNOVES FOR INSPECTION OF NUREG/CR-5809 DAF FC. AN INTEGRATED STRUCTURE AND SCAL' CONTAINMENT WELDS DENEATH COATINGS Firial ReportOctober ING METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE 1989. March 1990.

RESOLUTION. Draft Report For Comment.

FITZPATRICM,R.

U IC45758 V01: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR.5526. ANALYSIS OF RISK REDUCTION MEASURES AP-S ED E N M W G N R M N M INDUSTRY. Annual Summary Of Program PerformMce naports.CY 1990 MULTI-UNIT SITES.

NUREG/C45784. FITNESS FOR DUTY IN THE NUCLEAR PCWER N

TRY R ew T Fnt Year Of Propeam Performance And U EG 128. EVALVATON AND REFINEMENT OF LEAK RATE ESTIMATON MODELS.

DURR.C.L NUREG/CR-5598. IMMERSION STUDIES ON CANDIDATE CONTAINER FLEMING,T.

ALLOYS FOR THE TUFF REPOSITORY.

NUREG/CR-5758 V01: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY. Annual Suminary Of Program Performance Reports,CY DWYER,P.A.

1990 NUREG 1321: TESTING STANDARDS FOR P!(YSICAL SECURITY SYS NUREG/C45784. FITNESS FOR DUTY IN THE NUCLEAR POWER TEMS AT CATEGORY I FUEL CYCLE FACILITIES INDUSTRY.A Revew Of The Fnt Year Of Program Performance And NUREG-1322: AUCEPTANCE CR!TERtA FOR THE EVALUATION OF An Upda4 Of The Techrutat luuss.

CATEGORY l FUEL CYCLE FACILh'Y PHYSICAL SECUR;TY PLANS.

EASON.E.D.

FOLEY,W.J.

NUREG/CR-466tL CLOSEOUT OF IE BULLETIN 84-02, FAILURE *i OF NUREG/CR5729-MULTIVARIABLE MODEUNG OF PRESSUHE VESSEL AND PIPING.)-R DATA.

GENERAL ELECTR4 TYPE HFA RELAYS IN USE IN CLASS 1E SAFETY SYSTEMS.

-J EBEL.P,E.

NUREG/CR 5285: CLOSEOUT OF IE BULLETIN 79-13 CRACK!NG IN NUREG/CR.572t VIDEO SYSTEMS FOR ALARM ASSESSMENT.

FEEDWATER SYSTFM PIPING.

NUREG/C45288. CLOSEOUT OF IE BULLETIN 80-06 ENGINEERED EMRIT,R.

SAFETY FEATURE (ESF) RESET CONTROLS.

NUREG-0933 S01 12: A PRIORITIZATION OF GENERIC SAFETY NUREG/C45309: CLOSEOUT OF IE BULLETIN 83-07: APPARENTLY Nt E 933 S12 A PRIORITIZATICN OF GENERIC SAFETY ISSUS NUREG-0933 S13 A PRIORillZATION OF GENER6C SAFETY ISSUES FOURNEY,W.L ENSSLIN,N.

NUREGiCR-5703 LOWER BOUND INITIATON TOUGHNESS WITH A NUREC/CR-5550: PASSIVE NONDESTRUCTIVE ASSAY OF NUCLEAR MOblFIED CHA%Y SPECIMEN.

FOWLER.R.D.

ESCALANTE.E.

NUREG/CR.5520: PROCEDURES GUIDE FOR EX1RACTING AND NUREG/C44735 V07. EVALUATION AND COMPILATION OF DOE LOADING PROBABluSTIC RISK ASSESSMENT DATA INTO MAR.D WASTE PACKAGE TEST DATA. Biannual Report February July 1939.

USING IRRAS 2.5.

E SCHB ACH.E.J.

FRAKER.A.C.

NUREG/CR-5768_ ICE-CONDENSER AEROSOL TESTS.

NUREG/C44735 V07: EVALUATON AN0 COMPILATION OF DOE WA5TE PACKAGE TEST DATA. Bennual Report: February July 1989, NUREG-1301: OFFSITE DOSE CALCUL/. TION MANUAL GUIDANCE; FRANg,L STANDARD RADIOt.OGICAL EFFLUENT CONTROLS FOR PRES' NUREG/CR-5796:

STEAM GENERATOR OPERATING SURIZED WATER 9EACTORS Generic Letter 89-01.Suppiement No.

EXPERIENCE. UPDATE FOR 1989-1990.

1.

NUREG4302: OFFSITE DOSE CALCULATION MANUAL GUIDANCE.

FRIDERICHS,T.

STANDARD RADCI.OGICAL EFFLUENT CONTROLS FOR BO(LING NUREG/C45760 REPORT ON ANNEALING OF THE NOVCVORON-WATER REACTOR 3. Generic Letter 89 01,Sepplement N11 E24 UNIT 3 REACTOR VESSEL IN THE USSR.

EVANS,0.D.

1 FRIESEL,MJL NUREG/C45581-UNSA TURATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK FIELATED TO rlIGH-LEVEL WASTE NUREG/CR5645. ACOUSTIC EMISSION / FLAW RELATIONSHIPS FOR REPOSITORIES Final Report - Phase Ill_

INSERVICE MONITORING OF LWM FANOU*F.

FUEHRER,0.F.

NUREG/CR-5561: ANALYSIS OF BELLOWS EXPANSION JOtNTS IN NUREG/CR5655: SUBMERGENCE AND HIGH TEMPERATURE STEAM h.c SEQUOYAH CONTAINMENT.

TESTING OF CLAS' 1E ELECTRICAL CABLES.

FARAMARZLA.

F UENK AJORN.K.

NUREG/C45302 SCREENtNG OF GENERIC SAFETY ISSUES FOR Li-NUREG/C4568K MEttlANtCAL CHARACTERIZATION OF DENSELY CENSE RENEWAL CONSIDERATIONS WELDED APACHE LEAP TUFF.

i

L 56 PersOnel Author Index GALLACHER,0.W.

CORE,B.F.

NUREG/CR-5742 V01: FCASIBILITY ASSESSMENT Or A RISg.gAWD NUREG/CR e427 AUX 1LIARY FEEDWATER SYSTEM RISK.DASED IN-APFRO ACH TO TUWM SPECFICATONS Esecutwo Summa'Y SPECTON GUIDE FOR THE BYRON AND BRMDWOOD NUCLEAR NUNEA RS?F' "WTY ASSESSMENT OF A RISK BASED powgp ptAgtg.

APPROACH F

/ NCirICATIONS Ma n Report NUREG/CR 5761: AUXIUARY FEEDWATER SYSTEM RISK BASED IN.

ogm 4 SPECTON GUIDE FOR THE SALEM NUCLEAR POWER PLANT.

k $'

sNCEF/sAU7ATOb_

'*OTHETICAL HIGH.

'dUREGICR5763. AUXILLARY FEEDWATER SYSTEM RISK. BASED IN-NUREE '

9 IEVb

-5 WAF TE e'

WAY

$1TE IN SPECTION GUIDE FOR THE CAu.AWAY NUCLEAR POWER PLANT.

UNW e d W. TW. Ti p "

NUREG/C45764-AUKluARY FEEDWATEFl SYSTEM RISK BASED If&

NURFP n_'

A C slA.

• @wdE THREE.DJMENSION.

SPECTION GUIDE FOR THE GINNA NUCLE AR POWER PLANT.

c A'

LOW (

9R UNSATURATED, FRAC-

,"c m GORHAM,E.D.

Ntt b.

t=

.y x W '.NM, ASSESSMENT METHODOLOGY NUREG/CR.4551 V2 RIP 2 EVALUATION OF SEVERE ACCIDENT FOR r@ LEVF, As 2OAC1wE WASTE DISPOSAL IN RISKS: QUANTIFICATON OF MAJOR INPUT PARAMETERS Emperts' 1

UNSATURATEDfRACTURED TUFF, Determination O. Containment Loads And Molten Core Containment interact 6on Issues.

NUREG/C45654. CONTAINMENT VENTING ANALYSIS FOR THE GRANT T.

SHOREHAM NUCLEAR POWER STATION NUREG/CR 5784. FITNESS FOR DUTY IN THE NUCLEAR POWER GARBOCZl,E.J.

INDUSTRY.A Heview C4 The Fust Year Of Program Performance And NUREGICA 5727: CHLORIDE ION DIFFUSION IN LOW WATER.TO' An Update Of The Tectwcal Issues.

SOUD CEMENT PASTES GRE E N.E.R.

GELDARD,F.

NOREG/CR4469 V11: NONDESTRUCTIVE EXAMINATION (NDE) REll-NUREG/CR 5715 REFERENCE MANUA'. TOR THE CONT AIN 1.1 ABILITY FOR INSERVICE INSPECTION OF UGHT. WATER CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS HEACTORS. Semi Annual Report, ApnhSeptember 1989 OHADIAU.N.

GREENE.S.R.

NUREG/CR.4599 Vol N1: SHORT CRACK $ IN F < ING AND PIPING NUREG/CR.5565: THE RESPONSE OF BWR MARK 11 CONTAINMENTS WELDS Semiannual Report, March-September 1990.

TO STATON BLACKOur SEVERE ACCOENT SEQUENCES NUREG/CR 5571: THE RESPONSE OF BWR MARK lli CONTAIN.

E /C45630: PWR DRY CONTAINVENT PARAMETR;C STUDIES, NUREG/CR-5715. RE' AENCE MANUAL FOR THE CONT AIN t.t SEQUENCES.

CODE FOR CONTAmMENT SEVERE ACCIDENT ANALYS!S.

NUREG/CR 5623. BWR MARK 11 EXNESSEL CORIUM INTER ACTION ANALYSES.

GILBERT,D.W.

NUREG/C43916: PRESSURIZED MELT EJECTION INTO WATER GRE ENWOLL,0.A, W LS NUREG/CR 572t VIDEO SYSTEMS FOR ALARM ASSESSVENT.

GILBENT.E.S.

GREER,W.B.

NUREG/CR4214 R1PjA1: HEALTH EFFECTS MODELS FOR NUCLE..

NUREG/CR.5684-ANALYSES AND FIELD TESTS OF THE HYDRAUUC AR POWER PLANT ACCIDENT CONSEQUENCE PERIORMANCE OF CEMENT GROUT BOREHOLE SFALS.

ANALYSIS Mov', cations Of Modols Resuning From Recent Reports On Health Ette% Of lorumg Radiation. Low LET RadiatiortPar* 11: Scientif.

GREGG R.E.

• Ow. For Health...

NUREG/CR5717. PACKAGING SUPPUER INSPECTION GUIDE.

GINSBERG,T.

GREGORY,J.J.

NUR5G/CR-5282; ESTIMATION OF CONTAINMENT PRESQRE LOAD-NUREG/CR-4551 V2RtP2: EVALUATON OF SEVERE ACCIDENT ING DUE TO DIRECT CONTAINMENT HEAilNG FOR THE ZION PLANT RISKS: QUANTIFICATION OF MAJOR INPUT PA9AMETERS Euperts' NUREG/CR 5620. THATCH: A COMPUTER CODE FOR MODELLMG -

Deterrnination Of Containtnent Loads And Molten Core Contaenment THERMAL NETWORKS OF HIGH. TEMPERATURE GAS-COOLED NU' Interaction it;ues.

CLEAR REACTORS.

NUREGICR 5630: PWR DRV CONTAINMENT PARAMETRIC STUDIES.

GLENN.W.L.

GREGORY,G.H.

NUREG-1415 V04 Nol: OFFICE OF THE INSPECTOR NUREG/C45611: ISSUES AND APPROACHES FOR USING EQUIP.

GENERALSemiannual Report ApnhSeptember 1991.

MENT REUABiUTY ALERT LEVELS.

GLISSMEYER J.A.

GRE!M ANN,L.

NUREG/CR4757; LINE-LOSS DETERMINATON FOR AIR SAMPLER NUREG/CR5561: ANALYSIS OF BELLOWS EXPANSION JOINTS IN SYSTEMS.

THE SEQUOYAH CONTAINMENT.

GLOUDEM ANS J.R.

CRIFFITH,P, NUREG/CR-5305 V00 MULTILOOP INTEGRAL SYSTEM TEST NUREG/CR5809 DRF FC: AN INTEGRATED STRUCTURE AND SCAL.

(MIST) FINAL REPORT Summary NUREG/C45670 MULTILOOP INTEGRAL SYSTEM TEST (M:ST) MIST ING METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE FACluTY FUNCTIONAL SPECIFICATION RESOLUTION Draft Report For Comment.

GOOD,M.S.

GRIFFITH,R.O.

NUREG/CR.4469 Vi t: NONDESTRUCTIVE EXAMINATION (NDE) RELL NUREG/C45715: REFERENCE MANUAL FOR THE CONTAIN 1.1 ADIUTY FOR INSERVICE INSPECTON OF UGHT WATER CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS.

REACTORS SembAnnual Report, ApnhSeptember 1989' NUREGICR.5728: EXPER;MENTS TO INVESTIGATE 'HE EFFECT OF.

FUGHT PATH CN DIRECT CONTMNMENT HEATN (DCH) IN THE GOODRICH M.T.

SURTSEY TEST FACILITY,The Umited Flight Path (LL ; Tests NUREG/C45537: APPROACHES FOR THE VAUDATION OF MODELS USED FOR PERFORMANCE ASSESSMENT OF HtGH-LEVEL Nt9.E-GRIMLEY.A.J.

AR WASTE REPOSITORIES.

NUREG/CR5312: A TH7AMOOYNxMIC MODEL OF FUEL DISRUP.

TION IN ST.I.

GOOLD,R E.

NUAEG/CR-5690: PHYSICAL FITNESS TRAINING REFERENCE GRIMSHAW,C.A.

MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE FA-NUREG/CR5282: ESTWATION OF CONTAtNMENT PRESSURE LOAD-CluTIES POSSESSING FORMULA QUANTITIES OF SPECIAL NU-ING DUE TO DIRECT CONTAINMEtiT HEATING FOR THE ZION CLEAR MATERIALS-PtANT.

i

.. l

s Personal Author Index 57 GU,B.

HEAL 7ER,J.M.

NUREG/CR 5464 ANION RETENTON IN SOIL POSSIBLE APPLICA NUREG/CR 5809 DAF F C: AN INTEGRATED STRUCTURE AND SCAL.

TION TO REDUCE MITOhATION OF BURIED TECHNETIUM AND ING METHODOLOGY FOR SEVERE ACCOENT TECHNICAL ISSUE ODINE A Review RESOLUTON Draft Report For Comment.

GUNTHER W.

HEASLER,P.G.

NUREG/CR.5555 AGING ASSESSMENT Or THE WEstlNGHOUSE NUREG/CR4469 Vit: NONDESTRUCTIVE EXAMINATION (NDC) REll-PWR CONTROL ROD DRIVE SYSTEM ADILITY FOR INSERVICE INSPECTON OF LIGHT WATER gp REACTOR $ Some Annual Report Apr4 Septemtww 1989 NUREG-1439 STAFF TECHNICAL POSITON ON REGULATORY CON-HEDGES,D.

SOERATONS IN THE DEStON AND CONSTRUCTION OF THE EX-PLORATORY SHAFT FACILITY-NUREG.1293 R01: QUAUTY ASSURANCE GUCANCE FOR A LOW.

LEVEL HADCACTIVE WASTE DISPOSAL FACILITY.

HABE R.S.B.

HEISELMANN.H.W.

NUREG/CR 5538 V01: INFLUENCE OF ORGANIZATIONAL FACTORS NUREG/CR 5167: COST /DENEFIT ANALYSIS FOR GENERIC ISSUE ON PERFORMANCE RELIABILITY.Overwow And Deta4ed Vethodo.

logical Developmmt 23 REACTOR COOLANT PUMP SEAL F ALLURE.

HABIS,T.F.

HENNICK.A.

NUREG/CR-5670 MULTILOOP INTEGRAL SYSTEM TEST (MIST) MIST NUREG/CR 4666 CLOSEOUT OF IE BULLETIN 84 02. FAILURES OF FACILITY FUNCTIONAL SPECIFICATION.

GENERAL ELECTRIC TYPE HFA RELAYS IN USE IN CLASS 1E SAFETY SYSTEMS.

H ACK ETT.E.M.

NUREG/CR-5285: CLOSEOUT OF IE BULLETIN 7913: CRACKING IN F

A R SYSTFM P G

NUREG/CR-5577. EXTENSION AND EXTRAPOLATION OF J-R g

ES AND THEIR APPLICATION TO THE LOW UPPER SHELF SAFETY FEATURE (CSF) RESET CONTROLS.

NUREG/CR-5309. CLOSEOUT OF IE BULLETIN B3-07: APPARENTLY HAGEMEYER,D.

FRAUDULENT PRODUCTS SOLD BY RAY MILLER,1NC.

NUREG-0713 Vio-OCCUPATONAL RADIATION EXPOSURE AT COM-

" ^

^

• ER R

TORS AND OTHER NUR G/CR-5809 DRF FC-AN INTEGRATED STRUCTURE AND SCAL.

Ci T ES 8 en F n

NUREG/CR4690 VO)

R1:

GENERIC COMMUNICATONS ING METHODOLOGY FOR SEVERE ACCOENT TECHNICAL ISSUE INDEX Listmgs Of Communications 1971 1989 RESOLUTONPratt Reprwt For Comment.

HAMMOND,G.A.

HETZER.D.C.

NUREG/CR.5734. RECOMMENDATIONS TO THE NRC ON ACCEPTA, NUREG/CR-5343. RADONUCLIDE CHARACTERIZATION OF REAC-BLE STANDARD FORMAT AND CONTENT FOR THE FUNDAMEN.

TOR DECOMMISSIONING WASTE AND SPENT FUEL ASSEMBLY TAL NUCLEAR MATERIAL CONTROL (FNMC) PLAN REQUIRED FOR HARDWARE. Progress Report LOW ENRICHED URANIUM ENRICHMENT FACILITIES HICKEY,E E.

HANSON.D.J.

NUREG-1400 DRFT FC: AIR SAMPLING IN THE WORKPLACE. Draft NUREG/CR-5543. A SYSTEMATIC PROCESS FOR DEVELOPING AND Report For Comment.

ASSESSING ACCIDENT MANAGEMENT PLANS.

NUREG/CR-5691: INSTRUMENTATION AVAILABILITY FOR A PRES.

H4C KS,P.D.

SURIZED WATER REACTOR WITH A LARGE DRY CONTAINMENT NUREG/CR4667 V12: ENVIRONMENTALLY ASSISTED CRACKING IN DURING SEVERE ACCOENTS.

LIGHT WATER REACTORS. Semiannual Report. October 1990. March

. NUPEG/CR 5702. ACCIDENT MANAGEMENT INFORMATION NEEDS 1991.

FOR A BWR WITH A MARK 1 CONTAINMENT.

HANSON,R.T.

NUREG-1377 R02: NRC RESEARCH PROGRAM ON PLANT AGING:

NUREG/CR-5522: A COMPARISON OF PARAMETER ESTIMATION LISTING AND SUMMARIES OF REPORTS ISSUED THROUGH JUNE AND SENSITIVITY ANALYSIS TECHNIQUES AND THEIR IMPACT ON 1991.

THE UNCERTAINTY IN GROUND WATER FLOW MODEL PREDIC.

TIONS HILLS.flG-NUREG/CR-5716: MODEL VALIDATON AT THE LAS CRUCES HARPE R,F.T.

TRENCH GlTE.

NUREG/CR 4551 V2 RIP 2: EVALUATON OF SEVERE ACCIDENT RISKS-QUANTIFICATON OF MAJOR INPUT PARAMETERS Experts-HISER,A.L.

Determmation Of Containment Loads And Molten Core Containment NUREG.1426 Vot; COMPILATION OF REPORTS FROM RESEARCH Inte+ action issues.

SUPPORTED BY THE MA1ERIALS ENGINEERING BRANCH. DIVISION OF ENGINEERING. 1965 - 1990.

HARPER,al.R.

NUREG/CP 0037. PROCEEDINGS OF THE SEMINAR ON ASSESS-NUREG 1022 ROI DR FC: EVENT REPORTING SYSTEMS to CFR MENT OF FRACTURE PREDICTION TECHNOLOGY: PlPING AND 50 72 AND 50.73 Clantication Of NRC Systems And Guidelines for PRESSURE VESSELS Reportmg Draft Report For Comment HOGE.S.A.

HARRIS,C L NUREG/CR-5565. THE RESPONSE OF BWR MARK ll CONTAINMENTS NUREG/CR-5518 QUAUTY ASSURANCE PROCEDURES FOR THE TO STAHON BLACKOUT SEVERE ACCIDENT SEQUENCES.

CONTA.N SEVERE REACTOR ACCOENT COMPtfTER CODE.

NUF;EG/CR.5571: THE RESPONSE OF BWR MARK lli CONTAIN-HARTFIELD,R.A.

MENTS TO SHORT. TERM STATION BLACKOUT SEVERE ACCIDENT SEQUENCES.

NUREG-0020 V15: LICENSED OPERATING REACTORS STATUS SUM-MARY REPORT Data As Of December 31,1990.(Gray Book !)

HOF M AYER.C.H.

HAUTH,J.

NUREG/CR-4650 V04: SEISMIC FRAGILITY OF NUCLEAR POWER NUREG/CFr5784: FITNESS FOR DUTY IN THE NUCLEAR POWER PLANT COMPONENTS (*HASE 11) A Fragility Handbook On Eighteen Components.

INDUSTRY.A Review Of The Fwst Year Of Program Ps-formance And NUREG/CR-4887: RELAY TEST PROGRAM.Senes i Vibraton Tests.

An Update Of The Technical lanues.

NUREG/CR-55S5: THE HIGH LEVEL VIBRATION TEST PROGRAM. Final HAY NES,H.D.

NUREG/CR 4302 V02: AG!NG AND SERVICE WEAR Or CHECK HOLFORD D.J.

VALVES USED IN ENGINEERED SAFETY-FEATURE SYSTEMS OF NUREG/CR-5714: HYDROGEOLOGIC PERFORMANCE ASSESSMENT NUCLEAR POWER PLANTS,Agmg Assessments And Monitonng ANALYSIS OF THE LOW LEVEL RADIOACTIVE WASTE DISPOSAL Method Evaluatens.

FACILITY NEAR SHEFFIELD, ILUNOIS.

58 Personal Author Index HORZ,R.C.

J AC KSON.J.E.

NUREG/CR 5432 V02 RECOMMENDATIONS TO THE NPC FOR SOIL NUREG-1401 DRFT FC REGULATORY ANALYSIS FOR GENERIC COVER SYSTEMS OVER URANIUM MILL TAILINGS AND LOW-ISSUE 23. REACTOR COOLANT PUMP SEAL FAILURE. Draft Report LEVEL RADCACTIVE WASTES Laboratory And Feld Tests For Sod For Comment Covers.

JACOBUS.M.J.

HOSTETLER,C.J.

NUREG/CR 5655. SUBMERGENCE AND HIGH TfMPERATLRE STEAM NUREG/CR.5714. HYDROGEOLOGIC PERFORMANCE ASSESSMENT TESTING OF CLASS tE ELECTRtCAL CABLES.

ANALYSIS OF THE LO4 LEVEL RADIOACTIVE W ASTE DISPOSAL FACILITY NEAR SHEFFIELD, ILLINOIS.

J A E.M.

HSi[H B.J-NUREG/C45780-

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-DENT MANAGEMENT FOR BWRS.

NUREG/CR 57b7. VERIFICATON OF PlPING FOSPONSE CALCULA' NUREG/CR 5781:

SUMMARY

OF A WORKSHOP ON SEVERE ACCl, TON OF SMACS CODE WITH DATA FROM SEISMIC TESTING OF DENT MANAGEMENT FOR PWRS AN IN PLANT PIPING SYSTEM JENG.D.

Nb d/CR-5771: PROSADIUTY AND CONSEQUENCES OF M:SLOAD-NUREG-1407; PROCEDURAL AND SUDMITTAL GUIDANCE FOR INDI-ING FUEL IN A PWR-VOUAL PLANT EXAMINATION OF EXTERNAt EVENTS (IPEEE) FOR SEVERE ACCIDENT vulNERABluTIES Final Report HSU,F'EG/CR 5612: DEGRADATON MODEUNG WITH APPLICATION TO NUR JOHNS ND AGING AND MAWTENANCE EFFECTIVENESS EVALUATONS.

NETWORK. Annual Report For Apnl 1989 March 1990.

HU ANG,P.H.

NUREG/CR 5711: ASSESSMENT OF UNCERTAINTIES IN MEASURE.

JONES,K.R.

MENT OF PH IN HOSTILE ENVIRONMENTS CHARACTERISTIC OF NUREG/C45529. AN ASSESSMENT OF BWR MARK lli CONTAIN-NUCLF AR REPOSITORIES.

MENT CHALLENGES, F AILURE MODES, AND POTENTIAL IMPROVE-MENTS IN PERFORMANCE HUBER.D.S.

NUREG/CR-5667; INEL PERSONAL COMPUTER VERSION OF MACCS NUREG-1416 V04 N01; OFFICE OF THF INSPECTOR 1.5.

GENERAL.Semeannual RertApnFSeptember 1991, JOURNEL,A,0.

HUGHES,A A.

NUREG/CR-5639: UNCERTAINTY EVALUATON METHODS FOR NUREG/CR 5382: SCREENING OF GENERIC SAFETY ISSUES FOR U' WASTE PACKAGE PERFORMANCE ASSESSMENT.

CENSE RENEWAL CONSIDERATIONS, HUMPHRIES,DA JOY,D.

NUREG-0430 VIO:

UCENSED FUEL FACiUTY STATUS NUREG/CR-5682 CPEClFIC TOPtCS IN SEVERf ACCOENT MANAGE' MENT.

REPORT. inventory Difference Data. July 1989 June 1990(Gray Book gi)

HUNT.P.

NUREG/CR-5784. FITNESS FOR DUTY IN THE NUCLEAR POWER JOYCW INDUSTRY.A Rewew Of The First Year Of Program Performance Ants NUREG/C45577. EXTENSION AND EXTRAPOLATON OF J-R An Update Of The Techna;al Issues CURVES AND THE18 APPUCATION TO THE LOW UPPER SHELF TOUGHNESS ISSUE.

HUTTON P.H.

NSERVICE OR C-F S

NU EG/CR-5520: PROCEDURES GUIDE FOR FXTRACTING AND LOADING PROBADILISTIC RISK ASSESSMENT DATA INTO MAR D HUYAKORN,P.S.

USING IRRAS 2.5 NURE /CR.5352 R01: VAM2D VARIABLY SATURATED ANALYSIS MODEL IN TWO DIMENSIONS. Versson 5.2 With Hysterests And Chain KAM,F B.K-Decay Transport Documentation And User's Guide.

NUREG/C44816 R01: PR-EDB. POWER REACTOR EMBRITTLEMENT DAT A RASE,VER$10N 1. Program Desenption.

HY M AN,C.R.

NUREG/C4564B: TRANSPORT CALCULATIONS OF NEUTRON NUREG/C45565: THE RESPONSE OF BWR MARK 11 CONTAINMENTS TRANSMISSON THROUGH STEEL USING ENDF/B V, REVISED TO STATON BLACKOUT SEVERE ACCIDENT SEQUEN"ES ENDF/B V.AND ENDr/4VI 1RON EVALUATIONS.

NUHEG/CR 5"71: THE RESPONSE OF BWR MARK lil CONTAIN-MENTS TO SHORT. TERM STATION BLACKOUT SEVERE ACCOENT KAN A,D.D.

SEQUENCES NUREGIC45440: CRITICAL ASSESSMENT OF SEISMIC AND GEOME-NUREG/CR 5623. BWR MARK 11 EX VESSEL CORIUM INTERACTION CHANICS UTERATURE RELATED TO A HIGH LEVEL NUCLEAR ANALYSES-WASTE UNDERGROUND REPOSITORY.

IMBRO,E.V.

KAPLAN,E.

NUREG-1397. AN ASSESSMENT OF DESIGN CONTROL PRACTICES AND DESIGN RECONSTITUTION PROGRAMS IN THE NUCLEAR NUREG/C45798-PILOT PROGRAM TO ASSESS PROPOSED BASIC POWER tNDUSTRY.

QUAUTY ASSURANCE FIEOUIREMENTS IN THE MEDICAL USE OF BYPRODUCT MAT 6AIAL INABA.K.

I M NUREG/CR 5666: PROGRAMMATIC ROOT CAUSE ANALYSIS OF NUREGM' -4659 M SEM NM N EN WR MAINTENANCE PERSONNEL PERFORMANCE PROBLEMS' PLANT COMPONENTS (PHASE It).A Fragibty Handoook On Eighteen INTE RR ANTE.C.G.

Components.

NUREG/CR-4735 V07; EVALUATION Q COMPILATION OF DOE K ASSNER T.F.

WASTE PACKAGE TEST DATA. Biennual Report: February-July 1989 NUR IRWIN,0.R.

UGHT WATER REACTORS. Semiannual Report,Apnt-September 1989.

NUREG/CR-5697; USE OF THICKNESS REDUCTION TO ESTIMATE NUREG/CR-4667 Vit: ENVIRONMENTALLY ASSibiED CRACKING IN VALUES OF K.

UGHT WATER REACTORS. Sotsannual Report,Apnt-September 1990.

NUREG/CH-5703 LOWER-BOUND INITIATON TOUGHNESS WITH A NUREG/CR-4667 V12: ENVIRONMENTALLY ASSISTED CRACKING IN MODIFIED CHARPY SPECIMEN..

UGHT WATER REACTORS. Semiannual Report,0ctc5er 1990 - March ISHilM.

NUREG/CR-5809 ORF FC: AN INTEGRATED STRUCTURE AND SCAL.

KASTENBERG,WL lNG METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE NUREG/CR-5780*

SUMMARY

OF A WORKSHOP ON SEVERE ACCl-RESOLUTION Dra4 Report For Comment.

DENT MANAGEMENT FOR BWRS.

Personal Author index 59 NUREGICR 578t

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-KNUDSON.D.L DENT MANAGEMENT FOR PWRS NUREG/CR-5667. INEL PERSONAL COMPUTER VERS'ON OF MACCS KEENEY WALKER NUREG/CR-5592 ANALYTICAL STUDIES OF TRANSVERSE STRAIN KOHUT P.

EFFECTS ON FRACTURE TOUGHNESS FOR CIRCUMFERENTIALLY NUREG/CR-5526 ANALYSIS OF RISK REDUCTION MEASURES AFL ORIENTED CRACKS PLIED TO SHARED ESSENTIAL SERVtCE WATER SYSTEMS AT NUREC/CR 5650 AN INVESTIGATION OF CRACK.TiP STRESS FIELD MULTI UNIT SITES, CRITERIA FOR PREDICTING CLEAVAGE-CRACK INITIATION.

KOKSAL C.G.

KELLY.D.L NJREG/CR-5670: MULTILOOP INTEGRAL SYSTEM TEST (MIST) MIST NUREGICR-5529 AN ASSESSMENT OF BWR MARK lli CONTA N RCIUTY FUNCTIONAL SPECIFICATION MENT CHALLENGES. F AILURE MODES. AND POTENTIAL IMPROVE.'

MENTS IN PERFORMANCE KONDK;NF, NUREG/CR-5654 CONT AINMENT VENTING ANALYSIS FOR THE NUREG 1377 R02: Nk nESEARCH PROGRAM ON PLANT AGING-SHOREHAM NUCLEAR POWER STATON-USTIN"a AND SUMMARIES OF REPORTS ISSUED TelROUGH JUNE KELLY,0 B.

l#

NUREG 1407. PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDI-KOOLJ.B.

VOUAL PLANT EXAM > NATION OF EXTERNAL EVENTS OPEEE) FOR NUREGJCR-5M2 RO1: VAM2D - VARIABLY SATURATED ANALYSIS Si: VERE ACCOENT VULNERADIUTIES Final Report-MODEL IN TWO OtMENSIONS. Version 5 2 With Hysteresis And Chain CIELLY,J.E*

Decay Transport Occumentation And User's Guide.

NUREG/CR-579t CROUND WATER FLOW AND TRANSDORT MODEL-NUREG/CR 5531 MELCOR 1.8 0 A COMPUTER CODE FOR NUCLEAR REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS-ING OF THE NRC-UCENSED WASTE DISPOSAL FACluTY, WEST MENT ANALYSES.

VALLEY NEW YORK.

NUREG/CR-5795: VALIDATION AND TESTING OF THE VAM2D COM-CIEMNER,M.L.

PUTER CODE.

NUREG/CR 5714 HYDROGEOLOGIC PERFORMANCE ASSESSMENT KOT C A

^

^

Al NUREG/C45757: VERIFICATION OF PIPING RESPONSE CALCULA.

ACIL TY N AR SHEF i OL S

NUREG/CR 5h.f. HYDROGEOLOGIC PERFORMANCE ASSESSMENT TION OF SMACS CODE WITH DATA FROM SEISMIC TESTING OF ANALYSIS OF THE COMMERCIAL LOW-LEVEL RADIQACTIVE AN IN-PLANT PIPING SYSTEM.

W ASTE DISPOSAL FACluTY NEAR WEST VALL EY,NEW YORK.

KOZAK,M.W.

CIENN E ALLY,R.M.

NURFG/CR-5539: A SELF TEACHING CURRICULUM FOR THE NRC/

NUFEG 1407. PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDI, SNL LOW LEVEL WASTE PERFORMANCE ASSESSMENT METHOD-VOUAL PLANT EXAMINATION OF EXTERNAL EVENTS (1PEEE) FOR OL N SEVERE ACCIDENT VULNERABluTIES Final Report.

KREIDER,K.G.

KENNETT,R.J.

NUREG/CP-5711: ASSESSMENT OF UNCERTAINTIES IN MEASURE.

NUREG/CR 5622 THATCH A COMPUTER CODE FOR MODELUNG MENT OF PH IN HOSTILE ENVIRONMEN S CHARACTERISTIC OF THERMAL NETWORKS OF HIGH-TEMPERATURE GAS-COOLED NU.

NUCLEAR REPOSITORIES.

CLEAR REACTORS KREINER S.

CIHAN,T.A.

NUREG/CR-5550- PASSIVE NONDESTRUCTIVE ASSAY OF NUCLEAR CUREG/CR-3469 V06. OCCUPATIONAL DOSE REDUCTION AT NU.

MATERIALS.

CLEAR POWER PLANTS ANNOTATED BIBLIOGRAPHY OF SELECT.

ED READINGS IN RADIATION PROTECTION AND ALAR A.

KRESS.T.S.

NU9EGICR 5133 OOSE REDUCTION TECHNIQUES FOR HIGH-DOSE NUREGICR-5732 DRF FC: LODINE CHEMICAL FORMS IN LWR WORKER GROUPS IN NUCLEAR POWER PLANTS SEVERE ACCIDENTS Draft Report For Comment KIDO C.

KRISHNASWAMY,P, NUREG/CR-5717. PACKAGING SUPPLIER INSPECTION GUIDE.

NUREG/CR-4599 V01 N1: SHORT CRACKS IN PIPING AND PIPING WELDS Semiannual Report, MarchSeptember 1990.

NUREG/CR 5641 STUOY OF OPERATIONAL RISK-BASED CONFIG).

KROEGER,P.G.

RATION CONTROL NUREG/CR-5620: THATCH: A COMPUTER CODE FOR MODELUNG THERMAL NETWORKS OF HIGH-TEMPERATURE GAS-COOLED NU-KIMBRELLA.F, CLEAR REACTORS.

NUREGICR-5432 V03. RECOMMENDATIONS TO THE NRC FOR SOIL COVER SYSTEMS OVER URAN 1UM MILL TAIUNGS AND LOW.

KURTH R.E.

LEVEL RADtOACTIVE WASTES. Construction Methods And Guidance NUREG/CR-5695: A PROCESS FOR RISK. FOCUSED MAINTENANCE.

For Seahng Penetrations In Scel Covers KING.T.L NUREG/CR-5645 ACOUSTIC EMIS$10N/ FLAW RELATIONSHIPS FOR NUREG-1369: PREAPPLICATION SAFETY EVALUATION REPORT FOR INSERVICE MONITORING OF LWRS.

THE SODIUM ADVANCED FAST REACTOR (SAFR) UQUO METAL REACTOR.

LAFORGE,R.

NUREGiCR-3145 V09: GEOPHYSICAL INVESTIGATIONS OF THC KIRBY,LJ.

WESTERN OHC-INDIANA REGON. Annual ReporLOctober 1980 NUREG/CR-4070: RADONUCUDE DISTRIBUTIONS AND MIGRATION September 1990, MECHANISMS AT SHALLOW LAND BURIAL SITESPir,al Report Of PNL Research Investigations On The Distnbution, Migrahon, And Con.

LAMBRIGHT,J.A.

tainment Of Radionuclides Al Maxey Flats Kentucky, NUREG/CR 5606 A REVIEW OF THE SOUTH TEXAS PROJECT PROB-ABn.lSTIC SAFETY ANALYSIS FOR ACCIDENT FREQUENCY ESTI-KLOEHN.BA.

MATES AND CONTAINMENT BINNING.

NUREGICA-5288 CLOSEOUT OF lE BULLETIN 80-06-ENGINEERED SAFETY FEATURE (ESF) RESET CONTROLS.

LANDE S,J.D.

NUREG/CR 5651: AN INVESTIGATON OF CRACK TIP STRESS FIELD K N AS,LL CRITERIA FOR PREDICTING CLEAVAGE CRACK INITIATION.

NUREG/CR435-SELECTION OF SILICEOUS AGGREGATE FOR CONCRETEc LANDOW,M.

NUREG/CR5727: CHLORIDE ION DIFFUSON IN LOW WATER-TO.

NUREGICR-4599 V01 N1 SHORT CRACKS IN PIPING AND PIPING SOUD CEMENT PASTES.

WELDS. Semiannual Report, March-Septemcer 1990.

a

I 60 Personal Author indes LANDRY,R.R.

MAHLUM.D.D.

NUREG.136ir PREAPPUCATON SAFFTY EVALUAflON REPORT FOR NUREG /CR4669 EVALUATION OF EXPOSURE UM:TS TO TOoc THE SODIUM ADVANCED FAS1 REACTOR (SAFR) LIOUlO METAL GASES FOR NUCLEAR REACTOR CONTROL ROOM OPERATORS.

REACTOR M ARSCH ALL C.W.

LANE,S.G.

NUREGICR 4509 V01 N1: SHORT CRACKS IN PlPING AND PIPING NUREG/CR-3469 V06 OCCUPATIONAL DOSE REDUCTION AT WELDS.Semiannua! Report. March September 1990.

CLEAR POWER PLANTS. ANNOTATED BIBLOGRAPHY OF SELECI.

ED RE ADINGS IN RADIATION PROTECTION AND ALARA.

MARTIN RL NUREG/CE-4911; INCENTIVE REGULATION OF NUCLEAR POWER LEE,C E.

PLANTS BY STATE REGULATORS NUREGICR 5536 DCM3D: A DUAL-CONTINUUM, THREEDML

/N' NUREG/CR.5784. FITNESS FOR DUTY IN THE NUCLEAR POWER AL, GROUND-W ATER FLOW CODE FOR UNSATURATED, FRAC.

INDUSTRY.A Review Of The Frit Year Of Program Pedormance And TURED, POROUS MEDIA.

An Update Of The Technecal Issues LEHNE R.J.R.

MARTIN,R.P.

NUREG/CR 5634. (DENTIFICATON AND ASSESSMENT OF CONTAIN' NUREGICR-5663: RELAPS THERMAL HYDRAUUC ANALYSIS OF THL MENT AND RELEASE MANAGEMENT STRATEGlE3 FOR A BWR WNP1 PRESSURIZED WATER RE ACTOR.

MARK i CONTAINMENT.

NUREG/CR 5707: APPUCATON OF CONTAINMENT.AND RELEASE M ATTER.J.C.

MANAGEMENT TO A PWR ICE-CONDENSER PLANT' RE AND SCAL-NUREG/CR 5809 DAF FC: AN INTEGRATED STRUCTU NUREGICR 5721; VOEO SYSTEMS FOR ALARM ASSESSMENT HUREGICR 5722 INTERtOR INTRUSION DETECTION SYSTEMS ING METHODOLOGY FOR SEVERE ACCIDENT TECHN! CAL ISSUE NUREG/CR5723-SECURITY SYSTEM SIGNAL SUPERVISION.

RESOLUTION Draft Report For Comment M AY FIELD.M.E.

UR'LG[CR 5616. USER'S MANUAL FOR THE NEFTRAN 11 COMPUT*

NURMm3h mMMS & M SNAR % ASSEM-ER CODE-MENT OF FRACTURE PREDICTON. TECHNOLOGY: P1 PING AND PRESSURE VESSELS, LEUNG,V..

NUREG-1421. REGULATORY ANALYSIS FOR THE RESOLUTON OF MAZETIS,G.

GENERIC ISSUE 130: ESSENTIAL SERVICE WATER SYSTEM Fall.

NUREG 1421: REGULATORY ANALYSIS FOR THE RESOLUTON OF URES AT MULTl-UNIT SITES, GENERIC ISSUE 130 ESSENTIAL SERVICE WATER SYSTEM FAIL-URES AT MULTI-UNIT SITES.

LEVIN,A.E.

NUREG/CR-5623: BWR MARK 11 Ex-VESSEL CORIUM INTERACTION '

MCCONNELL,J.W.

ANALYSES NUREG/CR-5601 EFFECTS OF PH ON THE RELEASE OF RADIONU-CLIDES AND CHELATING AGENTS FROM CEMENT SOUDIFIED DE.

LE VY,S.

CONTAMINATION ON-EXCHANGE RESINS COLLECTED TROM OP.

NUREG/CR-5809 DAF FC AN INTEGRATED STRUCTURE AND SCAL.

ERATING NUCLEAR POWER STATONS ING METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE RESOLUTION Draft Report For Comment MCCRACKEN C.

NUREG-1407; PROCEDURAL AND SUEMITTAL GUIDANCE FOR INDI-N Ea

.R 5768. tCE CONDENSER AEROSOL TESTS SEVERE ACCIDENT VULNERABlVTIES Final Report LIM.H A

H N VERE Am

$A DN MAN EMEN FCR D RS NURE /GR$

DRF FC: DEPOSITION SOFTWARE TO CALCULATE NUREG/CR-5781:

SUMMARY

OF A WORKSIOP ON SEVERE ACCI.

PARTICLE PENETRATION - THROUGH AEROSOL TRANSPORT DENT MANAGEMENT FOR PWRS.

LINES Draft Report For Corwent LIN,C.C.

MCGUIRE,S.A.

NUREGtC45034 IDENTIFICATION AND ASSESSMENT OF CONTAIN, NUREG-1391: CHEMICAL TOUCITY OF URANIUM HEXAFLUORIDE MENT AND RELEASE MANAGEMENT STRATEGIES FOR % SWR COMPARED TO ACUTE EFFECTS OF RADIATION Final Report.

MARK i CONTAINMENT.

NUREG-1400 DRFT FC: AIR SAMPUNG IN THE WORKPLACE Draft a

Report For Comment LOFGREN,E.V.

NUREG/CR-5611: ISSUES AND APPROACHES FOR USING EQUIP, MCISAAC.C.V.

MENT REUA81UTY ALERT LEVELS NUREG/CR5001: EFFECTS OF PH ON THE R6 LEASE OF RADONU-NUREGICR 5695: A PROCESS FOR R!SK FOCUSED MAINTENANCE.

CUDES AND CHELATING AGENTS FROM CEMENT.SOLIOlFIED DE-LONGSINE.DI.

CONTAMINATION ON EXCHANGE RESINS COLLECTED FROM OP-

. ERATING NUCLEAR POWER STATIONS NUREGICR-5618 USER'S MANUAL FOR THE NEFTRAN 11 COMPUT*

NUREG!CR-5672 VOI: CHARACTERISTICS OF LOW-LEVEL RADIOAC-ER CODE' TIVE WASTE. Decontaminat on Waste Annual Report For Fiscal Year LOPE 2,B.

1990.

NUREG/CR 5595. FORECAST: REGULATORY EFFECTS COST ANALY.

SIS SOFTW ARE MANUAL Verman 3.0 N RE'G CR5300 V01: INTEGRATED REUABluTV AND RISK ANALY-LORE N2,R.A.

SIS SYSTEM (IRRAS) VERSION 2.5 Reference Manual NUREG/CR-5481: DATA

SUMMARY

REFORT FOR FISSON PRODUCT RELEASE TEST VI-4 MCMULt EN,R.

NUREG/CR-5668. DATA

SUMMARY

REPORT FOR FISSION PRODUCT NUREG-0675 S34. SAFDY EVALUATON REPORT RELATED TO THE RELEASE TEST VI-5.

OPERATION OF DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2. Docket Nos 50 275 And 50-323(Pacific Gas And Electr'c LOUtE,DLY.

Company)

NUREG/CR4718 REFERENCE MANUAL FOR THE CONTAIN 11 CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS.

MCNAMARA,N.

NUREG-0837 V10 N04, NRC TLD DIRECT RADIATION MONITORING -

M ACAULAY J.

NETWORK. Progress Report. October December 1990.

NUREG/CR5758 VOI: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG-0837 V11 Not: NRC TLD DIRECT RADIATION MONITORING INDUSTRY. Annual Summary Of Program Performance Reports,CY

. NF.TWORK Progress Report January. March 1991.

1990 NUHEG-0837 Vit NO2: NRC TLD DIRECT RADIATON MONITORING NUREG/CR 578r FITNESS FOR DUTY IN THE NUCLEAA POWER NETWORK. Progress Report. Apni,. lune 1991.

INDUSTRY A Review Of Tle First Year Of Program Performance And NUREG 0837 V11 NO3: NRL TLD DIRECf RAD ATION MONITORING An Update Of The TectvwcalIssues NETWORK. Progress Report July-September,1991.

Personal Author index 61 ECSHANE M C.

WOODY-FJ.

NUREG/CR 4670 RADIONUCLIDE DISTRtBUTONS AND MtGR ATON NUREG/CR-5809 DRF FO AN INTEGRATED STRUCTURE AND SCAL-MECHANISMS AT SHALLOW LAND BURIAL SITES Final Report Of ING METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE PNL Research Investigat:ons On The Distntution. Migration. And Con-RESOLUTON Drmit Report For Comment.

tainment Of Radionuclides At Maiey Flats. Kentucky.

MOORE,C.

MEERTA NUREG/CR-5784. FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-3145 V09 GEOPHYSICAL INVESTIGATONS OF THE INDUSTRY A Review Of The Fe( Year Of Program Periormance And WESTERN OHOINDIANA REGION Annual Report October 1989 An Update Of The Technical issues September 1990 MORAN B.W.

MEINHOLD.C.B.

NUREG/CR 5734. RECOMMENDATIONS TO THE NRC ON ACCEPTA.

NUREG/CR-4444: RADIATON SAFETY ISSUES RELATED TO RADO-BLE STANDARD FORMAT AND CONTENT FOR THE FUNDAMEN.

LARELED ANTIBODIES TAL NUCLE AR MATERIAL CONTROL (FNMC) PLAN REQUIRED FOR NUREG/CR-5798 PILOT PROGRAM TO ASSESS PROPOSED BA$1C LOW-ENRICHED URANIUM ENRICHMENT FACILITIES, QUALITY ASSURANCE REQUIREMENTS IN THE MEDICAL USE OF BYPRODUCT MATERIAL MOSKAL.T.E.

NUREG/CR 5670 MULTILOOP INTEGRAL SYSTEM TEST (MIST) MIST MEINKE,W.W.

F ACILITY FUNCTONAL SPECIFICATION.

NUREG-1301: OFFSITE DOSE CALCULATION MANUAL GUIDANCE:

STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR PRES.

MDTLEY,F.E.

SURIZED WATER REACTOR $.Genenc Letter 89-01, Supplement No, NUREG/CR 4063: AN INVESTIGATION OF CORE LlOUtD LEVEL DE.

1 PRESSION IN SMALL BREAK LOSS-OF COOLANT ACCIDENTS.

NUREG-1302, OFFSiTE DOSE CALCULATON MANUAL GUOANCE:

ST ANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR BOILING MUBAYl,V.

WATER REACTORS Genene Letter 89 31. Supplement No 1.

NUREG/CR 5771: PROBABILITY AND CONSEQUENCES OF MISLOAD-6 ING FUEL IN A PWH.

EERKLE,J.G.

NUREG/CR-5592: ANALYTICAL STUDIES OF TRANSVERSE STRAIN MURATA,K.K.

EFFECTS ON FRACTURE TOUGHNESS FOR CIRCUMFERENTIALLY NUREG/CR 5518. QUAllTY ASSURANCE PROCEDURES FOR THE ORIENTED CRACKS.

CONTAIN SEVERE REACTOR ACCIDENT COMPUTER CODE.

NUREG/CR-5715: REFERENCE MANUAL FOR THE CONTAIN 1.1 M ETLAY,D,S.

CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSIS.

NUREG/CR 5538 V01: INFLUENCE OF ORGANIZATIONAL FACTORS ON PERFORMANCE RELIABILITY.Ovennew And Detailed Methodo-MURFIN.G.W.

logical Development.

NUREG/CR 4551 /2 RIP 2.

EVALUATION OF SEVERE ACCIDENT RISKS: QUANTIFICATION OF MAJOR INPUT PARAMETERS. Experts' MEYER4F.

Deternunation Of Containment Loads And Molten Core Containment NUREG/CR 5682; SPECIFIC TOPICS IN SEVERE ACCIDENT MANAGE.

Interaction issues.

MENT.

MURPHY,A.J.

M E YE R.O.R.

NUREG-1407; PROCEDURAL AND SUBMITTAL GUtDANCE FOR INDI-NOREGICA-5543. A SYSTEMATIC PROCESS FOR DEVELOPING AND VtDUAL PLANT EXAMINATON OF EXTERNAL EVENTS OPEEE) FOR ASSESSING ACCIDENT MANAGEMENT PLANS.

SEVERE ACCIDENT VULNERABILITIES Final Repc t.

MILIAN,LW.

MURPHY,E.M.

NUREG/CR-3444 V08: THE IMPACT OF LWR 0ECONTAMINATONS NUREG/CR-5713; A REVIEW OF ENVIRONMENTAL CONDITONS AND ON SOllDIFICATON, WASTE DISPOSAL AND ASSOCIATED OCCU-PERFORMANCE OF THE COMMERCIAL LOW-LEVEL RADIOACTIVE PATIONAL EXPOSURE. Effects Of Composition On The WASTE DISPOSAL FACILTTY NEAR SHEFFIELD,lLLINOIS.

Stren0th,Swellng. And Water-immorsion Properties of Cement-Schdh fied lon Exchange Resin Wastes.

MURPHY,S.

NUREGICR-5758 V01: FITNESS FOR DUTY IN THE NUCLEAR POWER MILICl,T.

INDUSTRY. Annual Summary Of Program Performance Reports,CY NUREG/CR-5780.

SUMMARY

OF A WORKSHOP ON SEVERE ACCl-1990.

DENT MANAGEMENT FOR BWRS.

NUREG/CR-5784. FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR 5781:

SUMMARY

OF A WORKSHCP ON SEVERE ACCT.

INDUSTRY.A Review Of The First Year Of Program Performance And DENT MANAGEMENT FOR PWAS.

An Update Of The Techrucal Issues.

MILSTEAD W.

MUSICKI,Z.

NUPCG-0003 S01 12: A PRIORITIZATION OF GENERIC SAFETY NUREG/CR-5528. ANALYSIS OF RISK REDUCTION MEASURES AP-ISSUES PLIED TO SHARED ESSENTIAL SERVICE WATER SYSTE'1S AT NUREG 0933 St2 A PRtORIT12ATON OF GENERIC SAFETY ISSUES.

MULTI-UNIT SITES.

NUREG-0933 S13 A PRIORITIZATION OF GENERIC SAFETY ISSUES.

NUREG/CR-5682; HYDROGEN EOMBUSTION. CONTROL,AND VALUE-IMPACT ANALYSIS FOR PWR DRY CONTAINMENTS.

NUREG/CR 4674 V13: PRECURSORS TO POTENTIAL SEVERE CORE N AIR.P.K.

DAMAGE ACCIDENTS 1990 A STATUS REPORT. Main Report And Ap-NUREG/CR-5440; CRITICAL ASSESSMENT OF SEtSMIO AND GEOME.

pendix A CHANICS LITERATURE RELATED TO A HIGH-LEVEL NUCLEAR NUREG/CR-4674 V14 PRECURSORS TO POTENTIAL SEVERE CORE WASTE UNDERGROUND REPOSITORY..

DAMAGE ACCIDENTS:1990 A STATU3 REPORT.Appe%es B And NUREG/CR-5639: UNCERTAINTY EVALUATON METHODS FOR C.

WASTE PACKAGE PERFORMANCE ASSESSMENT.

MG'FITT.N.E.

NAKAMURA,T.

NUREG/CR 4427; AUXILIARY FEEDWATER SYSTEM RISK BASED IN-NUREG/CR 5481; DATA

SUMMARY

REPORT FOR FISSION PRODUCT SPECTION GUIDE FOR THE BYRON AND BRAOWOOD NUCLEAR RELEASE TEST VI-4.

POWER PLANTS.

NUREG/CR-5763-AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-NANSTAD.R.K.

SPECTION GUIDE FOR THE CALLAWAY NUCLEAR POWER PLANT, NUREG/CR-5696: IRRADIATION EFFECTS ON CHARPY IMPACT AND NUREG/CR4764. AUXILIARY FEEDWATER SYSTEM RISK BASED IN.

TENSILE PROPERTIES OF LOW UPDER-SHELF WELDS,HSSI SPECTON GUIDE FOR THE GINNA NUCLEAR POWER PLANT.

SERIES 2 AND 3.

MOLINA.T.

NELSON,E.E.

NUREG/CP 0115: PROCEEDINGS OF THE CSNI WORKSHOP ON PSA NUREG/CR-5729: MULTIVARIABLE MODELING OF PRESSURE APPLIUATIONS AND LIMITATIONS.

VESSEL AND PIPING J-R DATA.

l

62 Personal Author index NELSON.k.

NUREG/CR4755 VOI: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-5798 PtLOT PROGRAM TO ASSESS PRCPOSED B ASIC INDUSTRY. Annual Summary Of Program Performance Reports,0Y OUAUTY ASSURANCE REQUIREMENTS IN THE MEDICAL USE OF 1990.

BYPRODUCT MATERIAL NUHEG/CR 5764, FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY.A Revew Of The First Year Of Program Performance And NEOGY,P.

An Voriate Of The Technecat issues.

NUREGiCR-5707. APPUCATION OF CONTAINMENT AND RELIASE MANAGEMENT TO A PWR ICE-CONDENSER PLANT-ORNSTEIN.H.L NUREG 1275 V06: OPERATING EXPERIENCE FEEDBACK REPORT.

NU E'G CR 5167: COST / BENEFIT ANALYSIS FOR GENERIC ISSUE tor 23' REACTOR COOLANT PUMP SEAL. F ALLURE.

OSBORNE,M.F.

NJ EG'/CR 3916 PRESSURi2ED U ' t EJECTION INTO W ATER RE S TS NU

/CA 5778. EXPERIMENTS TO INVESTIGATE THE EFFECT OF E ASE T T FLIGHT PATH ON DIRECT CONTAINMENT HEATING (DCH) IN 1HE SUR1SEY TEST FACIUTY.The Umited Flight Path (LFP) Tests OWCZARSKLP.C.

NUREG/CH4658 FPFD 2: A CODE FOR FOLLOWING AIRBORNE FIS-NIELSON.H.L NUREG/CR-4670; RADIONUCUDE DISTRIBUTIONS AND MiGRATCN NU E / 576 SPA 90 E OR LCU FISSON MECHANISMS AT SHALLOW LAND BURIAL SITES Final Report Of PRODUCT CAPTURE IN SUPPRESSION POOLS PNL Research investigations On The Distnbuton, Mupation. And Con-tainment Of Radionuchdea At Mawy Flats, Kentucky-PADOVAN,LM.

NUREG-1022 RO1 DR FC: EVENT REPORTING SYSTEMS to CFR NIMNUAL,$.

NUREG/CR 5662. HYDROGEN COMBUSTION.CONTROLAND VALUE-50 72 AND 50 73 Clantication Of NRC Systems And Guidehnes for IMPACT ANALYSIS FOR PWR DRV CONTAINMENTS Reporting Draft Report For Comment.

NORDEN.K.

PAFFORD,0.J.

NUREG/CH-2907 V09-RADIOAC1tvE MATERIALS RELEASED FROM NUREG/CR 5529: AN' ASSESSMENT OF DWR MARK 111 CONTAh NUCLEAR POWER PLANTS Annual Report 1988.

MENT CHALLENGES FAILURE MODES, AND POTENTIAL iMPRO, MENTS IN PERFORMANCE.

NOWLEN,$.P.

g NUREG/CR.5548: AN INVESTIGATION OF THE EFFECTS OF THEH.

P AGE,J.D.

MAL AGING ON THE FIRE DAMAGEADILITY OF ELECTRIC CABLFS.

NUREG-1374; 1ECHNICAL FINDINGS RELATED TO GENERIC ISSUE NUREG/CR-5619 THE IMPACT OF THERMAL AGING ON THE FLAM-7RAn Evaluaten Of PWR Reactor Vessel Thermal Stress Dunng Natu-MABlVTY OF ELECTRIC CABLES.

rai Convection Cooldowet O' BRIE N.J.M.

PANCIER A V.W.

NUREG/CR-5538 V01. !N4UENCE OF ORGANIZATIONAL F ACTORS NUREG/CR 5682: SPECIFIC TOPICS IN SEVERE ACCIDENT MANAGE-ON PERFORMANCE REUAB:UTY Overvtew And Detailed Methodo WNT.

logical Developrnera PARKt K.

O'DONNELLE.

NURtG/CR-5282; ESTIMATION OF CONTAINMENT PRESSURE LOAD-NUREG/CR4918 V05. CONTROL OF WATER INFILTRATION INTO LNG DUE TO DIRECT CONTAINMENT HEATING FOR THE ZION NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On Fisid Ex-Pl. ANT.

penrwnts At A Hurmd Region Site.Bertsvale Maryland PARK,H.

ODLAND.D.J.

NUREG/CR-5780-

SUMMARY

OF A WORKS. SOP ON SEVERE ACCl-NUREG/CR 5665_ A SYSTEMATIC APPROACH TO REPETITIVE FAIL-DENT MANAGEMENT FOR BWRS.

URES-NUMEG/CR-5781:

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SUMMARY

OF A WORKSHOP ON SEVERE ACCI-

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DENT MANAGEMENT FOR PWRS.

NUREG/CR4667 Vt1: ENVIRONMENT #LLY ASSISTED CRACKING IN OLAGUE,N.E.

LIGHT W ATER REACTOHS Semiannual Report,Apnt-September 1990.

NUREG/CR-5435. CONCEPTUAU2ATON OF A HYPOTHETICAL HtGH-pang,y,3, LEVEL NUCLEAR WASTE REPOSITORY. SITE IN UNSATURATED, FRACTURED TUFF.

. NUREG/CR-5585: THE HIGH LEVEL VIBRATION TEST PROGRAM.F nat.

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USED FOR PERFORM ANCE ASSESSMENT OF HIGH-LEVEL NUCLE -

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O*.IVE.K.L NUR 350 3N EAR REGULATORY COMMISSION INFORMA-N REG Cd5571: THE RESPONSE OF BWR MARK lli CONTAIN-MENTS TO SHORT TERM STATION BLACKOUT SEVERE ACCIDENT OLIVER,M.S. '

SEQUENCES

- NUREG/CR-3916: PRESSURIZED MELT EJECTION INTO WATER poots.

PAULD.D.

NUREG!CR-5128: EVALUATION AND REFINEMENT OF LEAK-RATE OLSEN,P.C.

ESTIMATION MODELS.

NUREG 1400 DRFT FC: AIR SAMPUNG IN THE WORKPLACE. Draft Report For Corr ment.

P AY NE.A.C.

NUREG/CR 4551 V2 RIP 2; EVALUATON OF SEVERE ACCIDENT OLSON.J.

AtSKS-OUANTIFICATION OF MAJOR INPUT PARAMETERS Experts' NUREG/CR4911; INCENTIVE REGULATION OF NUCLEAR POWER Determination Of Contamment Loads And Motten Core Contamment PLANTS BY STATE HEGULATORS intoraction tssues

Personal Author index 63 NUREGtCR 5331: MELCOR ANALYSES FOR ACCIDENT PROGRES-RATNAM,U.

SiON ISSUES NUREGICR4423 THE PROBABILITY OF LINER FAILURE IN A MARK 1 CONTAINMENT.

NURFG/CR-4219 V07 N1. HE AVY-SECTON STEEL TECHNOLOGY RE1LK.O.

PROGRAM Semeannual Progress Recort for October 1989 March NUREG/CR 5345: PSSION PRODUCT RELEASE AND FUEL DEHAV-1990.

IOR OF IRRADIATED LIGHT WATER REACTOR FUEL UNDER UUREG/CR 4219 V07 N2 HEAVY SECTION STEEL TECHNOLOGY PROGRAM Semsannsel Progress Report For Apnl. September 1990 SEVERE ACCIDENT CONDITIONS The ACAR ST.1 E apenment.

REILLY,D PESHELJ1439 STAFF TECHNICAL POSITION ON REGULATORY CON-NUREG NUREG/CR-5550- PASSIVE NONDESTRUCTIVE ASSAY OF NUCLEAR SIDERATONS IN THE DESIGN AND CMSTRUCTION OF THE Ex-

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REITER,L PETERSON,H,T, NUREG-1407: PROCEDURAL AND SUBMITTAL GUIDANCE FOR INDI-NUREG-1446: STANDARDS FOR PROTECTION AGAINST RADIATION -

VIOUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) FOR 10 CFR PART 20. A Compansor' Of The Ersting And Revised Rulos.

SEVERE ACCIDENT VULNERABILITIES Ford Report

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PEYTON.L RICKARD,W.H.

d NUREG-1441: LESSONS LEARNED f ROM THE POST 4MERGENCY NUREG/CR-4670: RADIONUCLCE DISTRIBUTONS AND MIGRATION T

T ABLETOP EXERCISE IN BATON ROUGE. LOUISIANA.ON AUGUST MECHANISMS AT SHALLOW LAND BURIAL SITESFinal Report Of 28 AND SEPTEMBER 18,1990 PNL Research investigations On The Distnbution, Migration, And Con-tainment Of Radionuciates At Maxey Flats, Kentucky, PHAM M.

NUREGICA 5520. PROCEDURES GutDE FOR EXTRACTING AND RIOKY,R.W.

LOADING PROBADIUSTIC RISK ASSESSMENT DATA INTO MAR-D NUREGiCR 4918 V05 CONTROL OF WATER INFILTRATON INTO USING IRRAS 2.5-NEAR SURFACE LLW DISPOSA1 UNITS Progress Report On Field En.

PHILLIPS,LB.

NUREG/CR-5695 A PHOCESS FOR RISK FOCUSED MAINTENANCE, RIGGS,R.

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STUhTU NOSCAL.

NUREG/CR-4551 V2R t P2: EVALUATON OF SEVERE ACCIDENT NU E i 5B FF A NT A

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PNL Research Investigat'ons On The Distnbution, Migration. And Con-NUREG 0933 S01 12 A PRIORITIZATION OF GENERO SAFETY tainment Of P.adionuciados At Maxey Flats. Kentucky ISSUES NUREG/CR-5343: RADIONUCLIDE CHARACTERl2ATION OF REAC-NUREG-0933 S12: A PRIORITI2ATION OF GENERIC SAFETY ISSUES TOR DECOMMISSIONING WASTE AND SPENT FUEL ASSEMBLY NUREG 0933 S13: A PR ORITl2ATON OF GENERIC SAFETY ISSUES.

HARDWARE Progress Report, POMMERSHEIM.J.

RODRIOUELJ.R.

NUREG/CR-4269 MODELS OF TRANSPORT PROC ISSES IN Cl I-CRETE.

NUREG/CR 5722 INTERIOR INTRUSON DETECTION SYSTEMS.

PRICE L ROLFE,S.T.

NUNEG/CR-3%4 V02. TECHNIQUES FOR DETERMINING PROBABIL.

ITIES OF EVENTS AND PROCESSES AFFECTING THE PERI:ORM, ANCE OF GEOLOGIC REPOSITORIES Suggested Approaches ROOD,H.

PUGH.R.

NUREG 0675 S34 SAFETY EVALUATION n ? ORT RELATED TO THE NUREG/CR 5761: AUXILIARY FEEDWATER SYSTEM RISK-BASED IN, OPERATION OF DIA8LO CANYON NUCLEAR POWER PLANT,UMITS SPECTION GUIDF FOR THE SALEM NUCLEAR POWER PLANT.

1 AND 2. Docket Nos 50-275 And 50-323(Pacific Gas And Electnc NUREG/CR 5764. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN.

Company)

SPECTION GUIDE FOR THE GINNA NUCLEAR POWER PLANT.

ROSINSKl,S.T.

RADOATZ,C.T.

NUREG/CR.5748. RADIATION EMBRITTLEMENT OF THE NEUTRON NUREG-0713 VIO: OCCUPATIONAL RADIATION EXPOSURE AT COM-SHIELD TANK FROM THE SHIPPINGPORT REACTOR.

IVERCIAL NUCLEAR POWER REACTORS AND OTHER

{

FACILITIES.1988 Twenty Frst Annual Report ROy Nu G CR-3918: PRESSURIZED MFAT EJECTION INTO WATER RAMSDELL,J.V.

POOLS.

NUREG/CR-5656: EXTRAN: A COMPUTER CODE FOR ESTIMATING CONCENTRATIONS OF TOXIC SUBSTANCES AT CONTROL ROOM ROSS.T.M.

AIR INTAKES NUREG 1232 V03 S02: SAFETY EVALUATION REPORT ON TENNES.

NUREG/CR-5658. FPFP 2: A CODE FOR FOLLOWING AIRBORNE FIS.

SEE VALLEY AUTHORITY. BROWNS FERRY NUCLEAR PERFORM-

. SiON PRODUCTS IN GENERIC NUCLEAR PLANT FLOW PATHS, ANCE PLAN Browns Feny Unit 2 Restart RAN C.

RUFF,L NUREG/CR-5686: EFFECTIVENESS OF FRACTURE SEALING WITH NUREG/CR 3145 V09-GEOPHYSICAL INVESTIGATONS OF THE BENTONITE GROUTING WESTERN OHIO-INDIANA REGION Annual Report. October 1989 +

RASMUSSEN.T.C.

NUREG/CR-558 t: UNSATURATED FLOW AND TRANSPORT RUSH,0.C.

THROUGH FRACTURED ROCK RELATED TO HOH-LE%.TL WASTE NUREG/CR-5670: MULTILCOP INTEGRAL SYSTEM TEST (MIS 9 MIST RE POSITORT

~inal Report Pnase ill FACILITY FUNCTIONAL SPECIFICATION

64 Personal Author Index RUSSELL,K.D.

SE HQ ALB.R.

NUREGICA 5300 V01: INTEGRATED RELIABillTY AND RISK ANAlv-NUREG/CR-5609 DRF FC. AN INTEGRATED STRUCTURE AND SCAL.

SIS SYSTEM ORRAS) VER$ ION 2 5 Reference Manual INU METHODOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE RUSSE LL,N. A.

NUREG/CR $518 OUALITY ASSURANCE PROCEDURES FOR THE SE HME L,G.A, CONT AIN SEVERE "IE ACTOR ACCIDENT COMPUTER CODE-NUREG/CR 4757 LINE-LOSS DETERMINATION FOR AIR SAMPLER NVREG/CR-6715-REFERENCE MANUAL FOR THE CONTAIN 11 SYSTEMS CODE FOR CONTAINMENT SEVERE ACCIDENT ANALYSsS.

RUTHER,W.E.

SEITZ.R.R.

NUREG/CR.4667 V09 ENVIRONMENTALLY AS$1STED CRACKING IN NUREGICR-5614 PERFORMANCE OF INTACT AND PARTIALLY DE.

LIGHT 1A ATER REACTDRS Semiannual Renort.ApntSeptember 1989 GRADED CONCRETE BARRIERS IN LIMITING FLUID FLOW I

NUREG/CR4667 Vto. ENVIRONMENT ALLY ASSISTED CRAChtNG IN LIGHT W ATER REACTORS. Semannual Report. October 1989 March SETH.S.S.

1990.

NUREG/CR 5382. SCREENING OF GENLAIC SAFETY ISSUES FOR LI-NUREG/CR4667 V11: ENV'".ONMENTALLY ASSISTED CRAL,.c4G IN CENSE RENEWAL CONSIDERATIONS LIGHT WATER REACTORS Semannual Report April September 1990.

NUREG/CR 4667 VIP: ENVIRONMEr4 TALLY ASSISTED CRACKING IN SHA,WJ LIGHT WATER REACTORS. Semannual Report,0ctober 1990 March NUREG/CR 5456.

• 1ALYSIS OF MOW STRATIFICATION IN THE 1991.

SURGE LINE OF THE COMANCHE PEAK REACTOR.

SAMANTA,P.K.

SHACK,W.J.

NUREG/CR 5612: DEGRADATION MODELING 'WITH APPLICATION TO NUREGICR.4667 V10 ENVIRONMENTALLY ASPSTED CRACKING IN AGING AND MANTENANCE EFFECTIVENESS EVALUATIONS LIGHT WATER REACTORS. Semiannual Report, October 1989 - March NUREG/CR 5641; STUDY OF OPERATIONAL RISK UASED CONFIGO.

1990, RATION CONTROL-NUREG/CR-4667 V11; ENVIRONMENTALLY ASSISTED CRACKING IN SANE CKI,J.E.

LIGHT WATER REACTORS. Semannual Report.Apnt-September 1990.

NUREG/CR4667 v12: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4667 V11: ENVIRONMENTALLY ASSISTED CR ACKING IN LIGHT WATER REACTORS. Semannual Report October 1990 - March LIGHT WATER REACTORS Semannual Report.Apni-September 1990.

gggt NUREGICR 4667 V12. ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-5748-RADtATION EMBRITTLEMENT OF THE NEUTRON LIGHT W A1ER REACTORS. Semannual Report,0ctober 1990 March SHIELD TANN FROM THE SHIPPINGPORT REACTOR.

1991, SASSER LB.

SHAFFER.C.J.

NUREG/CR-5669: EVALUATION OF EXPOSURE LIMITS TO TOxlO NUREG/CR-5331: MELCOR ANALYSES FOR ACCIDENT PROGRES-GASES FOR NUCLEAR REACTOR CONTROL ROOM O')ERATORS SiON ISSUES SATHER,A, SHARPE,C.J.

NUREG/CR-4744 V04 N2 LONG-TERM EM9AITTLEMENT OF CAST NUREG/CR-5683. LASORATORY TESTING OF CEMENT GROUTING DUPLEX StelNLESS STEELS IN LWR EYSTEMS Semiannual OF FRACTUPM IN WELDED TUFF, Report, April-September 1989 SH AUK AT,S.K.

SATTISON.M.B.

NUREG-1401 DRFT FC. REGULATORY ANALYSIS FOR GENERIC NUREG/CA-5300 V01: INTEGRATED RELIABILITY AND RISK ANALY.

ISSUE 23. ArACTOR COOLANT PUMP SEAL FAILURE. Draft Report SIS SYSTEM (IRRAS) VERSION 2 5.Referance Manual.

For Comment SCHROEDE R,J. A.

SHEN,Y.H.

NUREG/CR-5529 AN ASSESSMENT OF BWR MARK lit CONTAIN-NUREG CR-5456: ANALYSIS OF FLOW STRATIFICATION IN THE MENT CHALLENGES, FAILURE MODES. AND POTENTIAL IMPROVE-SURGE LINE OF THE COMANCHE PE AK REACTOR MENTS IN PERFORMANCE.

SitTEYNGART S.

SCHULTZ,R.R.

NUREG/CR-4059 V04, SEISMIC FRAGIUTY OF NUCLEAR POWER NUREG/CR-4063. A

.ESTIGATION OF CORE LIQUID LEVEL DE*

PLANT COMPONENTS (PHASE II) A Fragility Handbooli On Eighteen PRESSION IN SMALL BREAK LOSS OF COOLANT ACCIDENTS Components SCHULZ,R.K.

NUREG/CR4918 V05: CONTROL OF WATER INFILTRATION INTO SHUM.D,K.M.

NEAR SURF ACE LLW DISPOSAL UNITS Progress Report On Field En-NUREG/C45592. ANALYTICAL STUDIES OF TRANSVERCE STRAIN penments At A Humd Region S4 tie BeItsville. Maryland.

EFFECTS ON FRACTURE TOUGHNESS FOR CIRCUMFERENTIALLY NUREG/CR$464 ANION RETENTION IN SOll: POSSIBLE APPLICA-TION TO REDUCE MITGRATION OF BURIED TECHNETIUM AND ORIENTED CRACKS ~

IODINE A Revow gqygogg,a w, SCIACCA,F W NUREG/GR-0003: EFFECT OF PRIOR DEFORMATION ON SENSITIZA-NUREG/CR 5595: FORECAST: REGULATORY EFFECTS COST ANALY.

TION DEVELOPMENT IN STAINLESS STEEL DURING CONTINUOUS SIS SOFTWARE MANUAL Version 3.0.

SCOTT.B.R.

SIMONEN,F.A.

NUREGIC442$4 R1P2A1: HEALTH EFFECTS MODELD FOR NUCLE, NUREG/C44489 Vtt: NONDESTRUCTIVE EXAMINATION (NDE) REll-AR POWER PLANT ACCIDENT CONSEQUENCE ABillTY FOR INSERVICE INSPECTION OF UGHT WATER ANALYSIS Modifications Of Models Resulting From Recent Reports On REACTORS Serne-Annual Report, Apnl September 1989.

lleaHh Effects Of lonmng Radiation. Low LET Radiation Part II: Soentit-ic Bases For Health, SIMPSON,0.

NUREG/Cf. e s V01: NEW YORK /NEW JERSEY REGIONAL SEISMIC SCOTT,P.M.

NETWOR, u nual Report For April 1989 March 1990.

NUREGiCR-4509 V01 N1: SHORT CRACKS IN PIPING AND PIPING '

WELDS Semannual Report, March-September 1990.

SKORPIK,J.R.

NUREG/CR 5128 EVALUATION AND REFLNEMENT OF LEAK. RATE NUREG/CR-564$' ACOUSTIC EMISSION / FLAW RELATIONSHIPS FOR ESilMATION MODELS.

INSERVICE MON!TORING OF LWRS.

SEEBER,L SMITH,B.W.

NUREG/CR 5778 V01: NEW YORK /NEW JERSEY REGIONAL SEISMIC NUREG/CR.5467: RISK BASED INSPECTION GUIDE FOR CRYbTAL NETWORK. Annual Heport For Apnl 1909. March 1990.

BlVER UNIT 3 NUCLEAR POWER PLANT,

l l

l-Personal Author index 65 SMITH.H.

NUNG-0837 V11 NO3 NRC TLD DIRECT RADIATON MONITORING NUREG/CR-5550 PASSIVE NONDESTRUCTIVE ASSAY OF NUCLE AR NETWORK Progress Report Juty.Septemt.nr,1991.

MA1ERIALS.

STUMPF.H.

SMOOT,J.L NUREGICR-4063 AN INVESTIGATION OF CORE LiOU!D LEVEL DE.

NUREG/CR-5737. HYDROGEOLOGIC PERFORMANCE ASSESSMENT PRESSION v4 SMALL BRE AK LOSSOF COOLANT ACCIDENTS.

ANALYSIS OF THE COMMERCIAL LOW. LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY NEAR WEST VALLEY,NEW YORK.

SUEN,C.J.

NUREG/CR S681: LOW-LEVEL WASTE SOURCE TERM MODEL DE-SOO.P-VELOPMENT AND TESilNG.

NUREG/CR-3444 V08. THE IMPACT OF LWR DECONTAMINAtlONS ON SOLIOiFIC/ % WASTE DISPOSAL AND ASSOCIATED OCCU-SULUVAN.K.

PATIONAL EXQSURE Effects Of Composition on The NUREG/CR-5555: AGING ASSESSMENT OF THE WESTINGHOUSE StrengthSwellm0, And Water immersion Proportes of Cement-Soi6 PWR CONTROL ROO DRIVE SYSTEM.

fed non-Exchange Resin Wastes.

SULUVAN.T.M.

SOPPET,W.K.

NUREG/CR-5681: LOW-LEVEL WASTE SOURCE TERM MODEL DE-NUREG/CR-417 V12: ENVIRONMENTALLY ASSISTED CRACKING IN VELOPMt!NT AND TESilNG.

LIGHT WATER REACTORS Sermannual Report. October 1990. March NUREG/CR-5773; EELECTION OF MODELS TO CALCUL ATE THE LLH 1991-SOURCE TERM.

SO2ER,A.

SUMMERS,R.M.

NUREG/CR-5623. BWR MARK li EX Vf SSEL CORIUM INTERACTION NUREG/CR4531: MELCOR 1.8 0- A COMPUTER CODE rOR NUCLEAP.

ANALYSES REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS-SPANNER,J C, NUREG/CR 4469 V11: NONDESTRUCTIVE EXAMINAllON (NDE) REll-SUN,J.G.

ABtLITY FOR INSERVICE IN9ECTON OF LIGHT WATER NUREG/CR-5456: ANALYSIS OF FLOW STRAtlFICATION IN THE REACTORS.Serm-Annual Report, Apnt-September 1989 SURGE LINE OF THE COMANCHE PEAK REACTOR.

D SPENCE,R.A.

SWIDER J.

NUREG-1022 R0t DR FC: EVENT REPORTING SYSTEMS 10 CFR NUREG/CR-5/B0:

SUMMARY

OF t. WORKSHOP ON SEVERE ACCH 50.72 AND 50.73 Clanhcabon Of NRC Systems And GLidehnes for DENT MANAGEMENT FOR BWRS.

Reporting Draft Report For Comment NUREG/C45781:

SUMMARY

OF A WORKSHOP ON SEVERE ACCl-DENT MANAGEMEN1 FOR PWRS.

NUREG/CR-5809 DRF FC: AN INTEGRATED STRUCTURE AND SCAL-SYPE.T.T.

ING METHOOOLOGY FOR SEVERE ACCIDENT TECHNICAL ISSUE NUREGICR-5606. A REVIEW OF THE SOUTH TEXAS PROJECT PROB-RESOLUTON Draft Feport For Comment.

ABILISTIC SAFETY ANALYSIS FOR ACCIDENT FREQUENCY ESTI-SRINIVASAN.M.G.

NUREG/CR-5757: VERiFICATON OF PIPING RESPONSE CALCULA-TALEYARKHAN,R.

TION OF SMACS CODE WITH DATA FROM SEISMIC TESTING OF NOREG/CR-5623 BWR MARK 11 EX VESSEL CORIUM INTERACllON AN IN-PLANT PIPING SYSTEM.

ANALYSES.

STAHLE D.

TAM P.S.

NUREG/CR$74t TECTONIC DEFORMATION REVEALED IN BALDCY-NUREG-0847 S06 SAFETY EVALUATION REPORT RELA 1ED TO THE PREF' TREEb AT REELFOOT LAKE. TENNESSEE.

OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND STALLM ANN.F W.

2. Docket Nos. 50 390 And 50 391.(Tennessee Valley Authonty)

NUREG/CR-4866 ROM PR-EDB. POWER REACTOR EMBRITTLEMENT NUREG 0847 S07: SAFETY EVALUATION REPORT HELA 1E11 TO THE DATA BASE. VERSION 1. Prograne Description.

OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 Docket Nos. 50-390 And 50-391 (Tennessee Valley Authonty)

STAMPS,D.W.

NUREG/CR 5525: HYDROGEN-Al4 DILUENT DETONATION STUDY FOR NUCLEAR REACTOR SAFETY ANALYSES.

NUREG R 3916: PHESSUR!2ED MELT EJECTION INTO WATER POOLS.

STEELE R NUREG/CR-5558. GENERIC ISSUE 87: FLEX 1BLE WEDGE GATE NUREd k5711: ASSESSMENT OF UNCERTAINTIES IN MEASURE-VALVE TEST PROGRAM, Phase il Results And Analysis' MENT OF PH IN HOGflLE ENV;AONMENTS CHARACTERISTIC OF STOCKMAN,H.W, NUCLEAR REPOSITORIES b

NUREG/CR-5345. FISSON PRODUCT RELEASE AND FUEL BEHAV.

IOR OF IRRADIATED LIGHT WATER REACTOR FUEL UNDER D

SEVERE ACCIDENT CONDITONS The ACRR ST.i Expenment.

NUREd CR-4816 Rol: PR-EDB: POWER REACTOR EMBRITTLEMENT DATA BASE. VERSION 1. Program Desenption.

STOETZEL,G.A.

NUREG 1 00 FT FC' AIR SAMPLING IN THE WORKPLACE. Draft TAY J'

N red /CR 5092: GENERIC RISK INSIGHTS FOR GENERAL ELLC-TRIC BOILING WATER REACTORS.

STRANGE,W.E.

NUREG/CR-5777: GLOBAL POSITIONING SYSTEM MEASUREMENTS TAROR,T.T.

OER A STRA'N MONinRING NETWORK IN THE EASTERN TWO.

NUREG/CR-4469 VII: NONDESTRUCTIVE EXAMINATION (NDr) RELL THIRDS OF Th6 t'YTC -TATES ABILITY FOR INSERVICE INSPECTON OF LIGHT WATER REACTORS. Semi-Annual Report, Apnt-September 1989.

STROMBERG,HA NUREG/CR-F1, m t.aC3 3 SUPPLIER INSPECTION GUIDE.

TERRILL4 NUREG/CR578t FITNESS FOR DUTY IN THE NUCLEAR POWER STRUCKMEYER,R.

INDUSTRY.A Review Of The Fast Year Of Prograin Performenct And NUREG-0837 V10 N04: NRC TLD DIRF.CT RADIATION MONITORING An Update Of The Technical issues.

NETWORK Progress Report. October December 1990 NUREG 0837 VII N01: NRC TLD DIRECT RADIATION MONITORING THATCHER D.F.

j NETWORK Progress Report January-March 1991.

NUREG-1401 DRFT FC: REGULATORY ANALYSIS FOR GENERIC NUREG-0837 VII NO2: NRC TLD OtRECT RADIATION MONITORING ISSUE 23: REACTOR COOLANT PUMP SEAL FAILURE. Draft Report NETWORK _ Progress Report Apni-June 1991.

For Comment o

66 Personal AuthDr index THEDF ANOUS T.G T VE T E N,U.

NUREG/L.R 5th M PROBABluTY OF LINER F AllUHE IN A MARbi NUREG/CR 5%4 RADONUCLIDE BEHAVOR IN THI' ENVIRONMENT.

CONT AINMENT.

NU3EG/CR4377. REvilW OF 1HE Ct:RONIC E KPOSURE PATHWAY NURE G/C64417, A UNWiED INTERPitET ATON OF ONEJirTH 10 MODELS IN MACCS AND SEVERAL OTHER WEtt KNOWN PRCR FULL SCALE THERMAL MixlNG EXPERIMENTS RELATED TO PRIS.

AbtuST'C RISK ASSESSMENT MODELS 995t/E D THi RMA NURE G/CR f,aN DR( SHOCK T SC AN INTEGRATED STRUCTURE AND SCAL.

UPDECR AF F.C.D.

194G HLTHODOLOUY FOR SEVERE ACCIDENT SCHNICAL ISSUE yyRgGfty.6536 DCMJD. A DUAL 40NilNUUM. THALE DIMENSION-RE SOL.UTION Dratt Report f or Comment AL GROUND WATER FLOW CODE LOR l'NSATURA1(D, FRAC.

T HOM A S.C.W.

TUREa POROUS MmA-NURLG/CR 4670 RADONUCLOE DISil4IBUTIONS AND MiGRATON MLCHANISMS AT SHALLOW LAFO BURIAL SITES Fnal Report Of VALDESJlCR.3964 V021ECHNOUES FOR DETE RMININ3 P PNL Retowch Inn 4tigations On The Dettntotet Mgraton. And Con-gggg g IllES OF EVEN18 AND PRECELSE $ AFF ECTING THE PtRFORM.

IAbd bC ACYEYi ATION OF he.AC.

ANCE OF GEOLOGIC REPOSITORIES Sure61*d AP4woeches N L

$3 TOR DROMMISSONit.G WASTE AND $ PENT FUEL ASSEVOLY HARDWARE Prog ess deport UR G CR $409 DRF IC. AN IN1EGRATED STRUCTURF *- L SCAL.

THOME.D K.

ING METHODOLOGY FOR SEVI RE ACCIDEW TE.CH' s ' ISSUE i

NUREG/GR 6661 YWO NEW NDT TECHNOUES *OR #NSPf CTON OF RESOLUTION Dratt Report For Camnent CONT AINMENT WELDS DENE ATH COATINGS Final ReportOctober

$089 March 1DN.

YANARbOALL,R.

NUREG/GR 5749 TECTONIC DEFORMA1CN REVEALED IN BALDCY.

THOMSSON.8 M PRFSS TREES AT RittFOOT LAKE,1f NNESSEE.

NUREG/C P4539 A SELF. TEACHING CRRICULUM FOR THE NRC/

SNL LOWlEVEL WASTE PERFORMANCE ASSESSMENT MLTHOD.

VANHORN,Ill.L.

OLOGY.-

NUREGiCR %20 Pf40CE DURES GUIDE FOR ENTRACTING AND LOADING PROFIABILISTIC fUSK ASSESSMLNT DATA INTO MAR D NU E 3rW PRE APPLICATION SAFETY EVALUA..JN REFORT FOP THE fiODIUM ADVANC D FAST RE AC10R (SAFR) 11Q00 METAL V ANZ ANT,b.W.

REACTOR NUREG/CR 6440 CRillCAL ASSESSMENT OF SEISMIC AND GEOME-3 TICHLER.J CHANICS LITERATURE ALLATED TO A HIOW.EVEL NUCLEAR NUREG/CR 7907 PD9 rad) ACTIVE MATCRIALS RELEASED FROM WASTE UNDERGROtlND REPOS110RY.

NUCLE AR PO%R Pl.ANib *nnual Report 1988 ygg gy,y,g TIES 1L4.8 R.

NUREG/CR-6612. DEGRADATON MODELING WITH APPUCATON TO NUR % A$W5 HYDROGEN-AIR DILUENT DETONATINI ST(Oy AGING AND MAINTENANCE EFFECTIVEtJESS EVAlUAflONS.

FOR NUrtEAR REACTOR SAFETY ANALYSEg NUREG/CR 5641: STUDY OF OPERATIONAL RISK-BASED CONFIGU-RATION CONTROL NUR(G/CR $$(i6. THE RESPONSE OF BWR MARK li CONTAINMENTS VIETH.P.

TO ST ATON BLACAOU1 $(VERE ACCOENT SEQUENCES NUREG/CR e599 V01 N1: MORT CRACKS IN PtPING AND PO40 NUREG/CR M71. THE RESPONSE OF BWR MMIK lli CONTAIN-WE L DS Serruannual Report, MarctvSeptamtier 1990 MENTS TO SHORT TERM STATION BLACKOUT SEVEHE ACCtCiNT SLOVENCES VD,T.V.

d TOQUAW NUREG/CR.4427: AUXILIARY FEEDW ATER SYSTEM RISK-BASED IN.

NURL bR 6764 FITNESS FOR DUTY IN THE NUCLEAR POWER SP WO H

A BRA WOOD NMR INDUSTRY A Revew Of The Firtt Yeat Of Program Performance And An Update Of The Technmal tanuwe' NU

/CR NONDESTRUCTIVE EMNATON WN REU.

ABill1Y FOR INSEFIVICE INSPECTON

")F LIGHT WATER T OSTE.A.P.

REACTORS Senu Annual Report Atml September 1989 NUREG/CR.4670- RADONUCLOE DISTRIBUTIONS AND MIGRATION NUREG/CR4467: RISK BASED INSPECTION GUIDE FOR CRYSi AL MECHANISMS AT SHALLOW LAND BURIAL Sills Final Report Ot RIVE R UNIT 3 NUCL E AR POWER PLANT.

PNL ResearA hvt it>9elions On The Distnl>utinn, Migration, And Con, t4UREG/C $761: AUxlLIARY FEEDWATER Si& TEM RISK BASED IN.

tainme *. Of 4.adtveuctu1es At Masey Flats' kentucliy' SPECTION GUIDE FOR THE SALEM NUCLE AR POWER PLANT, NUREG/CR 6763 AUXILIARY FEEDWATEM SYSTEM FilSK BASED IN-TDWLE.H.

SPECTON GUIDE FOR THE r.ALL AWAY NUCLE AR POWER PLANT, NUREG/CR 4600 V01 R1; GENERIC COMMUNIC A %NS NUREG/CR4764 AUxiLtARY FEEDWATER SYSTEM RISK. BASED IN-INDEA Latings Of Commutucations. 1971 1989.

SPECTON GUIDE FOR THE GINNA NUCLE AR POWER PLANT.

TRAVE R.LE.

VULIN.D.S.

NUREG/CR 5682. SPECIFIC TOPtCS IN SEVERE ACCIDENT MANAGE.

NUREG/CR-3469 V06 OCCUPATIONAL DOSE REDUCTON AT NU-MENT.

CLEAR POWER PLANTS ANNOT ATED BIBLIOGRAPHY OF SELECi+

T>tAVIS).R.

NUREGICR f/81: EMTA

SUMMARY

REPORT FOR FlSSION PRODUCT WAHl,K, RELE ASE TEST VI4 NUREG/CR4668. DATA

SUMMARY

REPORT FOR FISSON PRODUCT NUREG/CR 3964 V02: TECHNIOUES FOR DETERMINING PROBADil.

RELE ASE TEST VI $

lilES OF EVENTS AND PROCESSES AFf ECTING THE PERFORW A.NCE OF GEOLOGIC REPOSITORIES Suggested Approaches T R AVi$,R.

C DO L GW E REA O NUR G/CR 5606. A REVIfW OF THE SOUTH TEKAS PROJECT PROB.

1 ABILISitC SAFETY ANALYSIS FOR ACCIDENT FREQUEHCY ESTl-(RUBEY,DK.

MATES AND CONTAINMENT BINN:NG..

NUREGICR 5740 NEW GAMMA-RAY BUILDUP FACTOR DATA FOR POINT KERNEL CALCOLANNS ANS-6 4 3 AT ANDARD REFER-W ALTON.J C-ENCE D A14.

NUREGICR 5614 PERFORMANCE OF INTACT AND PARTIALLY DE.

TUTU,N K.

GRADED CONGRETE BARRIERS IN LIMITING FLUO FLOW.

NUMEGICR M82 ESTIMmlON OF CONTAINMENT PRESSURE LOAD.

WARD.LW.

ING OY TO DIRECT CONT AINMENT HEATING FOR THE ZION NUREG/CR.5543 A SYSTEMATIC PROCESS FOR DEVELOPING AND PLANT ASSESSING ACCOENT MANAGEMEN1 PLANS

.- {

l PerSonsi Author index 67 W ASHINQTON A E.

NURFW512ft E oLUATON AND REllNf MENT OF LE AK-MA1E NURE G rCR45 t B OUALITY ASSURANCE PROC 4 DURE S 8 0A,HL EST MATON MODEL5 CONT AIN SEVE RF RF ACTO' ACCIDE NT COMPUTER CODE NURIG'CR 6715 REFEREtt P MANUAL l'OR THE CONT AIN 1.1 WILLIAMS.D C.

CODE FOR CONT AINMES : ' EVERE ACUOENT ANALYSIS.

NUREG/CR4630, MA DAY CONT AINMENT PARAMETRIC STUDIE3 WAID'E tt'IEtt AM S,ML NURf G/CR fi!41 ANAI,YSIS OF BELLOWS EEPAMON JOINTS IN NURIJ/CR f448 TRANSPOR1 CALCULATION $ OF NEUTRON THE SLOVOY AH EONT AINMENT-TRANSMISSON THROUGH STEEL USING ENDF/RV.REVISf D W AT KINS,J C, ENDFiB V AND ENDF/B VIIRON EVALUATONS NURE G/CR 40ta AN INVEstlGATION OF CORE LOUlO LEVEL DE.

tNB hN f IC I E f LE LL E GAlg iLRE C %09 DAF FC AN INTEGRATED STRUCTURE AND BCAL.

N I /

VALVE TEST PROGRAM Phase ll Naues And Analyps ING METHODOLOGY 704 SEVERE ACCIDENT TECH 44AL ISSUE RE SOLUT ON Draft Report Ior Comment Q ATKINS.R A.

NURE G 1415 V04 401 OFFICE OF THE IN3PECTOR WILSONJN.

GE NERALSewannur.! ReportApril Sittember 1991.

fMREG 1314 PRE APPLICATON $AFETY EVALUATON REPORT FOR THE SODIUM ADVANCED FAST REACTOR (SAFR) LIQUID MET AL WI DB.E.

REACTOR HUREG/CR 34M V02. TE 34NOUES FOR DETtRMIN,NG PROBABtL.

ITIES OF EVENib AND PROCE SSES AFFECTING THE PERFOnM-WILSON.R.

ANCE OF GEOLOGIC REPOStTOR!E S Suggested Approaches NUREG/CR 5764 FITNESS FOR DUTY IN TPE NUCLEAR POWER WE DE R.CJ.

(WUSTRY.A Am* Of the M nar d Warn Pennce And t4UREG/CR W2 DAF FC-ODINE CHEMICAL FORMS IN LWH

^" VPd** U N 1 $E$ doses TO WA1ER WINEGARONER.W.

N E Rt a CALC L T F

POOLS IN SEVERE ACCOENT SEQUENCES NUREG/CR4760 ICF CONDENSLR AEROSOL TESTS WE DST E R,C.S.

wolfram.LM.

NURlG'GR 4481: DATA

SUMMARY

REPORT FOR FIS' ON PRODUCT NUREG/CR f420. PROCEDURES GUIDE FOR EXTRACTPNG AND ArLE At;F TEST VL4 LOADING PROOABtuSTIC RISK ASSESSMENT DATA INTO MAR-D NUREG/CR,fM4 DATA

SUMMARY

REPORT f OR FISSON PRODUCT U$ LNG 1HRAS 2 6.

RELEASE TE ST Vi b=

WOOD.R.S.

WEINST E IN,E.

NUREQ.0327 R05 CWNERS OF NUCLEAR POWER PLANTS NUREG 1441 LESSONS LEARNED FROM THE POST.l MERCENCY TADLETOP EXIRCISE IN BATON ROUGE. Lout $iANA,0N AUGUST WRIGHT.J.E.

PR AND SEPTE MMR 18.19M NUREG/CR 6729 MULTIVARIABLE MODEUNG OF PRESSURE NURE G-1442 POST.! MC RG.L NCY

RESPONSE

f1EbOURCES VESSEL AND PIPING J A DATA GUOE Based On the Post-I.mergency T A81LETOP Esercse en Bator*

Rouge,t.oumana On August 26 And Septamt,er 10.1930.

WRIGHT.R Q NUREG/CR b648 TRANSPORT CALCut ATIONS OF NEUTRON red /CP 0114 V01: PROCEEDINGS OF THE ECHTEENTH WATER fD f F R

E UT $

RF ACTOR SAF ETY lNFORM AT'ON MEETING NUREG/GP 0114 V02 PROCEEDINGS OF THE EIGHTEENTH WATER WU Y,.T N E P

V3 A i GS OF TH ElGHTEENTH WATER

/CR ba39. UNCERTAINTY EVALUATOf1 METHODS FOR 84 ACTOR SAFELY INFORVaTION MEETING WASTE PACKAGE PERFORMANCE ASSESSMENT.

NUREG/CP-011e TRAt SACTIONS OF THE NINETEENTH WATER RE.

ACTOR SAFETY INFORMATION MEETING.

W U E G/CR4352 R01: VAV2D VARIABLY SA1 UATED ANALYSIS WE ST R A.C.

MODEL IN TWO DIMENSIONS Verseon 6 2 With Hysteretts And Chain NUREG/CR 67f4 V01 FITNESS FOR DUTY IN THE f4UCLEAR POWER Decay Transport Documentateon And User's Gude lNDUSTRY Annual Summary Of Program Portormance fieportACY NUREGICR 594. GROUND WATER FLOW AND TRANSPORT MODE L.

1990.

ING OF THE NRC.LtCENSED WASTE DISPOSAL F ACILITY, WEST VALLEY NrW YORK WHE E LE R,T.A-NUREG/CR 5795 VAUDATON AND TESTING OF THE VAM20 COM.

NUREG/CR4000 A REVIEW OF THE SOUTH TEKAS PROJECT PROB-PUTER CODC.

ABluSTIC SAFETY ANALYSIS FOR ACCOENT F REQUENCY ESTl-MATES AND CONTAINMENT DINNING WOLFF,W.

NUREG/CRf.809 DRF FC.- AN INTEGRATED STRUCTURE AND SCAL-U G A 5648-TRANSPORT CALCULATIONS OF NEUTRON R SO TO aR For TRANSMISSION THROUGH STEEL USING ENOF/8 V. REVISED E NDF/B V.AND ENDF/B Yl lROtd EV ALUATONS WYNHOFF.N C.

WICHNER R P NUREG/CR4343 RADONUCLtDE CHARACTERl2ATION OF REAC.

NUREGlCR 5647. FISSON PRODUC1 PLATEOUT AND LIFTOFF IN TOR DECMSSOMNG WK AW SW W ASSEW I

THE MHTGR PRIMARY SYSTEM A REVIEW.

HARDWARE.Proyees Report WlERE NG A.P.J.

IANO.L NUREG/CR5716 MODEL VALCATION AT THE LAS CRUCES NUREG/CR4TBO

SUMMARY

OF A WORKSHOP ON SEVERE ACCl-TRENCH SITE' DENT MANAGEMENT FOR (FWAS.

NUREG/CR 5781:

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-WILk E RSON.C.L DENT MANAGEMENT FOR PWRS NUREG/C44670. FIADONUCUDE DISTRIOUTCNS AND M!GRATON MECHAN:SMS AT SHALLOW LAND BURIAL SITES Final Report Of Xt0NGLX.

PNL Research Investigeteor's On The Dettulon, Mystion. And Con.

t4UREG/CR4727. CHLOROE ION DIFFUSON IN LOW WATER tainment Of Racionuclides At Mamey Fiats, Kentuckp SOLID CEMENT PASTES WILK0WSKl,0.M.

Y AN,H.

NUREG/CR45M V01 N1: SHORT CRACAS IN PlPING AND PIPING NUREG/CR 5423 THE PROBABluTY OF LINER FAILURE IN A MARK l wet DS Semiannual Report March-September 1990.

CONTAINMENT.

(

)

68 Pefsonal Author index NUH[ G/C H %77 A UNirit D INTf RPht t Af TON 08 ONF FILTH TO YU D.

F Ut L SGAti 1HE HM Al. MisiN3 L APL BUV(N15 hl L A1iU 1O f hl k NUHLG/CH L tto SUMM AHY Of A nOHKbHUP 04 bl VI hl ACCI-

$UHTLD TH[HMAL $HOCA D( NT MAN AGE Mt NT F OR (JW4S NUHEG'CH 5781 buMMARY OF A WO4kbHOP DN 6tvtHE ACC1 YANO.J W.

r ~.NT MANAGEVi NT F OR hvh5 NU81E G/0ft Lf42 HYDaOGEN Combustion CONTROL.AND VALUE-IMPACT Ar4AL V5!$ F OR (NH DHY CONT A!NMt NTB ZlMMlHMAN.D A-NUr4[G!CR M22 A COMPARteON OF PAHAMtifh i b11M AllON YASUDA,DD.

AND SENS111vt1Y ANAlisiS TESHNIQUE $ AND THilH IMPACT ON fJU4tG/C4 MM iPFP ? A CODE FOR FOLLOWING AlHDORNE fl5 THE UNLt HT AINiv IN GROUND W At[ A F' LOW MODL( Ph( DIC-

$lON PHODuC15 IN Of NihiC NUCLE AR PLANT FLOW PVHS 16DNS YOUNGA ZUBE R,N.

NUrit G/Ch 3145 V09 GL OPHY sic AL INet stiGATIONS Of THE NUR[G 'CA-?,MQ Dhi FC AN INil GHAIED STHUC'l'HL AND hCAL -

WL Sf t hN OHIO INDIANA HtGloed Anrual Negott.Octotet ipB9 ING ML1HODOLOGY f OH $LVth0 ACCIDENT 11', (NICAL ISSUE Seldernt of 1999 Fit SOLUllON lism 84epy1 F ut Comnwnt t

Subject Index This index was developed from keywords and word stdngs in titles and abstracts. During this development period there will be some redundancy, which will be removed later when a rea.

i sonable thesaurus has been developed through experience. Suggestions for improvements a*e welcorne.

10 CFR Part 20 Accident Wenegement Plan NUREG 1446 bT ANDARDS FOR PROTICTION AGAINST RADIATON.

NUREG/CR f.543 A SYSTEMATIC PROCESS FOR DEVELOPING AND 10 CrR PART 20 A Compenson Of The Eusting And Reymed Rules ASSESSING ACCIDENT MANAGEME NT PLANS.

A633 Gr 9 Steel Acc6 dent bequence NUREG/C44667 V12. ENVIRONMENT ALLY ASStSTED CRACKING IN NUREG/CR4674 V13 PRECURSORS TO POTENTIAL SEVERE CORE LIGHT WATER REACTORS Sem6 annual ReportOctater 1990 March DAMAGE ACCIDENTS 1990 A STATOs REPORT Men Report And Ap-1991 pnndm A NUREG/CR4674 Vid PRECURSORS TO POTENTIAL SEVERE CORE ACRS Report

_ DAMAGE ACCIDENTS 1990 A STATUS REPORT.Appendes D And NUREG.1128 V12. A COM ATON OF REPORTS OF THE ADYlSORY C. -

COrAMITTLE ON REACTOR SAF EGUARDS 1990 Annual, Acoustic Emission OEOD NUREG/CR464h ACOUSffC EM;SSION/ FLAW RELATONSHIPS FOR NUREG-1272 V05 NO1 OFFICL FOR APALYS15 AND EVALUATON OF INSERVICE MONITORING OF LWRB OFTRA TONAL DAT A 1990 Annual Reprw1. Power Reactors NUREG-1272 VOS NO2 OFFICE FOR ANALYSl$ AND EVALUATION OF Adyteory Committee On Nuclear Weste OPERATIONAL DATA 1990 Annual Report Nonreactors, NUPEG 1423 V02 A COMPILATION OF REPORTS OF THE ADVISORY COMMITTEE ON NUCLEAR WASTE July 1990. June 1991.

NUREG/CR 3469 V06 OCCUPATONAL DOSE REDUCTON AT NU-Aerosot CLEAR POWER PLANTS ANNOTATED i.1LIOGRAPHY OF SELECT-NUREG/GR4006 CRF FC: DEPOSITION SOrTWARE TO CALCULATE ED READINGS IN RADIATION PROTECNN AND ALARA.

PARTfCLE PE NET RAT")N THROUGH AEROSOL TRANSPORT Abnormal Occurrence NUREG4090 V13 NO3 REPORT TO CONGRESS ON ADNORMAL Aggregate OCCURRENCES July Septemi er 1990 NUREG/CR 4235 $ ELECTION OF SILICEOUS AGGHEGATE FOR NUREG 0090 V13 Nu4 HEPORT TO CONGRESE ON ABNORMAL CONCRET E.

OCCURRENCES October December 1990.

NUREG.0090 V14 N01: REPORT TO CONGRESS ON ABNORMAL A0ing OCCURRENCES January March 1991.

NUREG.1144 R02 NUCLEAR PLANT AGING RESEARCH (NPAR) PRO-NUREG4090 Vta tw1 REPORT TO CONGRESS ON ADNORMAL GRAM PLAN Status And Accomphshments OCCURRENCES AprilJune 1991 NUREG/CR4302 V02; AGING AND SERVICE WEAR OF CHECK NUREG 0090 Vie NO3 REPORT TO CONJnESS ON ABNORMAL VALVES USED IN ENGINEERED 4AFETY.FEATLIRE SYSTEMS OF OCCURFl[NCES July-Septemter 1991.

NUCLEAR POWER PLANTS. Aging Assessments And Morutonng 3

Method Evaluohons N

0 0004 V15 N04 REGULATORY AND TECHNICAL REPORTS

" )R f Ok RO lV[ SYSTEM

^

^

P (ADSTRACT INDEX JOURNAL) Annual Compilation For 1990 NUREG/CR-f,612. DEGRADAflON MODELING WITH APPLICATION TO NUREG-0304 V16 N01; REGULATORY AND TECHNICAL REPORTS AGING AND MAINTENANCE EFFECTIVINESS EVAltlATIONS (ABSTRACT INDE X JOURNAL) Compilabon For Fnt Quarter 1991.Ja'.aary March A6r Sample? Systern NUREG 0304 V16 NO2. REGULATORY AND TECHNICAL REPORTS NUREG/C44757: LINE40SS DETERMINATION FOR AIR SAMPLER (A9STRACT INDEX JOURNAL)_ Compelabon For Second Quarter SYSTEMS.

1991,Apnt-Jule NUREG4304 Vt6 NO3. REGULATORY AND TECHNICAL REPORTS Air Sampling (ABSTRACT INDEX JOURNAL) CompHabon For Third Quarter NUREG 1400 ORrT FC; AIR SAMPLING IN THE WORkPLAPE DraN 1991.Juty September.

Report For Comment Acceptance Criterta Altt>orne Effluent NUREG-1322: ACCEPTANCE CRITERIA FOR THE EVALVAtlON OF NUREG/CR 2907 V09 RADIOACTIVE MATERIALS RELEASED FROM CATEGORY I FUEL CYCLE F ACILITY PHYSICAL SECURITY PLANS NUCLEAR POWER PLANTS Annual Report 1968 Accident Age.m Assessment NUREG 1450- POTENTIAL CRITICAL!TY ACCIDENT AT THE GENERAL NUREG/C45721: VIDEO SYSTEMS FOR ALARM ASSESSMENT.-

ELECTRIC NUCLEAR FUEL AND COMPONENT MANUFACTURING F ACILITi. MAY29,1991.

Alcohol Testing NUREG/CR 4214 RIP 2A1: HEALTH EFFECTS MODELS FOR NUCLE-NUREG/CR 5784. FITNESS FOR OUTY IN THE NUCLEAR POWER AR POWER PLANT ACCOENT CONSEOVENCE INDUSTRY.A Review Of The Fast Year Of Pragram Performance And AN ALYSIS M:ohcahons Of Models Resulting From Recent Reputs On An Update Of The Tectncallasues.

Health Effects Of ioniang Ra$ahon. Low LET Rasahon Part 11: Scianut.

6c Bases For Health.-

Alert Level NUREG/CR 5608: A REVIEW OF THE SOUTH TEXAS PROJECT PROB-NUREG/CR 5611: ISSUES AND APPROACHES FOR USING EQUIP.

ABILISTIC SAFETY ANALYSIS FOR ACCOEN1 FREQUENCY ESTi-MENT REllABILITY ALERT LEVELS, MATES AND CONTAINMENT DINNING.

Anton Enchange Occisent Management NUREG/C45464. ANON RETENTON IN SOtL POSSiBLE APPLICA-NUREGICR 5702-ACCIDENT MANAGEMENT INFORMATION NEEDS TION TO REDUCE MITGRATION OF BURIED TECHNETIUM AND FOR A BWR WITH A MARK I CONT AINVENT, MD!NE A Review 09

70 Subject Index Annealing NURtG ist V2 DNF FC ST ANDARD TICHNICAL Sf'E CIF6CATONS NUREG/CR 57(c REIORT ON ANNE ALING OF THE NOVOVOHON DAECDCK AND WILCOE PLANtB Dam (Sectons 2 0 3 31Dra'i ElH UNIT 3 RE ACTOR VESSEL !N THE USSR Report Frw Commer.t NURt.O 1430 V3 DHF FC ST ANDARD TECHNCAL SPECIHCATIONS UiG 45 V07: U S NUCLE AR REGULATORY COMM!SSON 1990 L m t ANNUAL, F4 POR f Aqueous Solution Baldeypress Tree NUREG/CR6711 ASSESSMENT OF UNCERT AINTIE S IN ME ASURE" NUREGiCR 6749 TECTONIC DEFORMATON Rt VEALED IN DALDCY+

MENT OF PH IN WJSTILE ENVIRONMENTS CHARACTER!STC OF PRESS Tms AT REELFOOT LARTENNESSEE NUCLEAR REPOSITOFUES gelio,e Espansion goint Atomic 8afety And Lkennin Board Panel NURE G rCH -%B1-ANALYbiS OF liELLOWS EXPANSON JOINTS IN NUREG 1363 V03 ATOMi SAFETY AND LICENSING DOARD PANEL THE SE OVOYA6* COf f1 AINMENT.

ANNUAL REPORT Fiscal Year IMO Belo* ground Vautt Attenuation Coeffic6ent NUREG 137(i V02 SMETY EV ALUATION REVIEW OF THE.PROTO-NURE G/CR-$740 NEW GAMMA RAY BUILDUP FACTOR DATA FOR TYPE LCf NSE. APPLICATON SAFETY ANALYSIS PONT KERNEL CALOULATIONS ANS-6 4 3 STANDARD RE)[R.

REPORT Delonground Vault Dentonite Grouting Ausillary Feed,atet NUREG/CR!0A6 EFFECTIVENESS OF FRACTURE SE ALING WIN NURLG/CR 6706 POTENTIAL SAFETY-RELATED PUMP LOSS AN AS-HENTONITE GRO. TING St SSMEN1 OF INDUSTRY DATA NRC Bulletin b6 04 Bolling Water Reactor Austhery Feedwe.et System NUREG 1302. OFFSITE DOSE CALCULATON MANUAL OUCANCE-NURf GiCR.44??: AUMUARY FFEDWATER SYSTEM RISK BASED IN-ST ANDARD RADIOLOGCAL EFFLUENT CONTROLS FOR DOILING SPECTON 610E FOR THE OfRON AND DRAIDWOOD NUCLf"AR WATER REACTORS Ge*ene Letter 89-01 s@plement No 1 5

POWER PL ANTS NUREG/CR 6781: AUrluARY FEEDWATE R SYSTEM RISK-BASED IN.

NUREG-1433 V1 DRF FC' S1 ANDAND TECHNCAL SPECIFICATONS Erf CTION OUtDE F OR THE SALEM NUCLE AR POWER PLANT GENE RAL EllCTRIC UNITS. DWR/4.Spacihcationa Draft Repcit f or NUREG/CR 5763. AUxfLIARf FLEDWATLR SYSTEM RfSK-BASED IN-Comment NUREC 1433 V2 DRF FC: ST ANDARD TECHNICAL SPECIFtCATIONS NL R E 5 UK L A F t TER b TEM ASED N GLNERAL ELECTRIC UNITS. BWR/4 Bases ($cctor.4 2 0 3 3) Draft SPECTION OUCE FOR TH5 GINNA NUCLE AR POWER PLANT-N 14 3 3 FC: STANDAftD TECHNICAL SPECIFICATONS BWR GENERAL ELECf RIC UNITS. BWR/4 Dases (Sectons S 4 310) Deatt NUREG 1307 OF FSf70 DOSE CALCUL ATION MANUAL GUCANCE:

Floport f or Comment ST ANDAfi, RADIOLOGCAL EFF LUENT CONTROLS FOR BOklNG fJUREG-14M VI DRF FC STANDARD TECHNICAL SPECIMCATONS WATEtt RE ACTORS Genenc letter 89-01 Septement No 1.

GENERAL ELECTRIC PL ANTS, DWR/6 Specthcations Dratt Report For NUREG 1433 V1 DRF FC. STANDARD TEdHNCAL SPECIFICATIONS Comment GENERAL, ELECTRC UNITS, BWR/4 Specificehone Draft Report Fog NUREG-1434 V2 DAF FC: STANDARD TECHNICAL SPfCIFICATIONS Comment.

GENERAL CLECTRC PLANTS, DWR/6 Banes (Sectons 20

+

NUREG-1433 V2 DAF FC STANDARD TECHNICAL brECIFCATONS 3 M Draft Report For Comment GENERAL ELECTRIC UNITS, DWR/4 Bases (Sachons 2 0 3 3) Draft NUREG 1434 V3 DRF f C. STANDARD TECHNCAL SPECIFICATIONS Reror1 For Comment GENERAL ELECTRIC PLANTS. BWR/6 Bases (Soctons 34 NUREG-1433 V3 DRF FC. STANDARD TECHNICAs GPECIFICATIONS 310) Draft Repor1 For Comment GENERAL ELECTRIC UNITS DWR/4 Bases ($ccions 3 4 310)Dra t NUREG/CR 4%1 V?R1P2. EVALUATION OF SEVERE ACCIDE NT r

Re-p. ort For Comment NUREG-1434 Vt DitF FC: STANDARD TECHNCAL SPECIFICATIONS RISAS QUANTIFICATION OF MA. LOR INPUT PARAME1ERS Egerts' Determinaban Of contamment Loads And Molton Core Containment GENERAL ELECTRIC PLANTS, BWR/6 Specificatrons Draft Report For interacton tasoos.

Comment NUREG/CR %29 AN ASSESSMENT OF BWR MARK Al CONTAIN-NUREG 1434 V2 DRF FC. ST ANDARD TECHNICAL SPECIFICATONS MENT CHALLENGES, FAILUnE MODES. AND POTENTIAL IMPROVE-GENERAL CL *0lRIC PLAN. L BWR/6 Bases (Sectone 20

• 3 3) Draft Repor1 For Comment.

MEniT9 tN PERF O*tM ANCE NUREG/CR.5M5-THE RESPONSE Or DWR MARK 11 CONT AINMENTS NUREGd434 V3 DRF FG-STANDARD ' HNICAL SPECIFICATONS TO STATION DL.ACKOUT SEVERE ACCOENT SEQUENCES GENERAL ELECTRIC PLANTS, BM J Bases (Sections 34 NUREG/CR-5571; THE F1ESPONSE OF BWR MARK ill CONTAIN.

V2$12 EV LUATON OF SEVERE ACCIDENT NU E C 456 O NE RISKb. QUANTiriMilON OF MA,10R INPUT PARAMETERS Ewports' Detenmnatori Of Containment Loads And Molten Core Containment NUREG/CR-%23 DWR MARK 11 EK VESSEL CORIUM INTERACTON Interact on tasuen AN AL Y St s.

NUREG/CR 652t AN ASSESSMENT OF BWR MARK lit CONTAIN-NUREG/CR b634: IDENTIFICATION AND ASSESSMENT OF CONTAIN-MENT CHALLE NGES, F AILURE MODES, AND POTENTIAL IMPROVE' MENT AND RELEASE MANAGEMENT STRATEGIES FOR A BWR M ARK 1 CONT AINME NT ibNSE OF BWR MARK 11 CONTAINMENTS

"# 0 N REG /C 6 CF NUR C

2h D M N GEMENT INFORMATON NEEDS NURE /

7 E RE P

CONTAtN, ME TO NORTITERM STATION BLACKOUT SEVERL ACCIDENT IO" ^ W"*'

^ M^

^

gggEG CR 6710 UMMA OF P ON SEVERE ACCL.

NUREG/CRM23 DWR MARK in Ex VESSEL CORiUM INTERACTON DENT MANAGEMEN1 FOR DWAS ANALYSEfe NUREG/C45634- (DENTiFCATON AND ASSESSMENT OF CONTAIN.

8#"8 MENT AND RELEASE MANAGEMENT STRATEGIES FOR A BWR NUREG 1445: REGULATORY ANALYSl3 IUR f rte REGOLUTION OF M ARK 1 CONT AINMENT.

GENERC SAFETY ISSUE-2* BOLTING DLGRADATON OR F ALLURE NUREG'C45692: GENERIC RISK INSIGHTS FOR GENERAL ELEC.

IN NUCI E AR POWER PLANTS.

TRIC BOILING W ATER REACTORS NUREG/CR 5702. ACCOENT MANAGEMENT INFORMATION NEEDS Bond Strength FOR A BWR WITH A MARK lCONTAINMENT, NUREG/CR 4295. BOND STRENGTH OF CEMENTITIOUS BOREHOLE NUREG/CR 5780. SUMM ARY OF A WORKSHOP ON SEVERE ACCI.

PLUGS IN WELDED TUFF.

DEPT MANAGEMENT FOR BWHS.

Borehole Plog Bat, cock And Wilcos NUREG/CR 4295 BOND STRENGTH OF CEMENTITIOUS BOREHOLE NUREG 1430 V1 DRF FC. STANDARD TECHNICAL SPECIFICATIONS PLUGS IN WELDED TUFF.

BADCOCK AND WILCOX PLANTS. Specificatons Ctatt Report For NUREG/CR468t ANALYSES AND FIELD TESTS OF THE HYDRAULIC Comment PERFORMANCE Or CEMENT GAOUT BOREFOLE SEALS

l Srbject index 71 0*doet E stirnate Cucumterenhai Fi.*

NURE G it'XI V07 DVDGE T ESilMATE S Fiscal Yee's 1992 lid NURE G,CR Mu2 ANALYTICAL STUDIES OF 1RAN$ VERSE STRAIN Buildup Factor W

W WCW MHW @ WMRM4W NUREG/CR 5740 NEW GAMVA RAY DUILDUP FACTOR DAT A FOR OMNW WW POINT s.E RNE't CALCULATIONS ANS4 4 3 STANDARD FIEFER' Class 1E Safety Statem UA NUREGICR-4%8 CLOSEOUT OF lE BULLETIN 64t2 F AILURES OF DFproduct Material GENERAL ELECTRIC TYPE HFA RELAYS IN USE IN CLASS 1E NUREG'CR 5798. P".OT PROGnAM TO ASSESS PROPOSED BAtlC SAf ETY SYSTEMS OVALITY ASSURANCE REQUIRE MENTS IN THE MLDiCAL USE OF BYPRODUCT MATERIAL Cleavage-Crect inttlatan NUREG/CR 4219 V07 N2 HE AVY4ECTON STEEL TECHNOLOGY CONTAIN 1 PROGRAM hwannual Progress Report For Aid Septemte ipX NURE G/CR $71$ REFERENCE MANUAL FOR THE CONT AIN 11 NUREG/CR-%51: AN INVESTIGATON OF CRACK TIP STRESS FIELD CODE FOR CONT AINMENT SEVERE ACCOLNT ANALYSIS CRITER'A FOR PREDICTING CLEAVAGE CRACK INiilATON.

CONTAIN Cude Closecut NUREG/CR 5518 OVALITY ASSURANCE PROCEDURES FOR THE NUREGICR 4%6 CLOSEOUT OF IE BULLETIN 84 01 FAILURES OF CONT AIN SEVERE RE ACTOR ACCIDENT COMPU11R CODE NUNEG/CR %30 PWR DRV CONI'AINMENT PARAMETRIC StVDIES-GENERAL ELECTRIC TiPE HFA RELAYS IN USE IN CLASS 1E SAFETY SYSTEMS NURER/CR 620h CLOSEOUT OF IE DULLETIN to 13 CRACKING W RE GI P ot t$ PROJEEDINGS Or THE CSf 3 WORASHOP ON PSA APPLICATONS AND Limit ATONS NU CR 288

( OSE 1 OF lE DULLETIN 80 06 ENGINEERED SAFETY FEATURE (ESF) REbti CONTROLS Comer t NUREG/CR 5309 CLOSEOUT OF 11 DVLLETIN 83 07. AhPARENTLY NURLGrCR %01' CertCTS OF PH ON THE RELEASE OF RADIONU.

FRAUDULENT PRODUCTS SOLD ElY RAY MILLER.lNC, CLIDES AND CHElATING AGENTS F ROM CEMENT.SOLIDWlED DE.

CONTAMINATION ON EXCHANGE RESIN 3 COLLECTED FROM Op.

Combust 6cn Engineering ERATING NUCLE AR POWER ST ATIONS NUREG 1432 V1 DRF FC. ST ANDARD TECHNICAL SPECIFICATIONS COMBUSTION LNGINEERING PLANTF Spactications Draft Report Coment Grout ror Comment NUREG/CR 46B4 ANALYSES AND FIELD TESTS OF THE HYDRAULIC NUREG 1432 V2 DRF FC: STANDARD 1ECHNICAL SPECIFICATIONS PERFO WANCE OF CEMLNT GROUT HOREHOLE SEALS COMBUSTION ENGINEERING PLANTS Bases (Sectons 20 Cesr+nt Groutinf 3 3) Draft Report For Comment NUREG 1432 V3 DRF FC: STANDARD 1ECHNICAL SPECIFICATIONS NUREGICR 5t*4 LABORATORY TESTING OF CEMENT GROUTING COMBUSTION ENGINEERING PLANTS Bar,es (Sections 34 OF F RACTURES IN WELDED TUFF.

3 g) p,r.tt Repart For Comment Coment Poste

• E C LO OE lON DIFFUSION IN LOW WATER-TO-gyn7g 4 [YS1EuAtlC APFROACH TO REPEilTIVE FAIL-SO P

URES Certif1cetes Of Compilance NUREG 0383 Vol R14. DIRECTORY OF CERTIFICATES OF COMPLl-Computer Code ANCE FOR RADIOACilVE MA1ERIALS PACKAGES Report Of NRC NUREQ/CR $316-QUALITY ASSUR ANCE PROCEDURES FOR THE Artroved Pacitages CONTAIN SEVERE REACTOR ACCOENT COMPU1ER CODE.

NURLQ4383 V02 R14 DIRECTORY OF CERTIFICATES OF COMPU.

NUREu/CR 5531: MELCOR 18 0. A COMPUTER CODE FOR NUCLEAR ANCE FOR RADCACTIVE MATERIALS PACKAGES Certificates Of REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS.

Comphance MENT ANALYSES.

NUREG 0383 V03 Rtt DIRECTORY OF CERTIFICATES OF COMPLl.

NUREG/CR-6536 DCM3D: A DUAL CONTINUUM, THREE LIMENSION-ANCE FOR RADIOACTIVE MATERIALS PACKAGES Report Of NRC AL GROUND WATER FLOW CODE FOR UNSATURATED, FRAC-Approved Quahty Assu anca Programs For Radioactive Matenals Pack.

TURED, POROUS MEDIA-r ages NUREG/CR 5610 USER'S MANUAL FOR THE NEFTRAN 11 COMPUT.

ER COf4.

Chain Decay NUREG/CR-5656 EXTRAN A COMPUTER CODE FOR ESilMATING NUREG/CR-51$2 R01: VAM2D VARIABLY SATURAT[0 ANALYSIS CONCENTRATONS OF TOXIC SUBSTANCES AT CONTROL ROOM MODEL IN TWO DIMENSIONS Verwon S 2 With Hystercass And Chain AIR INT AKES Decay Transport. Documentation And User's Gede-NUREG/CR 566L INEL PERSONAL COMPUTER VERSION OF MACCS Charpy impact NUREG/CR-M96 IRRADIATON EFFECTS ON CHARPY IMPACT AND Conceptual Model TE NSILE PROPERTIES OF LOW UPPER-SHELF WELOS.HSSI SERIES 2 AND 3.

NUREG/CR-5495: CONCEPTUAll2ATON OF A HYPOTHETICAL HIGH-LEVEL NUCLEAR WASTE RE POSITORY SITE IN Check Valve UNSATURAT[.D, FRACTURED TUF F.

NUREG/CR-4302 V02: AGING AND SERVICE WEAR OF CHECK Concrete VAWES USED IN ENGINEERED SAFETY. FEATURE SYSTEMS OF NUREG/CR-4235: SELECTION OF dillCEOUS AGGREGATE FOR NUCLEAR POWhR PLANTS Aging Assessments And Monitonng men Evabatons.

CONCRETE NUREG/CR-4h69 MODELS OF TRANSPORT PROCESSES IN CON.

Chelatin0 Apen, CRETE NUREGICR-5601. EFFECTS OF PH ON THE RELEASE OF RADONU.

CLOES AND CHELATING AGENTS FROM CEMENT SOLIDIFIED DE, Concrete Bam CONT AMINATION ION EXCHANGE RESINS COL.LECTED FROM OP.

REG /CR-5614 PERFORMANCE OF INT ACT AND PARTIALLY DE-ERATING NUCLEAR POWER STATONS GRADED CONCRETE BARRIERS IN LIMITING FLUID FLOW.

Chemical Toxictty Configuration Control NUREG 1301: CHEMICAL TOXICITY OF URANIUM HEXAFLVORCE NUREG/CR-%41: STUDY OF OPERATIONAL RISK-BASED CONPGV-COMPA"4ED TO ACUTE EFFECTS OF RADIATON Final Report RATON CONTROL Chloelde ton Container Material MUREG/CR.572t CHLOROE ON DIFFUSON IN LOW WATER-TO.

NUREG/CR 5590. IMMER$10N $1t01S ON CANDIDATE CONTAINER SOLO CEMENT PASTES.

ALLOYS FOR THE TUFF REPOSITORY.

i

=

72 Subject index Containment NURE Gt4 D77 CHtOROE ON DarvSON

' OW WAf f R 10-NukEG/CR 4$51 V?AIP2 EVALVATON OF SEVE RE ACGOLNT bOLID CEMLNT PAS 1ES RibKS OVANTIFICATON OF MAJOR INPUT PTRAMETER9 Emperts' Determination Of Contamment loads And Molten Core Containment Crack Intera.bori tasass NUREGICR4699 V01 N1 SHORT CRAMS IN PIPtNG AND PIPING NURE G/CR4561 ANALY$l$ Or BELLOWS ExPANf ON JO4NTS IN WELDS Semiannual Report. Ma<ch September 1930 r

THE SCOVOY AH CONTAINMENT.

NUREG/ORStP8 EVALUAflON AND RETINEMENT OF LEAK RAlt NUREGiCH M7W THE RESPONSE OF BWR MARK 111 CONTAIN-ESTIMATON MODELS MENTS TO E.HORT TikM STATION RL ActOUT Sf: VERE ACCIDENT NUREG/CR 6502 ANALYTICAL STUDIES OF TRANSVE RSE STRAIN SEQUENCE S ElFECTS ON FRACTURE TOUGHNESS FOR CIRCUMFEHENTIALLY NUREG'CR 1400 A REVIEW OF THE SOUTH TEKAS PROJECT PROB.

ORIENTED CRACKS ABILISTIC SA8 ETY ANALYSl$ FOR ACCIDENT FREQUENCY EST).

NUREG/CR 6614. PERFORMANCE OF INT ACT AND PARTIALLY DE+

MATES AND CONTAINMENT DiNNrNG GRADE D CONCRETL BARRIERS IN LIMitlNG FLut0 F LOW.

NUHEG/CR StOO PWR DRY CONTAiNULNT PARAMETRC STUDIES NURlG/CR 0654. CONT AINME NT VENTING ANALYSIS FOR THE Crack Arrest SHOREHAM NUCtt AR POWER STATION NUREG/CR 66#7 USE Or THICKNESS REDUCTON TO ESTIMATE NUREG/CR $667. HVDROGEN COMBUS* )N CONTROLAND VALUE-VALUE S OF n IMPACT ANALYSIS FOR PWR dry CONTAINMEN1S NUREG/CR 6691 IN%TRUMENTAflON AVAILABluTY FOR A PRES-Crack Growth SURIZED WATER DE ACTOR WITH A LARGE DRY CONTAINMENT NUREG/CR4667 V09 ENVIRONMENTALLY AS$!STED CRACKif4G IN DURWG SEVERE ACCIDENTS LIGHT WATER RE ACTCRS Semiannual Report.Apr&Septemter 1989 NUREG/CR4707. APPUCATON OF CONTAINMENT AND RELE ASE NUREG/CR4667 V10 ENVIRONMINTALLY ASSISTLD CRACAING IN MANAGEMENT TO A PWR ICE CONDENSER PLANT.

LOHT W ATER REACTORS Semiannual Report. October 1989 March Containment Heat 6ng NUREG/CR 6282 ESTIMATON OF CEP7AINMENT PRE $$URE LOAD.

Cracking ING DUE TO DIRECT CONTAINMLNT HEATING FOR THE TON NUREG/CR428% CLOSEOUT OF IE BULLETIN 7913 CRACKING IN PLANT-FEEDWATER &YSTEM PIPING.

Containment Pressure Cross System f ailure NUREG/CR4287. ESilMATON OF CONT AINMENT PRESWRE LOAD-NUREG4276 V06. OPERATING EXPERIENCE FEEDDACK REPORT -

ING DUE TO DIRECT CONT AINMENT HEATING FOR THE ZON 4

PLANT, SOLENOIDOPERATED VALVE PROBLEMS Commercial Power Read 99,,

Containmoi.t Vessel DCM3D NUREG/CR 6b51. TWO NEW NDT TECHNIOUES FOR INSPECTON Or CONT AlwMENT WELDS BENCATH COATINGS Fmal ReportOctobe' NUREu/CR 0536 DCM'tO A DUAL CONTINUUM, THREE DIMENSION-1989

• March 1990 AL, GROUND-WATER FLOW OODE FOR UNSAiliRATED, FRAC-TURED, POROUS MEDIA.

Conunuovo Co%

NUREG/GR4001 EFFECT OF PROR DErORMPOtt ON SEN6titZA' DEPOSITION Computer Code TION DEVELOPMENT IN STAINLt SS STEEL vRING CON 11NUOUS NUREG/GR 0006 DAF FC: DEPOSITION SOFTWARE TO CALCULATE COOUNG PARTICLE PEHETRATOh THROUGH AEROSOL TRANSPORT LINES Deatt Report For Comment Contract Research NJREG-0975 V08 COMPILATON OF CONTRACT RESEARCH FOR 8* '

U 4

O E IVATON AND COMP &ATON OF DOE -

4 GINEL ING n et A For 990.

= WASTE PACKAGE TEST 4 TA Biannual Report February 4u91989.

Controf Rn1 Drive Decommissioning -

NUREG/CR4555: AGING ASSESSMENT OF THE WESTINGHOUSE NUREG 1307 R02: REPOHT ON WASTE DURIAL CHARGES Encatation

(

PWR CONTROL ROD DANE SYSTEM Of Decornemssemng Waste Disposal Costs At Low level Waste Durial F aolities -

Control Room NUREQ/CR4343: RA@ONUCLtDE CHARACTERIZATON OF REAC.

NUREG/CR 6656 EXTRAN A CO*4PUTER CODE FOR E3TIMATING TO9 DECOMMISbONING WASTE AND SPENT FUEL ASSEMBLY CONCENTRATONS OF TOJRC buBSTANCES AT CONTROL ROOM HARDW ARE Progress Report Decontamination Control Room Opersiot NUREG 1442:

POST EMERGEN ' RESPONSE -RESOURCES NUREG/JR4669. EVALUATION OF EXPOSURE LIMITS TO TOKIC GUOE Based On The Post Emergency TABLETOP Enercise in Baton GASU FOR NUCLEAR REACTOR CONTROL ROOM OPERATORS Rougeloumana.On August to And Septemter 18,1990-NUREG/C43444 V08 THE IMPACT OF LWR DECONTAMINATONS Cochng Thermal cycle

- ON SOUDIFICATON. WASTE DISPOSAL AND ASSOCIATED OCCU-NURIG/GR4002. CONTINUOUS COOLNG THERMAL CYCLE EF.

PATIONAL EXPOSURE Effects of Compositen On The FECTS ON SE NSITIZAf ON IN STAINLESS STEEL Strength Swelling, And Water-Immerw.n Properties of Coment-Sohdi.

fed non-Enchan0e Resin Westes NUREGICR-4063 AN INVESilGATON Or CORE LIOulD LEVEL DE.

Deformation -

PRESSON IN SMAL L RREAK LOSS OF COOLANT ACC3 DENTS NUREw/GR4003 EFFECT OF PROR DEF^RMATION ON SENSITIZA-Core Damese TON DEVELOPMENT IN STAINLESS STEEL OURING CONTINUOUS COOLING.

NUREGIGr04674 V13 PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCCENTS 1900 A STAlVS REPORT. Main Report And Ap.

Degradation Pen $t A NUREG/CR 56 t DEGRADATON MODEUNG WITH APPLICATION TO NUREG/CR 4674 V14. PRECURSORS TO POTENTIAL SEVERE CORE AGlNG AND b AINTENANCE EFFECTIVENESS EVALUATONS.

DAMAGE ACCOENTS 1990 A STATUS REPORT.Appendines B And C.

Denelty NUREGICR 5680: MECHANICAL CHARACTERl2ATION OF DENSELN Coie Welt WELDED APACHE L.EAP TU%

NUREG/CR 5654, CONTAINMENT VENTING ANALYSIS FOR THE SHOREHAM NUCLEAR POWER STATION.

Depressurization Correalon NUREG/CR-5647, FISSON PRODUCT PLATEOUT AND UFTOFF IN THE MHTG4 PROARY SYSTEM A REVIEW NUREGICR 4269. MODELS OF TRANSPORT PROCESSES IN CON.

NUREG/C45647; FISSION PRODUCT PLATEOUT AND LIFTOFF IN CRETE THE MHTGR PRIMARY SYSTEM. A REVIEW.

- - -. -. - - -. -. - ~. -. -

Subject index 73 i

Despn CcWal Practice NUREGICR 4744 Vot N2 LONG. TERM IMBRITTLEMHit OF CAST NUHEG 1H1 AN A%ESSMENT OF DESIGN CON 1ROL PRACTICEh DUPLEX STAINLESS STEELS IN LMt SYSTEMS Senvannual i

AND DES 6GN RECONSTITUTON PROGRAMS IN THE NUCLE AR Report. April September 1990 POWER INDUST RL NURtG/CR-4818 R01: PR-EDD POWER REACTOR EMRR!TTLEMENT D3 sign Reconstitution Progrem f4URFG 1391 AN ASSESSMENT OF DE$iGN CONTROL PRACitCES Emergency Planning AND DESIGN RECONSTITUTION PROGRAMS IN THE NUCLE AR NUREG 1389 PREAPPLICATION SAFETY EVALVATION HEPORT FOR POWE R INDUSTR Y, THE SODIUM ADVANCED F AST RE ACTOR (SAFR) LIQUID METAL Dstonation NVREG/CR 662$ HYDROGE4 AIR-DILVENT DETONATION STUDY Emer9ency Respor to Data System FOR NUCLEAP REACTOR SAFETY ANALYSEL NUREG 1394 R0t: EMERGENCY RESPONSE DATA System (ERDSl IMPLE MENT ATION NUHEG/CR 6727 CHLORIDE lON DIFFUSION IN LOW WATER-TO.

Enforcement Actiort SOLtO CEMENT PASTES NUREG 0940 V09 N04 ENFORCEMENT ACTIONS SIGNIFICANT AC.

Ohact Containment Heating NU81EG/CR 6728 EkPERIMINTS TO INVESTIGATE THE tFFECT 08 NUREG4940 V10 N01: ENFORCEMENT ACTIONS SIGNIFICANT AC-FLIGHT PATH ON DlHECT CONTAINMENT HEmilNG (DCHI!N THE TiONS RESOLVE 0 Ouartedy Progren Repod 'onuary March 1991.

SURTSE Y TEST F AcilitY.The Limited Ileght Patn (LF P) Tests NUREG.0940 V10 Not tNrORCEMENT ACTONS blGNIFICANT AC-TlONS RESOLVED Ouarter rent ReportApr& June 1991.

Dose-Reduction 1echnique NUREGot40 V10 NO3: Et4f RC MLNT ACTIONS SIGNIFICANT AC-NURLG/CR 6132 DOSE REDUCTION 1ECHNiOVE0 FOR HIGH-DOSE T40NS RESOLVED Qua'teHy Progress Repor1JWy Sertember ; 391 WORAER GROUPS IN NUCLEAR POWER PLANTS Engineered Safety Feature R

B8 C F

U MMWMG N

/CA-5139 ECSEMDUCilON TECHNIQUES FOR HIGH-DOSE 3A V ATURt F FS T T k$

WORKE*1 UROUPS IN NUCLEAR POWER PLANTS.

NURES/CR f,768 tCE CONDENSER AEROSOL TESTS FE / $784 FITNESS FOR DUTY IN THE NUCLEAR POWER NR CR V0 A AND SERVICE WEAR OF CHECK INDUSTRY A Review Of The First Year Of Program Performance And VALVES USED IN ENGINEERED SAFETY 4EATURE SYSTEMS Or An Update Of the Techrucalissues NUCLEArt POWER PLANTS Agog Assessments And IA Wlonng DuratWity Method Evaluations NU

/CR 235. SELECTION OF SILICEOUS AGGFIEGATF. FOR

~

Environmentui Assessmerrt NUREG 1308. ENVIRONMENTAL ASSESSMENT FOR FINAL RULE ON ERDS NUCLEAR POWER PLANT LICENSE RENEyrALFinal Roport N R O 139 R MERGENCY RESPONSE DATA SYSTEM (CROS) l Env6tonmentaltmpact Statement NUREG 1437 V1 DRF F C: GENERIC ENVIRONMENTAL IMPACT EXTR AN Computer Code STATEMENT FOR LICENSE RENEWAL OF NUCLE AR PLANTS Man NUREGeCR %56 ExTRAN A COMPUTER CODF FOR ESTIMATING Reort Dra t Rouort For Comment r

CONCENTRATIONS OF Toxic SUBS 1 ANCES AT CONTROL ROOM fiUREG 1437 - v2 DAF FC: GENERIC ENVIRONMENTAL IMPACT AIR INTAKES STATEMFNT FOR LICENSE RENEWAL OF NUCL. EAR PLANTP Appendn.es Draft Report For Comment Etrthqualie NUREG/CH 3145 V09 GEOPHY$1 CAL INVE%hGAT,0NS OF THE Environmental Protection WEETERN OHIOINDIANA REGtON Annual ReporLOctober 1989 NUHEG-1429 DRFT FC: EPNIRONMENTAL STANDARD REVIEW PL AN Saptembar 1990 FCR THE REVIEb OF LICENSE RENEWAL APPLICAtlONS FOR NU-NUREG/CH M85 THE HIGH LEVEL V19 RATION TEST PROGRAM Fmat Ctf AR POWER PLANTS Draft Report For Comment Report NUREG-1440 ORFT FC: REGULAlORY ANALYSIS OF PROPOSED AMENDENTS TO REGULATIONS CONCERNING THE ENVIRON-Effluent Monitortn9 MENTAL WVIEW FOR RENEWAL OF NUCLEAR POWER PLANT NUREG 1301. OFFSITE DOSE CALCL.LATON MANUAL GUIDANCE:

OPERATING LICENSEb Draft Report For Common'.

STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR PRES-SURIZED WATER RE ACTORS Genene Letter 69 01. Supplement No.

Equipment Qualification 1.

NUREG/CR-565$ SUBMERGENCE AND HIGH TEMPERATURE STEAM NUREG 1300, OFFMTE DOSE CALCULATION MANUAL GutDANCli TESTING OF CLASS 1E ELECTRICAL CABLES STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR BOILING WATER REACTORS Gencnc Lette* 69 O t.Suoplement No.1.

Equipment Reliablitty NUREG/CR 5611: ISSUES AND APPROACHES FOR USING EQUIP.

Electric Cable MENT REllABILITY ALERT LEVCLS.

NUREG!CR 6546: AN INVESTIGATION Off THE fFFECTS OF THER-MAL AGING ON THE FIRE DAMAGEABILITY OF ELECTRIC CABLES Event NUREGICR 5019 THE IMPACT OF THERMAL, AGING ON THE FLAM-NURE3/CH 3964 V02. TECHNIQUE? FOR DPERMINING PROBADIL.

MABILITY OF ELEC1RIC CABLES ITIES CF EVENTS AND PROCESSES AFFECTING THE PERFORM-ANCE OF GEOLOGIC REPOSITORIES Suggested Appro&ches '

NUREG/CR 5655. SUOMERGENCE AND HIGH TEMPERATURE STEAM Event Reporting System TESTING OF CLASS 1E ELECTRICAL CABLES.

NUREG 1022 Roi DR FC: EVENT REPORTING SYSTEMS 10 CFR 50.72 AND 50 73 Clanficaton Of NRC Systems And Guioelines for Embrittlement Reportng Dratt Report For Comment NUREGICR4744 V04 N1; LONG. TERM EMBFilTTLEMENT OF CAST OUPLEX STAINLESS STEELS IN LWR SYSTEM 9 Semiannual En YestelCorium Repo.rt October 1988 March 1989 NUREG/CR 5623 BWR MARK ll ELVESSEL CORIUM INTERACTION NUREG/CR-4744 V04 N2. LONG-TERM EMBRITTLEMENT OF CAST ANALYSES DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiavun' ReportApr4Septerr ber 1989 Emploratory Shaft Factitty NUREG/CR-4744 V05 N1; LONG TERM EMBRITTLEMENT OF CAST NUREG-1439 STAFF TECHNICAL POSITION ON REGULATORY CON-DUPLEX STAINLESS STEELS IN LWR SYSTEMS Gemiannual SIDERATIONS IN THE DEStGN AND CONSTRUCTION OF THE Ex-Repor1, October 1989 March 1990.

PLORATORY SHAFT FACtLITY, g.yyq.-.

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74 Subject index 63posure NUREG/CP4017 PROCEEDINGS Or THE SEMINAR ON ASSESS-NUREG/CR 53M RADONUCLIDE BEHAVOR IN THE ENVIRCNMENt.

MENT OF FRACTURE PREDICTON TECHNOLOGY. ?iPING AND E 8P0"d Llmil PRESSURE YESSELS NUREG/CR-4599 V01 N1 SHORT CRACAS IN PIPING AND PIPING NUREG/CR S669 EVALUATON OF DPOSURE LIMITS TO TOxlC GASES FOR f4UCLE V4 REACTOR CONTROL ROOM OPERATORS WE LDS $emiennual Reput March $eptember 1970 NUREG/CR 5126 EVALUAtlON AND REFINEMENT OF LE AK RATE E sposure Pathway ESilMATON MODELS NUFif G/CR4377. REVIEW OF THE CHRONIC E APQSURE PATHWAY NUREG/CR4577. E XT ENSION AND EXTRAPOLATON OF 1R MODELS IN MACCS AND SEVERAL OTHER WELL,KNOWN PFO' E" RVES AND THEIR APPUCATION TO THE LOW UPPER SHELF ADIUSTIC RISK ASSES $ VENT MODELS TMHNESS ISSUE NUREG/CR4651: AN INVESTIGATON Or CRACK,ilp STRESS FIELD Esternet Ennt CR. FERIA FOR PRED CTING CLE AVAGE. CRACK INITIATO%

NUREG 1407. PROCEDURAL AND SUBMIT 1 AL GUIDANCE FOR INDI-NUREG/CR 5703 LOWER BOUND INITIATON TOUGHNESS WITH A VIDUAL PLANT EXAMtNATION CF EXTERNAL EVENTS (IPEEE) FOR M

SEVERE ACCIDENT VULNERABrdflES Final Report' ggR R 76 i L EE VOR OF SHALLOW FLAWS IN RE ACTOR PRESSURE VESSELS FOREC AST Computer Code NUREG/CR 5595. FORECAST REGULATORY EFFECTS COST ANALY, Fracture Bear,g SIS SOFTWARf MANUAL Verseon 3 0.

NUREG/CR4686 EFFECTIVENESS OF FRACTU84E SE AtlNG WiTH BENTONITE GROUTING FPFP2 i

NUREG/CR 56% (PFP 2 A CODE FOR FOLLOWiNG AIRBORNE FIS.

Fracture Toughness SON PRODUCTS IN GENERIC NUCLE AR PLANT rLOW PATHS NUREG'1374. TECHNICAL FINDINGS RELATED TO GENERIC ISSUE Feedwstor Syelem Piping 79 An Evaluaton Of PWR Reactor Vettet Thermal Streat Dunng Natu-rM Convecion Coolkwn NURtWCR 5265 CLOSEOUT OF IE BULLETIN 7613 CRACKING IN NUREG/CR J513-ESTIMATION OF FRACTURE TOUGHNESS OF

$ EEDWATER SYSTEM P Plt 4G CAST STAINLESS STEELS DUntHQ THERMAL AGING IN LWR SYS-NURE /CR 5546 AN INVESTtGATON OF THE EFFECTS OF THER-N EG CR-4744 V04 N1: LONG TERM EMDRITTLEMENT OF CAST MAL AGING ON THE FIRE DAMAGEt.BluTY OF ELECTR!C CABLES

1. U 8 M W #

Report.0ctobor 1988 March 1989 Fieston NURIG/CR-4748 V04 N2: LONG-TERM EMBRITTLEMENT OF CAST NUHEG/CN 5488: DAT A

SUMMARY

FIEPORT FOR FISSON PRODUCT DUPLE! ST r Ja$ STEELS IN LWR SYS TEMS Semiannual RELEASE TEST VF4 RetortApril September 1989 NUREG/CR-4744 VOS N2: LONG-TERM EMBRITTLEMENT OF CAST F6esion Product DUPLEX STAINLESS STEELS IN LWR SYSTEMS $emiannual NUREG/CR 5346. FISSION PRODUCT RELEASE AND FUEL B'HAV.

Report. April-September 1990 LOR OF lRRADIATLD LOHT WATER AEACTOR FUEL UNDER NURFG/CR4592-ANALYTICAL STUDIES Or TRANSVERSE STRAIN SEVERE ACCIDENT CONDITIONS The ACRR ST 1 E sponment.

Eff/ECTS ON FRACTURE TOUGHNESS FOR CIRCUMFERENTIALLY NUkrG/CR 6647. FISSION PRODUCT Pl.ATEOUT AND L'F10FF IN ORIENTED CRACKS 1HE MHTGR PRIMARY SYSTEM A REVIEW-NURLG/CR-5658 FPFP i A TODE FOR FOi10WlNG AIRBORNE FIS-NUREG/CR S696 IRRADIATON EFFECTS ON CHARPY IMPACT AND SON PRODUC'S IN GENERIC NUCLE AR PLANT FLOW PATHS TENSILE PROPERTIES OF LOW UPPER SHELF WELDS.HSSI NURE 8

A

SUMMARY

RE PORT FOR Fl$SION PRODUCT SERitS 2 A14D 3 NUREG/CR 57tJ LOWER-BuuND INITIA70N TOUGHNESS WITH A

^

PR t biU N SUP R ION HUREG R 729 M LTl RABLE MODEUNG OF PRESSURE VESSEL AND PIPING JR DATA.

Fitness-For Duty NUREG/CR 5767: THE BEHAVOR OF SHALLOV/ FLAWS IN REACTOR NUREG/CR 5758 V01. FITNESS FOR DUTY IN THE NUCLEAR POWER PRESSullE VESSELS.

IN STRY. Annual Summary Of Pro 3 ram Forformance Reports.CY Fractured Media NUREG/CR 5764 FITkESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR 5795: VAUDATION AND TESTING OF THE VAM2D COM-INDUSTRY.A Rev6ee Of The Fut Year Of Program Perforrnance And PUTER CODE.

An Update Of The Techrucal issuet p

Flammablilty NUREG/CR 558t: UNSATURATED FLOW AND TRANSPORT NUREG/CR4619 THE IMPACT OF THERMAL AGING ON THE FLAM.

THROUGH FRACTURED ROCK FIELATED TO HIGH-LEVEL WAS*E MABILITY OF ELECifitC CABLES.

REPOSITORIES. Final Report. Phase ill Filght Path Fractured Tuff NUREGICR 5728- (XPERIMENTS TO INVESTIGATE THE EFFECT OF NUREG/CR4495: CONCEPTUAUZATON OF A HYPOTHETICAL HIGH-FLIGHT PATH ON DlHECT CONTAINMENT HEATING (OCH) IN THE LEVEL NUCtEAR WASTE REPOSITORY SITE.

IN SURTSEY TEST F ACluTY.The Linted F hght Patn (LFP) Tests, UNSATURATEDf RAUTURED TUFF, Flow Path NUREG/CR 5701. A PERFORMANCE ASSESSMENT METHODOLOGY NUREG/CR 5658 FPFP 2: A CODE FOR FOLLOWING AIRDORNE FIS*

FOR HOH-L EVEL RADtOACTIVE WASTE DISPOSAL IN blON PROOtiCTS IN OFNERC NUCLEAR PLANT FLOW PATHS.

UNSATURATEDJRCTURED TUFF.

Flow Stratification Freudulent Product NUREG/CR4456 ANALYSIS OF FLOW STRATIFICATON IN THE NUREG/CR 5309. CtOSCOUT Or C BULLETIN 0347: APPARENTLY SURGE UNE OF THE COMANCHE PEAK REACTOp FRAVOULENT FRODUCTS SOLD BY RAY MILLER,1NC Fluid Flow Frequency Response NUREG/CR 5614. PERFORMANCE OF ICACT ANE ARTIALLY DE.

NUREG/CR-4967: RELAY TEST PROGRAM Senes i Vibration Tests.

GRADED CONCRETE BARRIERS IN LMTING FLUID FLOW Fuel Dama9e Fracture NUREG/CR449!: DAT A

SUMMARY

REPFHT FOR FISSON PRODUCT NUREG/CR4603 LABORATORY TESTING OF CEMENT GROUTING HELEASE TEST via OF FRACTURES IN WELDED TUFF.

=

NUREG/CR 5668 DATA

SUMMARY

REPORT FOR FISSON PRODUCT Fracture Mechanica NUREG-1426 V01: COMPILATION OF REPORTS FFIOM RESEARCH Fuel Disruption SUPPORTED DY THE MATERIALS ENGINEERING NUREG/CR 5312 A THERMODYNAMIC MODEL OF Ft/EL DISRUP-BRANCH.D$VISON OF ENGINEERING 1965 - tEO.

TlON IN ST.t.

Subject Index 75 7 undamental Nucleer Waterial Control Geostatistic NUnlGICR 5734 RECOMMENDATIONS TJ 1HE N6C ON AGCEP%

NUREG/CR$522 A COMPARISON OF PARAMETLR ESilMATION DLE STANDARD FORMAT AND CONTENT FOR THE FUNDAMEN-

1. A SENSITivlTY ANALYSIS TECHNOUES AND 1 HEIR IMPACT 04 TAL NUCLE AR MATERtAL CONTROL (FNMC) PLAN REQUIRED FOR W UNCERT AINTY IN Gr.OUND WATER FLOW MODEL PREDIC.

LOW E.NRCHED URANIUM ENRICHMENT FAC41 TIE S ttONS NU R $740. NEW GAMMA RAY DiSLDUP F ACTOR DA1 A FOR UC/

77 L Al POSITON!NG SYSTEM MEASUREMENTS NEL CALCULATONS ANS 6 4 3 STANDARD REFER.

OVER A STRAIN MON'TORING NETWORK IN THE EASTERN TWO-THIRDS OF 1HE UNITED STATES.

General Electric HUREG #413 Yt DAF FC. STANDARD TECHNCAL SPECIFICATONCL Grwnd Release GENERAL ELECTRC UNITS, BWR/4 Speuhcahons Draft Report Fo, NUREGIC4%80 LOW-LEVEL WASTE SOURCE TERM MODEL DE-Comment VELOPMENT AND "ESTING NUREG 1433 V2 DAF FC; ST ANDARD TECHNICAL SPECIFICATIONS GENERAL ELEC1RC UNITS, BWR/4 Bases (Sectons 2.0 3 3) Dra4 Ground Water Nw1 For Comment NUREG/CR 5622 A COMPARISON Or PARAMETER ESilMATION NUREG 1433 V3 DRF FC. ST ANDARD TECHNICAL SPECIFCATIONS AND SENSITIVITY ANALYSIS TECHNOUES AND THEIR IMPACT ON

- GENERAL CLECTRC UNITS, BWR/4 Bas.s (Sections 3 4 3.10) Drah THE UNCERTAINTY IN GROUND WATER FLOW MODE'l PREDIC.

Ratert For Comment.

TIONS NURLO-1434 V1 DRF FC: STANDARr) TECHNICAL SPECIFICATIONS NUREG/C45636 DCM3D A DUAL CONTINUUM, THPEEelMENSONJ GENERAL ELECTRIC PLANTS, BWR/6 Specrheations Draft Agri F~

AL, GROUND WATER FLOW CODE FOR UNSATURA1ED, FRAC-IGY4$4 V2 DRF FC $?ANDARD TECHNCAL SPECIFICAtlONS N

GENERAL ELECTRIC PLANTS. BWR/6 Bases (Sachons 20 Ground water Flow 3 3]Drsh Report Fe Comment NURt.G 1434 V3 DRF FC-STANDARD TECHNICAL bPECIFICATONS NUHEG/CA $794. GROUND WATER FLOW A.4D TRANSPORT MODEL.

ING OF THE NRC UCENSED WASTE DISPOSAL FACluTY. WEST

- GENERAL ELECTRC PLANTS, BWR/6. Bases (Sections 3.4 310) Draft Report For Comment, VALLEY

• NEW YORK' Generic Communication HTON Type Rsector NUREG/CR4690 V01 Rt GENERIC COMMUNCATONS NUREG/CR %20; THATCH. A COMPUTER CODE FOH MODELUNG INDEX ushngs Of Communicatu;ns 1971 198g THERMAL NETWORKS OF HIGH TEMPERATURE GAS COOLED NU-CLEAR REACTORS.

Leneric issuo 023 NUREG 1401 DRFT FC REGULATORY ANAL,YSl$ FOR OGNERC Hazard inden ISSUE 23 RE ACTOR COOLANT PUMP SEAL F AILURE Draft Report NUREG 1400 DRPT FC. AIR SAMPLING IN THE WORKPLACE Draft For Comment Report For Commerit NUREGrCR 5167: COST /BENErlT ANALYSIS FOR GENERIC ISSUE 23 REACTOR COOLANT PUMP SEAL FAltURE.

Hazardous Waste Disposal NUREG/CR 5464: ANION RETENTION IN SOIL: POSSIDLE APPUCA-NU

$ EGULATORY ANALYSIS FOR THE RESOLUTION OF GE NERC SAFETY ISSUE F9 BOLTING DEGRADATON OR FAlLURE DINE.A Review, IN NbCLE AR POWFR PLANTS Health Effects Model Generic issue 073 NUREG/CR-4214 RtP2At HEALTH EFFECTS MODELS FOR NUCLE.

NUREG-1374 TECHNICAL FINDINGS RELATED TO GENERIC ISSUE AR POWER PLANT ACCIDENT CONSEQUENCE 79 An Evaluahon Of PWR Rea tor Vessel Thermal Stress Dunng Natu.

ANALYSIS Modif4atens Of Models Resulting From Recent Reports On tal Convection Cocktowrt Health Effects Of lonizing Radation Low LET Ra&ation Part IL Scwotit-6c Bases For HeaNh.

Generic issue 08F NUREQ/CR4558 GENERC ISSuk 6h FLExlBLE WEDGE GATE Heat Transfer V ALVE TEST PROGP.AM Phas911 Results And Analysis NUREG/CR-6620: THATCit A COVPUTER CODE FOR MODELLING Generic issue 130 THERMAL NETWORKS OF HIGH1EMPERATURE GAS-COOLFD NU.

NUREG 1420 REGULATORY ANALYSIS FOR THC RESOLUTON OF CLEAR REACTORS' g

GENERC iSAUC 130 ESSENTIAL SERVCE WATER SYSTEM FAIL-Heatup Accident URES AT Mblin UNIT SITES NUREG/CR 5712: MORECA: A COMPUTER CODE FOR SIMULATING Generic issue 136 MODULAR HIGH TEMPERATURE GASCOOLED REACTOR CORE NUREG/CR 4893 TECHNCAL FINDrNGS REPORT FOR GENERg HLATUP ACCIDENTS.

ISSUE 126 Steam Genersier And Staam Une Overhil isues Heavy Section Steel Technology Program Generte Safety issue NUREG/CR 4219 V07 NL HEAVY SECHON STEEL TECHNOLOGY NUREG U933 501 12: A PRCRf 2ATON OF CENERIC SAF ETY PROGRAM Serruannual Prog 6ess Repo/t for October 1989. March l$$UES 1990.

NUREG 093J SIP A PRORITl2ATION OF GE{i{RC dAFETY tSSUES.

NURFG/CR-4211 V07 N2; HEAVY SECTON STEEL TECHNOLOGY Milie Sa^ #"f&#*S#E#'iSSJS WieiSsS PROGRAM Somsannual Hogteas Report For April September 1990.

D POWER PLANTS IMI Action Plan Regarements unre oived Safety High-Dose Nh514$o3 TNS OF SAFETY ISSUES AT UCENSED POWE A PLANTS Generic Safe WORKER GROUPS IN NUCL EAR POWER PLANTS.

"""ASE%'na'Ps"ankissuen

"'"* $^" 'S$u'" a "~

" *' ~i R =~~ W - a --'

NUREG/CR 5639 UNCERTAINTY EVALUATION VETHODS FOR Geologic Media WASTE PACKAGE PERFORMANCE ASStESSMEN*

NUREG/CA-5743. APPROACHES TO LARGE SCALE UNSATURATED FLOW IN HETEROGENEOUS. STRATIFIED, AND FRACTURED OEO, High-Level Waste LOGC MEDIA.

NUREG-1439 STAFF TECHNICAL POSITION ON REGULATORY CON.

SIDERATIONS IN THE DESIGN AND CONSTRUCTION OF THE EX-Geologne Repoaltory PtORATORY SHAFT FACILITY.

NUHEG/CR-3964 v02; TECHNIOUES FOR DETERMINING PROBABIL.

NUREGICR4964 V02: TECHNOUES FOR DETERMINING PROBASIL-

- ITIES OF EVENTS Af

• PROCESScS AFFECTING THE PERFORM-ITIES OF EVENTS AND PROCESSES AFFECTING THE FERFORM.

ANCE OF GEOLOG;C FIEPPJITOR'ES Sutgested Approaches ANCE OF GEOLOGC REPOSITORIES Sygested Approaches.

76 Subject index High-Level Waste Disposal NUREG 1455 TRANSFORMER FAILURF AND COMMON MODE LOSS nut *G/CR s618 USER S MANUAL FOR THE NEFTRAN il COMPUT.

OF INSTRUME NT POWER AT NtNE MILE POINT UNIT # ON ERCODE AUGUSI 13,1991.

NUHEGrCR $701 A PERFORMANCE ASSESSMENT METHODOLOGY FOR HIGH-LEVEL RADOACTfvE WASTE DISPOSAL IN inc6 dent Response UNSATURATED. FRACTURED TUFF.

NUREG 1441. LESSONS LEARNED FROM THE POST EMEROFNCY 1 ABLETOP E*ERCISE IN BATON ROUGE.LOUlslANA.ON AUGUST H69Movel Waste Repostlory 28 AND SEPTEMBER 18,1990 NUREG/CR 5495 CONCEPTUAlllATION OF A HYPOTHETICAL HIGH-NUREG 1442 POST. EMERGENCY RE SPONSE RESOURCES LEVEL NVCLEAR WASTE REPOSITORY SITE IN GUIDE.Bassd On the Post Eerergoncy TABLETOP Esercise in Baton UNSATURATED.F RACTURED TUF F.

Rouge,Loumana.On August 28 Arus Septemter it.1990 NUREG/CR-5537. APPROACHES FOR THE ir ALIDATON OF MODELS USED FOR PERFORMANCE ASSESSMENT OF HIGH LEVEL NUCLE-Individual Plant Easmination AR WASTE REPOSITORlES NUREG-1407; PROCEDURAL AND FJBMITTAL GUIDANCE FOR INDL NUREG/CRM81; UNSATURATED FLOW AND TRANSPORT VIDUAL PLANT EyAMiNATION OF EXTERNAL EVENTS (IPEEE) FOR THROUGH FLACTUF.ED ROCK RELATED 10 HIG4 LEVEL WASTE SEVERE ACCOENT VULNERABILITIES lanal Report REPOSITORIES Final Report Phase lit induced Seismietty Hostile Environment NUREG/CR-5778 V01: NEW YORK /NEW JERSEY REGONAL SEtSMIC f4UREG/CR 5711: ASSESSMENT Or UNCERTAINTIES IN MEASURE

• NETWORK Annual Report For April 1989 March 1990.

MENT OF PH IN HOSTILE ENVIRONMENTS CHARACTERISTIC OF NUCLEAR REPOSITORIES.

Industrial Ra6.ography NUREG-0713 Vio OCCUPATIOtwAL RADIATON EXPOSURE AT COM-hffy^fgg h^ny y

^"

REG / M43 A SYSTEMATIC PROCESS FOR DEVELDPING AND p

ASSESSING ACCIDLNT MANAGEMENT PLANS Informat6on D# gest NU EG/

49 8 V05-- CONTROL OF WATER INFILTRATION INTO NUREG-1350 V03. NUCLEAR REGULATORY COMM!SSION INFORMA-NEAR SURF ACE LLW DISPOSAL UNITS Progress Report On Field E, D6m WM penments At A Humid Regson Site.Beisviile, Maryland' inse<vice Inspection Hydraulic Conductivity NUREG/CR-4469 V11: f40NDESIRUCTIVE EXAMINATION (NDE) RELL NUREG/CR 5684 ANALYSES AND FIELD TESTS OF THE Hr'RAULIC ABtLITY FOR INSEnVICE INSPECTON OF LIGHT WATER PERFORMANCE OF CEMENT GROUT DOREHOLE SEALS RE ACTORS SemFAnnual Report Apr$ September 1909, NUREG/CR 5686: EFFECTIVENESS OF FRACTURE SEALING MTH BENTONITr UROUTING I"'

F CG CR 5551,1WO NEW NC1 CCHNIQUES FOR INSPE'CTION OF ltydrogen Combustion CONTAINMENT WELDS BENEATH COATINGT Ofiel ReportOctober NUREGICR$525. HYDROGEN A14 DILUENT LTTONATION STUDY 1989. Muen 1930.

FOR NUCLEAR REACTOR SAFETY ANALYSES-NUREG/C45662 HYDROGEN COMBUSTION. CONTROL.AND VALUE.

hspection Nide IMPACT ANALYSIS FOR PWR DAY CONTAINMENTS.

NURES

,4427; AUXIUARY FEEDWATER SYSTEM RISK-BASED IN-SPEC :MN GUIDE FOR THE BTRON AND BRAIDWOOD NUCLEAR Hydrogeologic POWE R PLANTre.

NUREG/CR 5714. HYDROGEOLOGIC Pl,RFORMANCE ASSESSVH I NUREG/CR4467. RISK BASED INSPECTON Gt.nDii e uYSTAL ANALYSIS OF THE LOW-LEiEL RADIOACTIVE WASTE DISPOSAL RIVER UNIT 3 NUCLEAR POWER PLANT.

F ACILITY NEAR SHEFFIELD, ILLINOIS.

NUREG/CR 5717. PACKAGING SUPPLIER INSPEvu. a uva NUREG/CR 5137: HYDROGEOLOGIC PERFORMANCE ASSESSMENT NUREG/C45761: AUXILLARt' FEEDWATER SY 3 TEM RISK BASED IN-ANALYSIS OF THE COMMERCIAL LOW LIVEL RADIOACTIVE SPECTON GUIDE FOR THE SALEM NUCtE AR POWER PLANT.

WASTE DISPOSAL FACILITY NEAR WEST VALLEY,NEW YORK.

NUREG/C4576P AUXILLARY FEEDWATER SYSYEM RISK-BASED in SPECTION GUIDE FOR THE CALEAWAY NUCLEAR POWER PLANL Hydrostatic Constraint NUREG/CR 5764 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-NUREG/C44219 V07 NL HEAVY SECTON STEEL TECHNOLOGY SPECTION GUIDE FOR THE GINNA NUCLEAR POWER PLANT.

PROGRAM Serrnannual Progest Report For April-September 1990 NUREG/CRM51; AN INVESTIGATION OF CRACK TIP STRESS FIELD instrument Power CR!TERIA FOR PREDICTING CLEAVAGC CRACK INITIATON.

NUREG 1455 TRANSFOPMER FAILURE AND COMMON-MODE LOSS OF INSTRUMENT POWER AT NiNE MILE POINT UNIT 2 ON NU EG/CR 4666: CLOSEOUT OF IE DULLETIN 8442: FAILURES OF GENERAL ELJCfRIC TYPE HFA RELAYS IN USE IN CLASS 1E Intrusion Detection System HURE R2 C OSEOUT OF IE BULLETIN 79-13 CRACKING IN FEEDWATER SYSTEM PIPING god, p NUREd/CR 5288. CLOSEOUT OF IE BULLETIN 80 06 ENGINEERED SAFETY FEATURF (FSF) RESET CONTROL 3 NUsG/CR-4757; LIN1 LOSS DETERMINATOM FOR AIR SAMPLER SYSTEMS NUREGICR 5309 CLOSEOUT OF IE BULLETIN 8347; APPARENTLY-NUREG/CR[5464: ANION RETENTION IN Soil: POSSIBLE APPLICA-FRAUDULENT PRODUCTS SOLD BY RAY MILLER tNC.

TON TO REDUCE MITGRATON OF BURIED TECHNETIUM AND IRRAS ODINE A Revww.

NUREG/CR-5300 V01: INTEGRATED RELIABILITY AND RISK ANALY-NUREG/CR 5732 ORF FC: LODINE CHEMICAL FORMS - IN LWH St$ nySTEM CRRAS) VERSION 2 5 Reierence Manual.

SEVERE ACCIDENTS Draft Report For Comment NUREG/CRM20: PROCEDURES GUIDE FOR EATPACTING ANO D

PROBABILISTIC RISK ASSESSMENT DATA INTO HAR-D lon-Eschange riesin Waste NUREG/CFL5601; EFFEUTS OF PH ON THE RELEASE OF RADIONU-CLtDES AND CHELATING AGENTS FROM CEMENT. SOLIDIFIED DE.

Ice-Condenser CONTAM.WATON ION EXCHANGE F1ESINS COLLEC'ED FROM OP-NUREG/CR-5758 ICE CONDENSER AEROSOL TESTS _

. ERATING NUCLEAR POWER STATIONS incentive Regulation toniong Radiatlur -

NUREG/C44911: INCENTIVE REGULATON OF NUCLEAR POWEq NUREGICR.4214 R1P2A1: HEALTH EFFECTS MODELS FOR NUCLE-PLANTS By STATE REGULATL,RS AR POWER PLANT ACCIDENT.

CONSEQUENCE ANALYSIS ModAcations Of Modets Resulting From Recent Reports On incident investigat6on -

Health Effects Of lonlano Radiation Low LET Ra$ation.Part (L Scentif-

- NUREG-1303 R01: INCIDENT INVESTIGATON MANUAL ic Bases For Hea%.-

1 Subject index 77 treedtsted Reactor Fuel tMtE G /CR4732 DAF F C-ODINE CHEM CAL FORM 9 IN LWR NUREG 0725 H07: PUBLtc INFORYATON CIRCULAR FOH SHA SEvtRE ACCIDENTS Enatt Npor1 For Gum *nent MENTS OF IRRADIATt.D PEACTOR FUEL NUREG/CR 5768 ICEOONDENSER AEROSOL TESTS trrediation Las Cruces Ytench Site NUREG/CR %96 1RPADIATION f3 FLCTS ON CHARPY IMPACT AND NUREG/CR 5716 MODEL VALIDATION AT THE LAS CRUCES TENS!LE PROPE Rite S OF LOW UPPER SHELF WELDS.HSSI TRENCH SITE SERIES 2 AND 3 Leeching isolation Valve NUREG/CR 6681. LOW-LEVEL WASTE SOURCE TERM MODEL DE.

NUREG/CR $558 GENERIC (SSUE 87: FLLX1BLE WEDGE GATE VELOPMENT AND TESTING VALVE TEST PROGRAM Phase il Results Ahd Analysta Leak Rate NU G/CR S$77. EXTENSON AND EXTRAPOLATION O*

J-R St A CURVES AND THEIR APPLICATON TO THE LOW UPPER SHELF TOUGHNESS 'SSUE Legal issuances NUREG/CR-5129 MUtilvARIABLE MODELING 08: PRESSURE NUREG 07!0 V32102 INDEXES TO NUCLEAR REGULATORY COM-VE SSEL AND P! PING J R DAT A.

MISSION ISSUANCE S July-Decette' 1990 LER tsuREG-0760 V32 N0! NUCLEAR REGULATORY COMMISSON IS-NUREGICR-2000 V09N12 LEENSEE EVENT REPORT (LER)

EARREbtA RY COMMISSON IS-NURE G 50 2 NU EG V0 L $$E VENT RFPORT (LER)

SUANCES FOR DLCEMoER 1990 Pages 39k496 1991.

NUREG-0".0 33101: INDEXES TO NUCLEAR REGULATORY COM-COMP 1LATION For Month Of Janu75EE NUREG/CR-2000 V10 N2-UCE EVENT REPORT (LER)

MISSON ISSUANCESJanuary-Mwch 1991.

COMPIL ATION For Manth Of Fetwua 1991.

NURf G-07M V33102. INDEXES TO NUCLEAR REGULATORY COM-NUREG/CR 2000 V10 N3-LICEN EE EVENT REPORT (LE R)

MISSION ISSU ANCE S January Jur* 1991 COMPILATON For Month of March 1991.

NUREG 0760 V33 N01' NUCLEAR F1GULATLAY COMMISSON IS-NUHEG/CR 2000 V10 N4 LICENSE E EVE NT REPORT (LER)

SUANCES FOR JANUARY 1991. Pagos 140 COMPIL ATON For Manth Of April 1691..

NUREG 0750 V33 NO2 NUCLEAR REGULA10RY COMMISSON IS.

NUREG/CR 2000 V10 NS LICENSEE EVENT FEPORT (t ER}

SUANCES FOR FEBRUARY 1991. Pa9es 61173 COMPILATON ror Month of May 1991 NUREG 0750 V33 NO3 NUCLEAR REGULATORY COMMISSON IS-NUREG/GR-2000 V10 N6 LICENSE E EVENT REPORT (L E R)

SUANCES FOR MARCH 1991.Pages 174232.

COMPILATION For Month of June 1991.

NUREG4750 V33 N04 NUCLEAR REGULATORY COMMISSON (S-NUREG/CR 2000 V10 N7-LICENSEE EVfNT REPORT 4ER)

SUANCES FOR APRIL 1991 Pages 233 293 COMPILATION For Month of Juty 1901.

NUREG4750 V33 tob. NUCLEAR REGULATORY COMMS$1vN IS.

NUREG/C M 00u V10 N9 LICENSEE EVENT REPORT (LE R)

SUANCES FOR MAY 1991 Pages 295J59 COMPILATION For Month Of Aagust 1991.

NUREG-0750 V33 N00 NUCLLTR REGULATORY COMMISSON IS-NUREGICR 2000 V10 N9 LICENSEE EVENT REFORT (LER)

SUANCES FOR JUN21991 Pages 461619.

COMPILATION For Month Of September 1991 NUREG-0750 V34 N01: NUCLEAR REGULATORY COMMISe C N IS-NUREC /CR-209 V10N10 LICENSEE EVENT REPORT (! ER)

SUANC8ES FOR JULY 1991.Dages 1148.

COMPIL ATIC 'for Month of Octoter 1991.

NUREG-0750 V34 NO2. NUCLEAR REGULATOlly COMMISSION IS-NU, REG /CR 2000 V10N t1: LICENSE E EVENT REPORT (L ER)

SUANCES MR AUGUST 1991 Pages 149-183, v0MPILATION For Month Ol N.,vernter 1991*

NUREG-0700 V34 NO3 NUCLEAR REGULATORY COMMISSION IS-LWR SUANCES FOR SEPTEMBER 1991. Pa9es 164228 NUREG/CR4444 V08 THE IMPACT OF LWR DECONTAMINATONS NUREG4750 V34 N04 NUCLEAR RFGULATORY COMMi$SION IS-ON SOLIDIFICATON, WASTE DISPOSAL AND ASSOCIATED OCCU-SUAUS A OCTM m Pages 22m f ATIONAL EXPOSURE Effres Of Composition On The Leesons Learned erength Swalhrg Ard Water Wnersion Pmperties of Cement Sold NUREG 1441: LESSONS LE ARNED FROM THE POST EMERGENCY N RE /

v 0

iRUCTIVE EXAMINATION (NDE) REll-TABWOP MRQSE W WON RMWSAM MM 28 AND SEPTEMBER 13,1990.

ADILITY FOR INSERVICE INSPECTION OF LIGHT WATER RE ACTORS Semo Annual Report, Aptd-Septamter 19 fig License Application NUREG/CR-4513 ESTIMATION OF FRACTURE TOUGHNESS OF T STAINLESS STEELS DURING THERMAL /.GING IN LWR SYS-NURE".c1199 R02: STANDARD FORMAT AND CONTENT OF A Li-CENSE APPLICATION FOR A LOW LEVEL RADIOACTIVE WASTE i UREG/CR-4067 V09 ENVIRONMENTALLY ASSISTED CRACKING IN DISPOSAL FACW LIGHT WATER REACTORS. Serruannual Report.Aord-Se NUREG-1200 R02: STANDARD REVIEW PLAN FOR THE REVIEW OF A NUREG/CR-4667 V10. ENVIRONMtNT ALLY ASSISTED btomber 1989 RACKING IN LICENSE APPUCATION FOR A LOW-LEVEL RADIOACTIVE WASTE LIGHT WATER REACTORS Semannual ReportOctober 1989 March DS SAL F Cill g

NUREGICR-4667 VII. ENVIRONMENTALLY ASSISTED CRACKING IN TYPE LICENSE APPUCATON SAFETY ANALYSIS LIGHT WATER RE ACTORS Semannual Report,Aptli-September 1990.

FIEPORT Belowground Vault.

i NUREG/CR-4667 Vit ENVtRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS. Serruantml RepoaOctober 1990 March hnte Renewal 1991.

NUREG,1144 R02: NUCLE AR PLANT AGING RESEARCH WPAR) PRO-NUREG/CR4144 V04 N1: LONG. TERM EMBRITTLEMENT OF CAST GRAM PLANJtatus Ar.d Accomphahments DUPLEX STAINLESS S1 EELS IN LWR SYSTEMS Semannua; -

NUREG 1362: RECULATORY ANALYSIS FOR FINAL RULE ON NUCLE-ReporLOctober 1}88 Much 1989 AR POWER PLANT * ' CENSE RENEWAL Feal Report.

NUREG/CR-4744 V04 NE LONG-TERM EMBRITTLEMENT OF CAST NUREG 1398 ENVIRONMENTAL ASSESSMENT FOR FINAL AULE ON DUPLEX STAINLESS STEELS IN LWR SYS"MS Semiannual NUCLEAR POWER PLANT LICENSE RENEWALFinal Report Report.Aprd September 1989 NUREG-1412; FOUNDATION FOR THE ADEOUACY OF THE LICENS-NUREG/CR 4744 V05 N1: LONG TERM EMBRITTLAENT OF CAST ING BASES A Supplement To The Stater,ent Of Cons.deratione For DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semannual The Rute On Nuclear Power Plant License Renewal (10 CFR Port $4)

ReportOctobat 1999. March 1990 Final Report NUREG/CR4744 V05 N2 LONG TERM EMBRITTLEMENT OF CAST NUREG 1428 ANALYSIS OF PUBLtC COMMENTS ON THE PROPCSED DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual ROLE ON NUCLEAR DOWER PLANT LICENSE RENEWAL Rep. ort. April-Septornber 1990 NUREG-1429 ORFT FC: ENVIRONMENTAL STANDARD REVIEW PLAN NUREG/CR 5345: FISSO'l PRODUCT RELEASE AND FUEL BEHAV-FOR THE REVIEW OF LICENSE RENEWAL APPUCATONS FOR NU OR OF LARADIATED LIGHT WATER REACTOR FUEL UNDER CLEAR POWER PLANTS Draft Repor1 For Comment SEVERE ACCIDENT CONDITIONS The ACRR ST 1 openment NUREG 1437 V1 DRF FC: GEMRIC ENilRONMENTAL IMPACT NUREG/CR-5643: ACOUSTIC EMISSON/ FLAW RELATONSHIPS FOR STATEMENT FOR LICENSE RENEWAL OF NUCLEAR PLANTS Main INSERVICE MONITORING OF LWRS ReportDraft r'leport For Comment.

. ~.

78 Subject Inder NUREG 1437 V2 DRF FC GliNERiC ENWnONWNT AL #r4 CT NUREGCR 4744 V00 N1 LONG TERV EMBitt1LEMEtJT OF CAST STATEMENT FOR UCENSE RE NEW AL L# NUCLEAR DUPLE X STAINLESS STEELS IN LWR SYSTEMS Semiannual Pt ANTS Appendees Droft Report For Comment As wt October 1989 March 1930 NUREG-1440 DRFT FC. REGULATORY ANALYSIS OF 5% POSED NURIQ/CR-4744 VOS N2. LONG-TER*A EMBRITTLEt1ENT OF CAST AMENDuf 4TS TO RtGVLATONS cot 4CERNING Thli ENVIRON-DUPLE X STAINLESS STEELS IN LWR SYSit MS Sem aeuel MENTAL REVIEW FOR RE NEWAL OF NUCL&AP POWER Pt.AN1 ReportAprSSeptemter 1990.

OPE 4ATING UCEN5t S Dram R_ eptv1 For Commant NUREG/CR 5346 F15 SON FHODUCT RELE ASE AND FUEL BEHAV-NUREGICR SM2 $CREENING OF GENERIC SAFETY ISSUES FOR LI-IOW OF IRRADIATED LIGHT WATER RE ACTOR FUEt 'JNDER CENSE RENE WAL CONSIDERAf TONS SEVERE ACCIDENT CONDITONS The ACRR St.t Espenn wt t.lconsed Fuel Feelitty Status Report NURFGICA 6645 ACOUS1tC EMISSON/ FLAW RELATONSHIPS FOR INSERVICE MONITORING OF LWRS' CHEF'ICAL NUREG 0430 V10' UCENSED FUEL FACILITY STATUS NUREQ/CR $132 DRF FC: LOD!NE FORMS IN LWR AEPORT Inventory Ofte'erce Data July 1999. June 1990 (Gray Book II)

SEVERE ACCtDENTS DraN RePtdl For Comment NUREG/CR 5768 #CE CONOLNSER AEROSOL TESTS.

Uconned Operating Reactors NUREG 0020 V16 LICENSED OPERATING REACTORS STATUS SUM' y ng MARY REPOHT.Detu As Of Decomtwa 31,1990(G1af Dook 1)

NUREG/CR 4757: LINE-LOSS DETERMINATION FOR AIR SAMPLER SYSTEMS.

Ucensee Event Report NUREG 10n RO1 DR FC: EVENT REPORTING SYSTEMS 10 CFR Liner Failure 50.72 AND 6013 Clanteahon 'M NRC Systems And Gudelines to, f4UREG/CR $423 THE PROBABluTY OF LINER FAILURE IN A MARK 1 Reportmg Dratt Atport For Comment CON 1 AINME NT.

,]

NURLG/CH 2000 v09h12-UCENSE C EVENT REPORT (LER)

NL EG/ 2 V

CE E

ENT REPORT (LER)

NU G/C45282 ESTIMA1 CONTAINMENT PRESSURE LOAD.

COMPILATION For Month 0f January 1991_

ING DUE TO DIRECT CONI AINMENT HEATING FOR THE ZON NUREG/CR 2000 V10 N2. LICENSEE EVENT REPORT (LE R)

PLANT, COMPIL ATION For Meth of Fettuery 1991 NUREG/CR 2000 V10 N3: LICENSEE EVENT REPORT (LER)

Lose Of Coolant Acc6 dent COMPLATON For Month Of March 1991.

NUREQ/CR 4063 AN INVESitGATON OF CORE LOUID LEVEL DE-NUREG/C" T000 V10 N4.

LICENSEE EVENT REPORT (LER)

COMPILATION For Month Ot Aprit t991 PRESSION IN SMALL BRE AK LOSS OLCOOLANT ACCIDENTS NUREG/CR $395 VO1: MULTILOOP INTEGRAL SYSTEM TEST NURE G/GR-2000 V10 NS-UCENSEE FVENT REPORT 3ER)

(MIST) FINAL RLPORT Summ COMPILATION For Month Of May 1991-NUREG/CR $670: MULTILOOPNTEGRAL SYSHM fEST (MIST) MIST NUl;EO/CR 2000 V10 No. UCENSEE EVENT REPORT (LE R)

COMPILATION Fo' Month Of June 1991 FACitJTY FUNCTIONAL SPf CIFICATION NUAEG/CR 2000 V10 N7. UCENSEE EVENT REPC1T (LER)

Low Enriched Uranium NU EG/

VO N8 i

SEE EVENT REPORT (LER)

NUREG/GR 6734 RECOMMENDATIONS TO THE NRC ON ACCEPTA-COV9t ATION For Month of A BLE STANDARD FOR"AT AND CONTENT FOR THE FUNDAMEN-Lkast 1991 NUMEG/CR 2000 V10 N9 ENSE E EVENT REPORT (LER)

TAL NUCLEAR MATERIAL CONTROL (FNMC) PLAN REOUIRED FOR COMPILATON For Month Of September 109g LOW. ENRICHED URANIUM ENR6CHVENT F ACILITIES NUREG/CR 2000 V10N10; LICENSEE EVENT REPORT (LER)

COMPILATION ror Month Of October 1991 L ow-Level Weste NUREG/CR 2000 V10N11: LICENSEE EVENT REPORT (LE R)

NUREG/Ch-4670, RADONUCLIDE DISTRIBUTONS AND MIGRATION COMPILATON For Month of November 1991, MECHANISMS AT SHALLOW LAND BURIAL SITES Final Report Of Uconsing Bases PNL Research investigatons On The Dstnbution. SAgraten, And Con-NUREG 1412. FOUNDATION FOR THE ADEOUACY Or THE UCENS-tainment Of Hadecinuchdes At Maxey Flats, Kentucky ING BASES A Supplement To The Statement Ot Considershh For NUREG/CR 5432 V01: RECOMMENDATIONS TO THE NRC FOR SOlt The Rule On Nuclear Power Piar t Ucer se Rene*al (10 CFR Pvt t*

COVER SYSTEMS OVER URANIUM MILL TAluNGS ANO LOW-Final Report L.EVEL RADIOACTIVE WASTES Idantifcation And Ranking Of Soits ro, Dispossi Facthty Covers.

NUREG/C45432 V02: RECOMMENDATONS TO THE NRC FOR SOIL NUREG/CR-5647: FISSION PRODUCT PLATEOUT AND UFTOFF IN COVER SY3TEMS OVrR URANIUM MILL TAILINGS AND LOW.

THE MHTGR PRIMARY SYSTEM A REVIEW-LEVEL RADIOACTIVE WASTES. Laturatory And Field Tests For Sod Covers Ught Water Reactor NUREG/CR 5432 V03. RECOMMENDATONS TO THE NRC FOR SOIL NUREG/CR.3444 V08 THE IMPACT OF LWR DECONTAMINATIONS COVER SYSTEMS OVER URANIUM MILL TA! LINGS AND LOW-ON SOUDiFCATON. WASTE DISPOSAL AND ASSOCIATED OCCU-LEVEL RADIOACTIVE WASTES, Construction Methods And Guidance PATIONAL EXPOSURE Ettects Of Composition On The a

Pene n

s

~

g lNTACT AND PARTIALLY DE-n n Propedies of ConwSohs lo En h R n s

GRADED CONCRETE BARRIERS IN LIMITING FtulD FLOW NURCG/GR 446b11: NONDESTRUCTIVei EXAMINATION NDE) REll.

NUREGICR 5672 V01: CHARACTERISTICS OF LOW LEVEL RADIOAC-L ABluTY FOR INSERvlCE !NSPECTON OF UGHT WATER TiVE WASTE. Occontamination W.ste.Annu.! Report For Fiscal Year ESYAI F

TU E T )UGHNESS OF N

G/C145681: LOW-LEVEL WASTE SOURCE TERM MODEL DE-NU GC 53 T STAINLCSS STEELS DURING THERMAL AGING IN LWR SYS-N T TI i

NUREG/C44667 V09: ENVIRONMENTALLY ASSISTED PRACKING IN SOURCE TERM.

UGHT W ATER RE ACTORS Semiannual ReportApni-Septemter 198t NUREG/CR-5791 VAUDATION AND TESTING OF Tl;E VAM20 COM-NUREG/CR-4667 V10; ENVIRONMENTALLY ASSISTED C'RACalNG IN PUTER CODE.

L HT WATuR REACTORS. Semiannual ReporLOctober 1983 March NUREG/CR+667 ir11: ENVIRONMENTALLY ASSISTED ORAv.NG Ig NUREG 1199 R02-STANDARD FORMAT AND CONTENT OF A u, UGHT WATER REACTORS Semiannual Report >pr* September 1990.

CENSE APPLtCATON FOR A LOW 4 EVEL RADIOACTIVE WASTE NUREG/C44667 V1i ENVnONMENTALLY AS$15TED CRACKING IN DISPOSAL FACIU1Y.

UGHT WATER REACTORS. Semiannual ReportOctober 1990

• March NUREG 1200 RC2: STANDARD REVIEW PLAN FOR 1HE REVIEW OF A 1991.

LiCENSd APPLICATION FOR A LOW LEVEL RADIOACTIVE WASTE NUREG/C44744 V04 N1: LONG-TERM EMBRIT1LEMENT OF CAST DISPOSAL FACiUTY.

DUPLEX ST AINLESS STEELS IN LWR SYSTE JS $emiannual NUREG-1293 R01: QUALITY ASSURANCE GUIDANCE FOR A LOW-Repor10ctober 1988 March 1989 LEVEL RADOACTIVE WASTE DISPOSAL FACILITY, f4UREG/CR-4744 V04 N2 LONG. TERM EJBRITTLEMENT OF CAST NUREG-1375 V02; SAFETY EVALUATION REVIEW OF THE PROTO-DUPLEX STAINLESS STEELS IN LWR SYSTEMS $emiannual TYPE LICENSE APPUCATION SAFETY ANALYSIS Report.Apr* September 1989

. REPOR f Belowgecund Vau't.

Subject index 79 NURE G/CR-4918 W5 CONTROL OF WATER INriL* ATON INTO Migration NEAR SUHF ACE LLW DISPOSAL UNITS Prog <ess Res t On Field Es-NUREG/CR 4670 RADONUCUDE DISTRIBUTONS AND MiGRATON penments At A Had Re.go. n Site Beltsville Maryland MECHANISYS AT SHALLOW LAND BURIAL SITES Fmal Report Of NUREG/cR 5343 RADONUCLCE CHARAC1E m2ATON OF REAC-PNL Research invest.gations On The Distobuton. Migration. And Com TOR DECOMMISSONING W ASTE AND SPENT FUCL ASSEMBLY tamment Of Redionuclides At Maxey Flats. kontacky HARDWARE Prog'ess Report NURrGiCR-5539 A SELF 1E ACHING CURRICULUM FOR THE NRC Mintoeding Fuel SNL LOW LEVEL WASTE PERFORMANCE ASSESSMENT METHOD.

NUREG/CR 5771 PROBABILITY AND CONSEQUENCES OF Mist.6AD.

^

NU E /CR 5713 A REVIEW OF ENVIRONMENTAL CONDITONS AND PERFORMANCE OF THE COMMERCIAL LOW-LEVEL RAbOACTIVE M;t!gation W ASTE DISPOSAL r ActuTY NE AC SHEFFIELD ILLINOIS NUREG/CR 5714 HYDROGEOLOGIC PERFORMANCE ASSESSMENT NUREG/CR-5634 IDENTIFICATON AND ASSESSMENT CF CONTAIN-ANALYSIS OF THE LOW 4EVEL DADIOAC1tVE WASTE DISPOSAL MENT AND RELEASE MANAGEMENT STRATEGtES FOR A BWR FACluTY NEM SHEFFIELD ILUNOIS M ARK l CONT AINMENT' NURE G/CR 5737. HfDROGEDLOGIC PERFORMANCE ASSESSMENT Model Val 6dation ANALYSIS OF THE COMMERCIAL LON LEVEL P ADOACTIVE WASTE DISPOSAL F ACluTY NEAR WEST VALLEY,NSW YORK.,

NUREGICR-5716 MOUEL VALIDAilVN AT THE LAS CRUCES TRENCH SITE.

MACCS Computer Code NUREG/CR 5304 RADIONUCLtDE BEHAVIOR IN THE ENVIRONMENT, Modeta And Results Data Base NUREG/CR 5377. REVIEW OF THE CHRONIC EXPOSURE PATHWAY NUREG/CR-5520 PROCEDURES GUOE FOR EXTRACTING AND MODELS IN MACCS AND SEVERAL OTHFR WELLANOWN PROB.

LOADING PRODABluSTIC RISh ASSESSMENT DATA INTO MAR-0 ABIUSilC R!SK ASSESSMANT MODELS USING IRRA* 2.5 NUREG/CR %67. INEL PERSONAL COMPUTER VERSION OF MACCS 15 Modified-Charpy specimert NUREG/CP $703. LOWER BOUND IMTIATION TOUGliNESS WITH A NUREG/CR 5330 MELCOR ANALYSES FOR ACCOENT PROGRES-SiON ISSUE S Modular HTOR NUREG/CR %31. MELCOR 18 0 A COMPUTER CODE FOR NUCLE AR NUREG/CR 5712. MORECA A COMPUTER CODE FOR S;MULATING REACTOR SEVERE ACCOENT SOURCE TERM AND R!SK ASSESS-MENT ANALYSES.

MODULAR HIGH TEMPERATURE GAS COOLED REACTOR CORE HEATUP ACCOENTS.

MHTGR NUREG/CR-5647: FiSSON PRODUCT PLATEOUT AND LtFTOFF tN Men Debris THE MHTGR PRIMARY SYSTEM A REVIEW NUREG/UR4728 EXPERIMENTS TO INVESTIGATE THE EFFECT OF NUREG/CR W47: FISSON DRODUCT PLATEOUT AND LIFTOFF IN FLIGHT PATH ON DIRECT CONTAINMENT HEATING (DCH) IN THE THE MHTGR PRIMARY SYSTEM. A REAEW SURTCEY TE ST FACILITY,The L.irrwted Flight Path (trP) Tests.

klST Monitoring NUREG/CR $395 V01: MULTILOOP INTEGRAL SYS TEM TEST NUREG/CR 5645 ACOUSTIC EMISSON/ FLAW RELATONSHIP3 FOR (MIST) FINAL REPORT. Summary INSERVICE MON!TOHING OF LWRS.

NUREG/CR 5670. MULTtLOOP iNTEGR/L SYSTEM TEST (MIST) MIST F ACluTY FUNCTONAL SPECIFICATION Multiloop integral System Test MORECA Computer Code NUREG/CR-539'. V00 MULTILOOP INTEGRAL SYSTEM TEST NUREG/CR 5712. MORECA. A COMPUTER CODE FOR SIMULATING (MIST) FINAL REPORT Summary NUREG/CR 5670. MULTlLOOP INTEGRAL SYSTEM TEST (MIST) MIST MODULAR HIGH-TEMPERATURE GAS COOLED REACTOR CORE HEATUP ACCOENTS.

FACluT( FUNCTIONAL SPECIFICATION NEFTRAN 11 Computer Cmle UR G CR 5%6. PROGRAMMATIC ROOT CAUSE ANALYSIS OF MAINTENANCE PERSONNEL PERFORMANCE PROBLEMS CODE.

NUREG/CR-5695 A PROCESS FOR RISK FOCUSED MAINTENANCE.

NRC Approved Packages Mark 1 Containment NUREG-0383 V01 R14. DIRECTORY OF CERTIFICATES OF COMPU.

NUREG/CR-5423 THE PROBABILITY OF LINER FAILURE IN A MARK 1 ANCE FOR RADCACTIVE MATERIALS PACKAGES Peport Of NRC CONTAINMENT.

Approved Packages.

NUREG/CRM34 IDENTIFICATON AND ASSESSMENT OF CONTAIN-MENT AND RELEASE MANAGEMENT STRATEGIES FOR A BWR NRC Buhetin 86-04 V ARK I CONT AINMENT, NUREGICR-5706: POTENTIAL SAFETY RELATED PUMP LOSS: AN AS-NUREG/CR 5702: ACCIDENT MANAGEMENT INFORMATON NEEDS SESSMENT OF INDUSTRY DAT A NRC Bulletm BB-04.

FOR A SWR WITH A MARK l CONTAINMENT.

Navler Stoke Mark Il Containment NUREG/CR 5456: ANALYSIS OF FLOW STRATIFICATION IN THE NUREG/CR-5565, lHE RESPONSE OF BWR M ARK fl CONTAINMENTF SURGE LINE OF THE COMANCHE PEAK REACTOR _

TO STATON BLACKOUT SEVERE ACCIDENT SEQUENCES, Mark Ill Containment Neutron NUREG/CR-5648. TRANSPORT CALCULATINS OF NEUTRON NUREG/CR-5529 AN ASSESSMENT OF BWR MAR 6 111 CONTAIN-TRANSMIS$0N THROUGH STEEL USING ENDF/B-V, REVISED MP CA ENGES FA L RE MODES. AND POTENTLAL IMPROVE-ENDF/B-V.AND ENDF/B-VI1RON EVALVATIONS.

Mechanical Vitwation Neutron Shleid Tank NUREG/CA-4067: RELA v TEST PROGRAM Senes i Vibration Tests.

NUREG/CR 5748. RADIATON EMBRITTLEMENT OF THE NEUTRON SHIELD TANK FROM THE SHIPPINGPORT REACTOR Wedical Screening NUREG/CR-5689 MEDICAL SCREENtNG REFERENCE MANUAL FOR

. Nondestructive Examination SECURITY FORCE PERSONNEL AT FUEL CYCLE FACluTIES POS.

NUREG/CR-4469 V10 NONDESTRUCTIVE EXAMINATION (NDE) REll-SES$1NG FORMULA QUANTITIES OF SPECIAL NUCLEAR MATERi.

ABluTY FOR INSERVICE INSPECTION OF LIGHT WATER ALS ROCTORS Serrw Annual Report. Apni-September 1989-Medical use Nondest uctive Testing NUREG/CR-5799. PILOT PROGRAM TO ASW.SS PROPOSED BAStC NUREG/CR 5550 TWO NEW NOT TECHNIQUES FOR INPPECTON OF QUAUTY ASSURANCE REQUIREMENTS W THE MEDICAL US" OF CONTAINMENT WELDS BENEATH COATINGCFinal ReportOctober BYPRODUCT MATERIAL 1989. March 1990 1

80 SemitCtindex Notification Requirement Offolte Dose Cateutauan Manual NUREG 1022 401 DR FC EVEtei uEPORiiNG SYStLMS 10 GFH NUHLG 1301 OF F SHE DOSE CALCULAllON M ANJAL UUIDANC:

60 72 AND 50 f 3 ClatAcat on Of NRC Systems And Gukielmes for ST ANDARD RADIOtOGICAL ElFLUENT CONTROLS FOR PRES-Reportag Dren Report For Comment SURF 7ED WATER REACTORS Genenc Letter 6901,$upplemAnt No 1

Novovotoneth Unit 3 NUREG.1302. OFFhlTE DOSE CA(COLATION MANUAL GUIDANCE NUREG/CR-SM AEPORT ON ANNE ALING OF THE NOVOVORON-STANDARD RADCLOGICAL EFFLUENT CONTROLS FOR DOILING E 2H UNIT 3 RE ACTOR VESSEL IN THE USSR WATE R REACTORS Generc in ter 6D41. Supplement No.1.

(

Nuclear Air Clos 31ng Op an Eap enc NUREG/CP 0116 VD1: PROCEEDINGS OF 1HE 21ST DOE /NRC NU.

,,,p 01: OFFICf FOR ANALYWS AND EVAtVATION OF CLEAR AIR CLEAN 1NG CONSERENCE Sessons 14 8 Held N San OPE RATION AL DAT A 1990 Antiual Fletort Power Reactors NUth/

1YVO[F NUREG 1272 V05 f402 OFFICE FOR ANALYSIS AND EVALUATON OF DI & OF THE 2iST DOE /NRC NU-CLEAR AIR ULEANING CONFEREf4CE SES$10NS 9 16 Held in San N

G/CR 5796 ST AM GE ERA R OPERATING Diego, Cahtorrua Aupt 13 16.1990 EXPERIENCE. UPDATE FOR 1989 1990.

Nuclear Criticality NUREG 1450 POTENTIAL CRITORITY ACCIDENT AT THE GENERAL Operating Esperience Feedback Repod ELECTRIC NUCLEAR FUEL AND COMPONENT MANUFACTilRING W6@5 m NAM MRM HWN MM -

SOLENOtDOPERATED VALVE PROBLEMSCommercial Power Reac.

F ACILITY, M AY 29,1991.

tors Nuclear Material

~

NUREG/C45550 PASSIVE NONDESTRUCTIVE ASSAY Or NUCLEMI Operationai twent t,.TERiAlg NUREG/C44674 V13 PRECURSORS TO POTENTIAL SEVERE CORE

- DAMAGE ACCIDENTS 1990 A STATUS FIEPORT Mam Report And Ap<

Nuclear Med6 cine pendia A NUneG/CR 44*4 RADIATION SAFETY ISSUES RELA 1ED TO RADIO.

NUREG/C44674 Vid PRECURSORS TO POTENTIAL SEVERE CORE LADELED ANTIBODIES DAMAGE ACCIDENTS:1970 A STATUS REPORT Appvidae, B And Nuclear Plant Aging Research NUREQ 1144 R02. NUCLE AR PLANT AGING 9ESE ARCH (NPAR) PRO-Operational Safety.

GRAM PLAN Status And Accompishments NUREG/Ch-5742 V01: FEASIBILITY ASSESSMENT OF A RISK BASED APPROACH TO TECHNICAL SPECIFICATONS Enocutive Summary Nuclear Power Plant hiUREG/C45742 V02 FEASI0lLITY ASSESSMENT OF A HISK-DASED ROW M RMM MWM Main NW C 4911 CL IVt F U TO N LE R POWER PLANTS BY STATE REGULATORS Ownera Nuclear Regulatory Legislation NUREG4327 ROS: OWNERS CF NUCLEAR POWER PLANTS.

NUREG-0980 YO1 N01 NUCLEAR REGULATORY LEGISLATION.101st PR-EDO OY80 V02 N01: NUOLEAR REGULATORY LEGISLATON 101st NUREG/CR4816 RO1: F A EDir POWER REACTOR EMBRITTLEMENT NU Congress DAT A BASE, VERSION 1. Program Ds,senphon.

Nucles. Regulatory Research PRA NUREG-t266 V05: NRC SAFETY RESEARCH iN SUPPORT OF REGU.

NUREG/C44427: AUxlLl/RY FEEDWATER SYSTEM RISK BASED IN-LATON FY 1990 SPECTION GUIDE FOR THE BYRON AND DR,.OWOOO NUCLEAR POWER PLANTS.

Nuclear Repository NUREG/C45300 V01: INTEGRATED REllABillTY AND RISK ANALY.

NUREGICR-5711: ASSESSMENT OF UNCERTAINT;ES IN MEASURO SIS SYS TEM (1RRAS) VERSON 2.5 Reference ManuaFOR CRYST MENT OF PH IN HOstlLE ENVIRONMENTS CHARACTLRIS50 OF NUREG/CR 5467: Al5K-BASED INSPECTION GUIDE NUCLE AR REPOSITORIES.

HIVER UNIT 3 NUCLEAR POWER PLANT.

NUREG/CR 5520: PROCEDURES GUIDE FOR EXTRACTING AND Nuclear Safety Research LOADING PROBADluSTIC RISK ASSESSMENT DATA INTO MAR-D y

NUREGICP 0116. TRANSALTIONS OF THE NINETEENTH WATER RE.

USING IRRAS 2 5 ACTO 9 SAFETY INFORMATION MEETING NUREG/CR 5682, SPECIFIC TOPICS IN SEVERE ACCtDENT MANAGE-MENT Nuclear Weste Management NUREGIC45701: AUXILIARY FEEDWATER SYSTEM RISK BASED IN-F JREG 1423 V02: A COMPitATON OF REPORTS OF THE ADVISORY SPECTION GUIDE FOR THE SALEM NUCLEAR POWER PLANT.

COMMITTEE ON NUCLEAR WASTE.luly 1990 June 1991, NUREG/CR 5764 AUxlLIARY FEEDWA1ER SYSTEM RISK BASED If&

SPECTION GUIDE FOR THE GINNA NUCLEAR FWER PLANT Nuclear Weste Repository NUREG/CR 5440: CRITICAL ASSEStiMENT OF SEISMIC AND GEOME-PWR CHANICS LITERATURE MLATED TO A HIGH-LEVEL NUCLEAR NUREG 1301: OFFslTE DOSE CALCULATON WIANUAL GUIDANCE:

W ASTE UNDERGROUND REPOSITORY-STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR PRES.

Occupational Dose teduction SURi2ED WATER REACTORS Generte Letter 69 01. Supplement No.

s l

NUREG/CR 3469 V06 OCCUPATONAL DOSE REDUCTION AT NO, NUREG 1374-TECHNICAL FINDINGS RELATED TO GENERIC ISSUE CLEAR POWER PLANTS ANNOTATED DIBLIOGRAPHY OF SELECT.

ED READINGS IN RADIATION PROTECHON AND ALARA 79 An Evaluaton Of f%R Reactor vessel Thermal Stress Dunng Natu--

tal Convocton Cooldown.

Occupational taposure NUREG 1430 V1 DRF FC-STANDARD TECHNICAL SPECIFICATONS NUREG/CR 5139 DOSE REDUCTON TECHNOUES FOR HIG4 DOSE BADCOCK AND WILCOX PLANTS Spec 6catens Draft Report For WORKER GROUPS IN NUCLEAR POWER PLANTS.

NU EG 0 V2 DRF FC: STANDARD TECHNICAL SPECIFICATONS Occupational Radiation Esposure BABCOCK AND WtLCOX PLANTS Bates (Sectone 2 0 3.31. Draft NUREG-0713 V10: OCCUPATONAL RADIATION EXPOSURE AT COM-Repor1 For Comment MERCIAL NUCLEAR POWER REAC' ORS AND OTHER NUREG 1430 V3 DRF FC: STANDARD TECHNCat SPECIFICATIONS FACILITIES,1988 Twenty First Antva1 Report BADCOCK AND WILCOX PLANTS Bases (Sections 3 4 3 9).Drtft Report For Commert Office Of The inspector General NUREG 1431 V1 DRF FC STANUARD TECHNICAL SPECIFICATIONS NUREG-1415 V03 NO2: OFFICE OF THE INSPECTOR WESTINGHOUSE PLANTS SpecAca%nsDraft Repori For Comment GE NERAL Sern annual Report October 1990. March 1991.

NUREG-1431 V2 CRF FC: $1 ANDARD TECHNICAL SPECIFICATIONS NUREG 1415 V04 N01: CF FICE OF THE INSPECTOR WESTINGHOUSE PLAW3 Bases fSectons 2 0-3.3) Draft Report For GENERAL Semiantwal Repet April September 1991.

Comment

~

Subject Index 81 NUREG 1431 V3 DRF FC st ANDARD TECH SCAL SPECIF6CATON9 NUREC 0936 V10 Not NRC RE GUL AT OR Y AGE NDA C,uarterty WESTINGHOUSE PLANT $ Bues (Secteons 3 4-3 b) Dratt Repurt Ior Repur1.AprNano 1991.

Comment NUREG 0936 V10 N33 NRC REGULATORY AGE ND A Quarterly NUREG 1432 VI DM FC: STANDARD TECHNICAL SPECIFICATONS heport,JuN Septemt or 199E COVBUSTON I NTNt ERING PL ANTS Speciteatens Drait Report For Comment Physical Fitne64 NUAEG 1432 Vi DRF FC ST ANDARD TECHNICAL SPEC $1 CATIONS NUREG/CR46ep MEDICAL SCREENING RE82RENCE W NUAL FOR COM0UST.ON ENGINEERING PLANTS Babes (Sections 20 SECUR,iY FORCE PERSONNEL AT FUEL UYCLE FActCTIES POS-DR$ C NOaHD h'CHNICAL SPECIF6CATONS NV 143 V COMBUSTION ENGINEERING PLANib Dates (Sechons 34

• NUREG/CR $693 PHY SICAL FITNE SS TRAINuJO PEF E RENCE 3 81 D'a'i Rewt Fpr Cornmc4 NUREG/CR-406) AN INVESTIGATION OF CORE LIQUID Lf VEL DE.

MANUAL FOR SECuntTY FORCE PERbONNEL AT FUEL CYCLE FA-PRE SSION IN SuAll BRE AK LOSS OFC)OLANT ACCIDEN'IS CiUTIFS POSSESSING FORMULA OUANTITIES OF SPECIAL NU-NUREG'CR 5%$ AGING ASSESSMENT OF THE WESTINGHCUSE CLE AR MATERIALS.

PWR CONTROL ROD DRIVE SYSTE M NUREG/CR 500 PWR DRY CONTAINMFNT PARAMETRIC STUDIES.

F.iysical Security NUREG/CR4662: HYDROGEN COMBUSTION CONTROL.AND VALUE.

NUREG 1321: TESilNG STANC tRDS FOR PH/SICAL SECURITY SYS+

IMPACT ANALYSIS FOR PWR DRY CONTAINMENTS TEMS AT CATEGORY I FUEL CYCLE FACIUTIES NUREG/CR $663-RELAPS THERMAL HYDRAUUC ANALYSIS OF THE NUREG/CH $721: VIDEO SYSTEMS FOR ALARM ASSES $ MINT.

WNPt PRES $URi?ED WATER RE ACTOR NUREG/CR 5722 INTEROR INTRUSION DETECTION SYSTEMS NUREG/CR 5691: INSTRUMENTATON AVAILADIUTY f OR A PRES-NUREG/CR 5723 SECURITY SYSTEM SIGNAL SUPERVISON SURIZED WATER REACTOR WITH A LARGE DRY CONTAINMENT DURING SEVERE ACCIDE NTS Physical Security Plan NURE G/CA5707: APPLICATON OF CONTAINMENT AND RELEASE NUREG 1322. ACCEPTANCE CRITERIA FOR THE EVALVATON OF MANAGEMENT TO A PWR ICE CONDENSER PLANT.

CATEGORY l FUEL CYCLE FACittTY PHYS 6 CAL SECURifY PLANS NUREG/CR 5771: PROBABluTY AND CONSEOUU!CES OF M!SLOAD ING FUEL IN A PWR.

Pipe NUREG/CR 5781: SUMt1ARY OF A WOhkSHOP ON SEVERE ACCl-DENT MANAGEMENT FOR PWRS.

NUREG/CR4E65: THE HIGH LEvtl VIBRATON TEST PROGRAM Final p,porg NUREG/CR $796 STE AM GENERATOR OPERATING EXPERIENCE. UPDATE FOR 1989 1990 Pipe C*ecking Packa9e Supplier NUREGO975 V08: COf.;PILATION OF CONTRACT RESEARCH FOR NUREG/CR 57t7. PACKAGING $UPPUER INSPECTION GUIDE.

THE MATERIALS ENGINEERING BRANCH. DIVISION OF ENGINEERING Annual Report For FY 1990.

Parameter NUREq/CR 5522 A COMPtR' SON OF

' A MATION Piping AND SENSITIVITY ANALYSIS TECHNIQUEfPAr m ',r

'

• ACT ON NUREG/CP-0037; PROCEEDINGS OF THE SEMINAR ON ASSESS.

THE UNCERTAINTY IN GROUND WATEP Au4 PRE DIC.

MENT OF FRACTURE PREDICTION TECHNOLOGY: PIPING AND TIONS.

PREnSURE VESSELS NUREGiCR 4599 V01 NL SHORT CR ACKS IN PIPING AND PIPING Derticle Penetration WELDS Seehnnual Fleport. March-September 1990 NUREG/GR-0006 DRF FC DEPOSITION SOFN 7 t,ALCULATE NUREG/CR4501: ANALYSIS OF BELLOWS ExPANSON OlNTS IN PARTICLE PENETRATION THROUGH AERU M TRANSPORT THE SEQUOYAH CONTAINMENT.

LINES Draft Repor1 For Comment NUREG/CR472ii MULTIVARIABLE MODEUNG OF PRES $URE Possive Nondestructive Assay VLSSEL AND PIPING J.R DATA.

NUREG/CR 5757; VERIFICATON OF "lPING RESPONSC. CALCULA-NUREG/CR $550 PASSIVE NONDESTRUCTIVE ASSAY OF NUCLE AR MATERIALE TON OF SMACS CODE WITH DATA FROM SEISMIC TESTING OF AN IN PLANT PiPlNG SYSTEM.

Performance Aeoessment NUREG/CR4537: APPROACHES FOR THE VAUDATION OF MODELS Plant Aging USED FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL NUCLE.

NUREG-1377 A02: NRC RESEARCH PROGRAM ON PLANT AGING:

AR WASTE REPOSITORtES LISTING AND SUMMARIES OF REPORTS ISSUED THROUGH JUNE NUREG/CR 55'19 A SELF 1EACHING CURRICULUM FOR THE NRC/

18E OW LEVEL WASTE PERFORMANCE ASSESSMENT METHOD

• Post Emergency Response NUREG/CR 5618. USER'S MANUAL FOR THE NEFTRAN 11 COMPUT.

NUREG-144 t: LESSONS LEARNED FRC44 THE PCST. EMERGENCY ER CODE TABLETOP EXERCISE IN DATON HOUGE.LOUISlANAON AUGUST

!.UREG/CR4639 UNCERTAINTY EVALUATION METHODS FOR 28 AND SEPTEMBER 16.1990 WASTE PACKAGE PERFORMANCE ASSESSMENT, NUREG 1442:

POST EMERGENCY

RESPONSE

RESOURCES NUREG/CR 5701: A PERFORMANCE ASSESSMENT METHODOLOGY GUIDE Based On The Post-Emergency TABLETOP Emercise in Batori FOR HIGH-LEVEL RADOACTIVE WASTE DISPOSAL IN Rouge.Louissans.On August 28 And September 18.1990.

UNSATURATED. FRACTURED TUFF.

Pov%r Seactor performance History MW0713 V10: OCCUPATONAL RADIATION EXPOSURE AT COM-NUREG 1214 R07. HISTORICAL DATA

SUMMARY

OF THE SYSTEM AT-MERCIAL NUCLEAR POWER REACTORS AND OTHER IC ASSESSMENT OF UCENSEE PERFORMANCE NUREG 1214 R08 HISTOR! CAL DATA

SUMMARY

OF THE SYSTEMAT.

F ACIUTIES.1988 iwenty Frst Annual Report.

IC ASSESSMENT OF LICENSEE PEOFORMANCE.

NUREG/CR-4816 RO1: PR EDB. POWER REACTOR EMBRITTLEMENT DATA BASE.VERSON 1. Program Desenption-Performanca Rollability Practice And Procedure Digest NUREGICR 5538 V01: INFLUENCE OF ORGANIZATIOl L FACTORS ON PERFORMANCE REUABluTY. Overview And Detailed Methob NUREG-0388 005 R09 UNITED STATES NUCLEAR JiFGULATORY 5al Dwetopment COMMISSON STAFF PRACTICE AtiD PROCEEURE DIGEST. Commission. Appeal Brar6 And Licensing Board Personnel Perforfnence Decisions July 1972 September 1990.

NUREG/CR 5666. PROGRAMMATIC ROOT CAUSE ANALYSIS Op NUREG 0388 006: UNITED STATES NUCLEAR REGULATORY COM-MMNTENANCE PERSONNEL PERFORMANCE PROBLEMS.

MISSON STAFF PRACTICE AND PROCEDURE DIGEST. Commission.

A9 peal Board And Ucensing DecisionsJuly 1972 - Decerreer 1990.

Petitione For Rulemaking NUHEG-0936 V09 N04: NRC REGULATORY AGENDA Quarterly Pressure vessel Report,0ctober-December 1990 NUREG 0975 V08: COMPILATON OF CONTRACT RESEARCH FOR NURE G-0936 V10- NO1: HRC REGULATORY AGENDA Quarterty THE MATERIALS ENGINEERING BRANCH. DIVISION OF Report. January-Ma'ch 1991.

ENGINEERING.Ar*nual Report For FY 1990

82 Subject index NURf G/CP,0037 PRCCE t D!NGS OF THE SEM%AR ON AWM Probabilistic Rid Assessment MENT OF FRACTURE PRI DICTION 1[CHNOLC3Y PIPING AND NUREGICR e427. Auxillary FCLDWAT(R SYSTEM RISK BA%ED 14-PRE SSURE vt SSEt S.

SPECTION GUIDE f CR THE BYRON AND BRAIDWOOD NUCLEAR NURE GICR 4219 V07 N1 HE AVYSCCTION SittL TECHNOLOGY powtn etAratS PROGRAM Semarinuat Progms Report for Odoter IM9 - March NUREG/CR L377; REVIFW OF THE CHRONIC EKPOSURE PATHWAY Nb G/CR4219 V07N2 HEAVf-SECTION STEEL TECHNot OGY DLSTC SK A SEB CNT ODELS AYC i

F N RON NUMEG/CRM20 PROCf DURES GUIDE FOR EXTRACTING AND N E R 5( 6 1 1

TRANSMISSION THROUGH STIEL USING [NDF /D V.REylSLD LOADING FAOBABILISTIC RISK ASSESSMENT DATA (NTO MAR D tR I /R F L v DL ODEI Or PPFSSURE t4UR 4 551 MELCOR 1110: A COMPUTER d)DE FOR HUCLE AR VESSEL AND pipit 43 J.R DAT A REACTOR SEVERE ACCOtNT SOURCE TERV AND RISK AS$tSS.

MEN 7 ANALYSES Pres 6Jrtred Mett t)ntion NUREG/CR $701; AUKluARY FtEDWATER BfSTEM RISK BA$f D IN NUREGICRa910 PRESSURIZED MEtt (LJE CTION INTO WATER SPECTION OUIDF FOR THG SAllV NUCLEAR POWER PLANT-POOLS NUREG/CR 5764 AUxluARY FLEDWATLR SYSf LM RISK BASED 14 Pressurised thermal bhock NUREG/CH-5677= A UNtFitD INTERPRETATION OF ONE-FIF TH TO prot >abmetic Safety Analysis FULL SCALE THERMAL MulNG EXPFRiMENTS RELATED TO PRES

• NUREG/CR&% A REVIEW OF THE SOU1H 1ExAS PnOJECT PROB-SURIZED THERMAL SHGCir ANJSTIC SAFETY ANALYSIS FOR ACCIDENT FREQUf NCY ESil-Pressurised water bactor M ' ES AND CONTAINMENT BINNING.

NUREG 1301 OrFSf1E EK6E CALCULAtlON MANUAL GUIDANCE-Probals 4 NURbe tafety Astesament GTANDARD RADIOLOG CAL EFFLUENT CONTROLS FOR PRES' P W PRWDWGS OF THE CSNI WORKSHOP ON PSA SURIZED WATER REACTORS Genanc Letter 89 01. Supplement No' APPUCATONS AND LIMif ATONS-NUREG 1374 TECHNCAL F WOtNGS RELATED TO GENERIC ISSUE 7 An valu PW T Reactor VeM Thermal Stress Dunng Natu.

Prw uRE /CP 0037. PROCEEDINGS Ol: THE SEMINAR Of4 ASSEPS-NUREG 1430 V1 DR5 FC: 1TANDARD TECHNICAL SPECIFICATONS MENT OF FRACTURE PREDICTION TECNi40 LOGY; Po1NG AND

+

BADCOCK AND WILCOx PLANTS. 3pecttcetions Draft Aprort For PRESSURE VESSELS.

Comment NURf G/CP40114 V01: PROCEEDING 9 OF THF. [IGHTEENTH WATER NURLG-1430 V2 DRF FC: S' ANDARD 9ECHNICAL SPECIFICATIONS RE ACTOR BAFETY INFORMATON MEIthG BABCOCK AND PliLCOx PLANTS _.ses (Sections 20 3 3) Draft NUREG/CE0114 V02 PROCECDiNGS Or THE [IGH1EEN1H WATER Report Far Comment.

REACTOR SAFE 1Y $NFORMAtlON VEETING NUHlG 1430 V3 DRF FC ST ANDARD TF CHNCAL SPECIFICATIONS NUREG/CP-0114 V03. PROCE EDINGS OF THE CtGHTEENTH WAff R BABCOCK AND WILCOX DLANTS Baws (Sectons 3 4 3 9) Draft REACTOR SAFETY INFORMATON MEETING.

Report For Comment NUHEG 1431 V1 DRf f C. STANDARD TECHNCAL SPECIFICATIONS NUREO/CP-0115 PROCEE!ANOS OF THE CSNI WORKSHOP ON PSA APPUCATIONS AND LIMITATIONS WESTINGHOUSE PLANTS Sr Ekehons Draft hport Fat Comment NUREG 1431 V2 DPF FC; ST ANUARD TECHNICAL SPECIF:CATONS NUREG/CP-Olio V01 PROCEEDINGS OF THE 21ST DOEiNRC NU.

'e GHOUSE PLANTS Bases (Sections 2 0-3 3)Dran RepM Fo' CLEAR AIR CLEANING CONFERENCE Suws 1

• 8 Held in San D

Cahtortus, Aukist 1316i1990.

NUREG 1431 V3 DAF f C. STANDARD TECHNICAL SPECIFICATIONS NUREG'CP4116 V02 PROCLEDINGS OF THE 21ST DOE /NHC NO-WESTINGHOUSE PLANTS Bases (Sections 3 4-3 9) Draft Remrt Fo, CLEAR AIR CLEANING CONFERENCE SESSIONS 9 16 Hold it San Comment Diego, Calforma. August 1316,1990=

NUREG 1432 V1 DAF FC: STANDARD TECHNCAL SPECIFICA.lONS COMHUS TION ENGINEERING PLANTS Srecticatione Dratt Rem Program Performance For Com.nont NUREG/CR 6768 V01: FITNESS FOR DUTY IN THE NUCLEAR POWE R NUREG-1432 V2 DRF FC: STANDARD TECHNICAL SPECIFICATIONS INDUSTRY.Anr.ual Summary Of Program Pcriormance Reports,CY COM8USTON ENGINEERING PL ANTS Bases (Soctions 2.0 1990.

3 31 Dratt Repor1 For Comment NUREG/CR.$784. FITNESE FOR DUTY IN THE NUCLEAft POWER NUR$G 1432 V3 DNF FC STANDARD TECHNtCAL SPECIFICAftONS INDUSTRYA Review Of The First Year Of Program Performance And COMBUSTION ENGINEERING PLANTS Bases (Sections 3A An update Of The Technwallanues 3 Drat Report For Comment NUR O/GR-4063-AN INVESTOATON OF CORE UGUlO LEVEL DE-Pump PRESSON IN SMALL BREAK LOSS-OF COOLANT ACCOENTS ^

NU3EG/CR 5555, AGING ASSFSSMENT OF THE WLSTINGHOUSE NUREu/CR4706: POTENTIAL SAFETY.RELATED PUMP LOSS: AN AS-PWR COi, TROL ROD DRIVE SYSTEM SESSMTNT OF INDUSTRY DATA NRC Du eten 80 04.

n NOR(.3/CR 5630: PWR DRY CONTAINMENT PARAMETRIC STUDIES NUREG/CR-5062 HYDROGEN COMBUSilON. CONTROL,AND VALUE.

QuaMy Assurance IMPACT ANALYS!$ FOR PWR DRY CONTAINMFNTS NUREG 1?a3 RO1: OUAUTY ASSURANCE G10ANCE FOR A LOW-NUREG/CR 5663. RELAP5 THERMAL.HYDRAUUC ANALYSl3 OF THE LEVEL RADIOACTIVE WASTE DISPOSAL FAlauTY.

WNPt PRESSURIZED WATER AFACTOR-NUREG/CR4516: OUAUTY ASSURANCE PROCEDURES FOR THE NUREG/CR-5691: INSTRUMENT ATON AVAILABluTY FOR i c RES CONTAIN SEVERE REACTON ACCCENT COMPUTER CODE. -

SURIZED WATER REACTOR WITH A LARGE ORY CONTAINMENT NUREG/CR4538 V01: INFUiENCE OF ORGANIZATIONAL FACTORS DURING SEVERE ACCIDENTS ON PERFORMANCE REUABluTY. Overview And Detailed Methodo.

NUREG/CR-5707; APPUCATON OF CONTAINMENT AND RELEASE nogeat Development.

MANAGEMENT TO A PWR ICE CONDENSER PLANT.

NUREG/CR 5798. PILOT PROGRAM TO ASSESS PROPOSED BA$lC NUREG/CR 5771: PROBABlulY AND CONSEQUENCES OF JSLOAD-QUAuTy ASgURANCE RFOUIREMENTS IN THE MEDICAL U4E OF ING FUFL IN A PWR-NUREG/CR 5701: SUMMARi OF A WORKSHOP ON SEVERE ACCI.

BYPRODUCT MATERIAL' DENT MANAGEMENT FOR PWRS.

Quality Assurance Prog.t.m NURL G/CR-5706:

STEAM -

GENERATOR OPERATING EXPERIENCE, UPDATE FOR 1989 1990 NUREG-0383 VC2 Rte. DIRECTORY OF CERTIFICATES OF COMPLl-ANCE FOR RADCACTIVE MATERIALS PACKAGES Cortificates Of Primary Coolant System Comphance.

NUREGICA 5672 VOI: CHARACTER:STICS OF LOW tEVEL RADCAC-NUREG 0383 V03 R11: DIRECTORY OF CERTIFICATES OF COMPLi-TIVE WASTE Decontaminaten Waste Annual Report For Ftecal Year ANCE FOR RADOACTIVE MATERIALS PACKAGES Report Of NRO 1990.

Approved Quahty Assurance Programs For Radioattive Matenala Puk.

Probabinatic Risk Analysis NUREG-1150 V03' SEVERE ACC; DENT RISKS AN ASSESSMiAT FOR RELAPl/ MOD 3 FIVE U S NUCLEAR POWER PLANTS.APpendees D And E Finat NUREG/CR-5663 RE. AP5 THERMAL HYDRAUUC ANALYSIS OF 1HE Report WNP1 PRESSURIZED WATER REACTOR.

_------a--------~~~~

1 l

Subject index 83 RESAR bP/90 NUREG/CR M41 STUDY OF OPERATIONAL RISdASED CG4 4GU-NUREG 1413 SAFETY EVALUATON RlF')RT RELATLD 10 THE PAL.

RATON CONTROL UMtNARY DESIGN O& f ML STANDARC NUCLf AR STEAM SUPPLY NUREG/ CAM 92 GENE 84C RISK INSIGHTS FOR GENERAL f Lt C-REF ERENCE SYST[M,RESAR SP/90 DoOct No 60 601 (W est6ng.

TRC (4DILING WATER RE ACTORS house Electoc Cowestion, Inc)

NURtG/CR 570). APPUCATION OF CONTAINMENT AWO REL[r4E Radiat6on MANAGEMENT TO A PWR (CE CONDE NSER PLANT.

NUREG/CM771 PROBABILITY AND CONSEQU) ICES OF MISLOAD-UURLGtM1 CHEMCAL TOriCITY Or URANIUM HEKAFLUORIDE ING FUEL IN A PWR.

COMPARFD TO AWfI EF FECTS OF A ADtATON Fra' Report NUREG 1446 St ANDAr1DS FOR PROTECilON AGAINST RAD 6ATION.

Reactor Cavity N E 4 RAD 1

[

FEYt$3 EL E O HA NURE G /CA-3916. PRESSURitED MELT EJECTON IN10 WATER LABELE D ANTIBODIE S.

POOL 8 Red!stler Dose Reactor Cornponent NU84EG/GR 5BD8 CALCUL ATION Gr ABSORBED DOSES TO WATER NUREG/( - M11. ISSUES AND APPROACHFS FOR USING COUIP.

POOL D IN SEVERE ACCIDENT 5EOUENCES MENT RELIABlUTY ALERT LEVELS Fiedletion Fmerttelement NUREGIUM746 RADIATION (MBRITTLEMENT OF THE Nr.UTRON.

Reactor Containment NUREG/CM7tl. RETERENCE MANUAL FOR THE CONT AIN 11 SH) ELD T ANA F ROM THE SH!PPINGPORT RE ACTOR CODE FOR CONTAINMENT bEVERE ACCIDENT ANALYSIS Radietton Protection NURFG/CR 34ti9 V06 OCCUPATIONAL DOSE REDUCTION AT NU-Reactor Control System i

CLEAR POWER PLANTS ANNOTATEU BiBUOGRAPHY OF SELECT.

NUREG/CR 4659 V04 SEISuc FRAGIUTY OF NUCLEAR POWER ED RE ADINGS IN RADi ATON DROTECTION AND ALARA.

PLANT COMPONENTS (PHASE 11) A fragility hant,ftcok On Eghteen Components Qadloactive Effluent NUREG'CfM64L STUDY Or OPERATONAL RISK-BASED CONFIGV, NUREG/CR4773 SELECTON OF MODELS TO CALCULATE THE LLW RATON CONTROL SOURCE TERM Reactor Coolant Pump Radioactive Material NUREG 1401 DAFT FC= RtGULATORY ANALYSIS FOR GENERIC NURf G 0383 VU2 R14 DIREC10RY OF CERTIFICATES OF COMPLt-ISSUE 23 REACTOR COOLANT PUMP SEAL FJulVRE Draft Repod ANCE FOR RADCACTIVE MATERIALS PACKAGES Certrficates Of f or Comrnent

/Yfhp07 VOp RADIOACTIVE MATERIALS RELEASED FROM N

NUCL E AR POWER PL ANTS Annual Report 1988 M REAN MAM N M WM

• Lad 6oactive West, Reactor Core NUREG/CFM714 HYDROGEOLOGIC PERNAMANCE ASSESSMFNT NUREG/CR-5526 ANAt VSIS OF RISK REDUCTION MEASURES AP.

ANALYSIS OF THE LOW LEVEL RADCAC11VE WASTE DISPOSAL PUED TO SHARED ESSLNTIAL SERVICE WATER SYSTEMS AT FACluTY NEAR SHEFFIELD. ILUNOIS.

MULTI UdlT SITE 5L Radioactive Weste Disposal Reactor Maintenance NUREG/CR-3444 V0P YHE IMPACT OF LWR DECONT AMINATlONS NUREO/CR4612. DEGRADATON MODELING WITH APPLICATION TO ON SOLIDIFICATON. WASTE DISPOSAL AND ASSOCIATED OCCO-AGING AND MAINTENANCE EFF ECTIVENESS EVALUATONS.

PATONAL EXPOSURE Ettects Of Compositen on The Strength.Seethng. And Water. immersion Pr".twrtes of Cementdohd..

Reactor Pressure Vessel feed ion Enchange Resen Wautes NUREG 1426 V00 COMPILATION OF FIEDORTS FROM RESEARCH Rodsolabe4d Anubody SUPPORTED BY THE MATERIALS ENGINEERING BRANCH.DIVISON OF ENGINEERtNG 1905 1990.

NUREG/CR 4444 RADtAllON SAFETY ISGUES RELATED TO RADIO ~

LABELED ANTIBOD ES-NUREGICR 5767: THE BEHAVIOR OF SHALLOW FLAWS IN F4EACTOR PRESSURE VESSELS Radionuclide

/

F r

E LE S RA N E / R-525. HYDROGEN tWDILUENT DETONATION STUDY CUDES AND CHELATING AGENTS FROM CEMENT SOUDIFIED DE, FOR NUCL EAR REACTOR SAFETY ANALYSES.

CONTAMWATON ON EXCHANGE RESNS COLL.ECTED FROM OP, hUPEG/CR 5538 VOL INFLUENCE OF ORGANIZATONAL FACTORS ERATING NUCLEAR POWE R 10 ATIONS.

ON PERf ORMANCE REUABILITY.Overvew And Evaried Methucky logical Devekipment.

Redtonucl6de Distribut6on NUREG/CR-5780;

SUMMARY

OF A WORKSHOP ON SEVERE ACCI.

NUREGICR4670 RADIONUCUDE DISTRIBUTONS AND MiGRATON DENT MANAGEMENT FOR BWRS, T

MECHANISMS AT SHALLOW LAND DURIAL SITES Final Report Of NUREGICR 5780

SUMMARY

OF A WORKSHOP ON SEVERE AOCl-PNL Research investigatons On The Distnbubon, Migration, And Con.

DENT MANAGEMENT FOR PWAS.

tainment Of Radionuchdes At Money Flats, Kentucky setor 'Lafety Research Rad 6onucl de Transport NUREt /CP 01te TRANSACTONS OF THE NINETEENTH WATER RC-NUREG/CR 5713 A REVIEW OF ENVIRONMENTAL CONDITIONS AND ACTOR SAFETY INFORMATON MEETING.

PERFORMANCE OF THE COMVERCIAL LOW-LEVEL RADIOACTIVE W ASTE DISPOSAL F ACluTY NE AR SHE FFIE L OAUNOIS Rest;or Vessel NUREG/CR 5714 HYDROGEOLOGIC PERFORMANCE ASSESSMENT ANALYSIS OF THE LOW LFVEL RADIOACTIVE WWE DISPOSAL NUREG 1374. TECHNICAL FINDINGS RELATED TO GENERIC ISSUE F ACILITY NEAR SHEFFIELD tt.UNors 79 An Evaluahon Of PWR Reactor Vessel Thermal Stress Dur6ng Natw NUREG/CR 5717; HYDROGE6 LOGIC PERFORMANCE ASSESSMENT N EG 5 60 RT ON ANNEAUNG OF THE NOVOVORON-ANALYSIS OF THE COMMERCIAL LOW-LEVEL RADCACTIVE WASTE DISPOSAL FACluTY NE AR WEST VALLEY,NEW YORK.

3 REAGOR WSSR W THE USSR HUREG/CR 5794 grout"> WATER FLOW AND TRANSPORT MODEL.

ING FTE R ICENSED WASTE DISPOSAL FACIUTY. WEST Regu o Agenda Report. October-December 1990.

Reector Accident NUREG 0936 V10 Not NRC REGULATORY AGENDA.Ouadeny Nt: REG /CP.0114 V01 PROCEEDINGS OF THE EIGHTEENTH WATEP Report. January-Ma'th 1991 REACTOR SAFETY INFORMATON MEETING NUREG-0936 V10 140 2.

NRC REGULATORY AGENDA Quarterty NUREG/CR 5634. OENTIFICATON AND ASSESSMENT OF CONTAIN--

ReportApril-June 1991.

MENT AND RELEASE MANAGEMENT STRATEC'ES FOR A BWR NURE G-0936 V10 NO3 NRC REGULATORY AGE NDA Ovenerty M AR A 1 CONT AINME NT, ReportJuly September 1991,

84 Subject index Regulatory AnalyCe Retin NUREGN40 DRFT FC REGULA10RV ANALYSIS Of PROPOSE D NUREG/CR4444 V0B THE IMPACT OF LWR DECONT AMINATIONS AMINDO ENTS TO REGULATIONS CONCERNING THE ENVlRON ON tiOLIDirlCATION WASTE D$POOA AND ASSOCIATLD OCCU-MEN 1 AL REVIEW FOR RENEWAL OF NUCLEAR POWER PLANT PATION AL E APOSURC Eftects Of con ws*on On The OPERATING LICE NSt B Dralt Repon For Comment NUDEG 1445 HEGULATORY ANALYSIS FOR THE RESOtV* TON OF Strength.Sweihng Artt Water-immerson Properties of Cement sold GENERIO SAF ETY ISSUE-29 BOLTING DEGRADATION OR FAlLURE t.ed ion E4 hangs Resen Wasten IN NUCL EAR POWER PLANT $

Restart NUREGiCR M95 FORECAST REGULATORY EFI ECTS COST ANALY*

NUREG 1D2 V03 502 BAFETY EVAtVATiON REPORT ON TENNES-S'S SOFTWARE MANUAL Verwon 3 0 ME VALLEY AUTHORITY. DROWtd FERRY NUCLFAR PE RFORM-Regulatory And Techn6 cal Report NUREG4304 V15 N04 RE GULA1DR y AND TECHNtCAL PEPORTS pg NY CH EPOt4TS NNM W A NMWW M WW WW MD N

G 304 01 REG AT (ABSTRACT INDEX JOURNAL) Compelston For First Quarter ni,k Anotyei.

19a t, January Me ch r

NUAEG-0304 V16 NO2, REGULATORf AND TECHNICAL ftEPORTS tiUREG/CR 546P RISK-BASED INSPECTION OUtDE FOR CRYST AL RIVER UNIT 3 NUCLEAR POWER PLANT.

(ABSTRACT INDEX JOURNAL) Compdaten f or Second Oue'ter 1991 At4Jun*

NUREG 0304 V16 t403 REGULATORY AND TECHNICAL REPOR19 Risk Analytte System NUREG/CR L300 V01: INTEGRATED REttABILtTY AND RISK ANALY-(ADSTRACT INDEA JOURNAL) Compilat*on For Thrd Quarte' 1991. July Septemter SIS SYSTEM CARAS) VERSION 2 5 RMetence Manual Regulatory Conalderation RM Reduction NUREG-1439 ST AFF TECHNICAL POSITION ON REGULATORY CON.

NUREG/CR4$26 ANAt YSIS OF RISK REDUCTION MEASURES AP.

MDERATIONS IN THE DESIGN AND CONSTmMTION OF THE EX, PLIED TO SHARED ESSENTIAL SERVICE WATER SYSTEMS AT PLORATORY SHAFT F ACILITY.

MULTIUNIT SITES Relay Rock Mechavde NUREG/CR 4%6 CLOSEOUT Of tE BULLETIN 84-02 i A1 LURES OF NUREG/CR $440 CRITICAL ASSESSMENT 01 SDSMIC AND GEOME.

GENEPAL ELECTRIC TYPE HFA RELAYS IN USE IN CLASS 1E CHANICS LITERATURE RELATED TO A HIGH LEVEt, NVOLEAR SAFETY SYSTE MS WASTE UNDERGROUND REPOSITORY.

Relay Test Program Root Cause NUREQ/CR 4807 RELAY TEST PROGRAM Seres i Vatn 1 Tees NUREGICR $M4 PROGRAMMATIC ROOT CAUSE ANALYSIS OF MAINTENANCE PERSONNEL PERFORMANCE PROBLEMS Rollabitsty NUREG/CR 5742 Vol; FEASIBILITY ASSESSMENT OF A RISK-BASED Rules APPROACH TO TECHNICAL 8PECIFICATIONS Executsve Sirnmar NUREG4936 V09 t404 NRC RE GULATORY AGE NDA Quartetty NURf G/CH 6742 V02 FEASIBILf rY ASSESSMENT OF A RISK <DAyED RePortOctoterbecember 19M o

APPROACH TO TECHNICAL SPECIFICATIONS Main Haport NUREG 0936 V10 Noi; NRC REGULATORY AGENDA.Quartorty HePetitive Fellure ReportJanuarv-March 1991.

NUREG 0936 V10 NO2 NRC REGULA10RY AGENDA Ouarterly NUREG/CR 615 A SYSTEMATIC APPROACH TO REPETITIVE FAIL-ReportAor& June 1991.

URES NURE40936 V10 NO3 NRC REGULATORY AGENDA Oua terty Report To Congress Report, July Septemter 1991.

NUREG 0090 V13 NO3 REPORT TO CONGRESS ON ABNORMAL Rules Of Practice OCCURRENCES July September 1990.

NUREG 0386 005 R39. UNITED STATES NUCLEAR REGULATORY NURE0 0090 V13 N04, REPORT TO CONGRESS ON ABNORMAL COMMISSION STAFF PRACTICE AND PROCEDURE

^"

NU G6 1

T NGRESS ON ABNORMAL OCClRRENC Decisions July 1972. September 1990 NUREG 90 VI 1 b T

CONGRESS ON ABNORMAL 6 N WLD STM WAEAR MWM N OCCURRENCES MISSION STAFF PRACTICE ANC PROCEDURE DIGEST.Commason.

NUREG 0000 V14'Apnt-June 1991 Noy pr. PORT TO CONGRESS ON ABNORMAL Apoeal Board And Ocensmg Docm July M72 December N OCCURRENCES July September 1991.

ggp Repoellory Site NUREG 1214 R08 HISTORICAL DAT A

SUMMARY

OF THE SYSTEMAT.

NUREG/CR 5495: CONCEPTUAll2ATION OF A HYPOTHETICAL HIGH, IC ASSESSMENT OF LICENSEE PERFORMANCE.

LEVEL NUCLt'AR WASTE REPOSITORY SIT E IN UNSATURATED.FRACTJRED TUFF' UA t4URE I 5757; VERIFICATON OF PIPING RESPONSE CALCULA.

R4eearch Program TION OF SMACS CODE W TH DATA FROM MISMIC TESilN3 OF NUREG-1377 R02: NRC RESEARCH PROGRAM ON PLANT A3tNG AN IN PLANT PIPING SYSTEM.

LISTING AND SUMMARIES OF REPORTS ISSUED THROUGH JUNE

. SP ARC 90 Computer Code NUREG/CR 5765 SPARC 90 A CODE FOR CALCULATING FisStON Research Report PRODUCT CAPTURE IN SUPPRESSION POOLS NUREG 1426 V01: COMPILATION OF REPORTS FROM RESEARCH SUPPORTED DV THE M ATE RIALS ENGINEERING SOUIRT Computer Code HRANCH. DIVISION OF ENGINEERING. 1965 1990 NUREG/CR-5128 EVALUATION AND REFINEMENT OF LEAK-RATE ESTIMATION MODELS

- Reeldual Heat Removal NUREG/CR 5706. POTENTIAL SAFETY-RELATED PUMP LOSL AN AS.

ST 1 Test SESSMENT OF INDUSTRY DAT ANRC Buitehn ge M NUREG/CR 5312: A THERMODYNAMIC MODEL OF FUEL DISRUP.

Resadual Lif etime NUGEG-1144 R02: NUCLEAR PLANT AGING RESEARCH (NPAR) PRO.

Safeguardo GRAM PLAN Status And Accomphshments NUnEG/CR 5723. SECURITY SYSTEM SIGNAL SUPERVISION.

' ReOdual Stress Safeguards Summary Event List NUREG/CR 5697 USE OF THICKNFSS REDUCTION TO ESitMAT8; NUREG 0525 Rit: SAFEGUARDS

SUMMARY

EVENT LIST (SSEL) Pre-VALUES OF K NRC Through December 31.1990.

- ~~

.=

D

Subject Index 85 Sately Evaluaten Report Setemic Monitoring t4URI G 4676 $34 SAFETY EVALVATON REPORT HELATLD TO THL NUREG/CR $628 8'ENNM LVANIA Sil5MIC MON!10 RING NETWORK OPERATON OF DIABLO CANYON NUCLEAR POWf R PLANT. UNITS AND RELA 1ED TECTONIC STUD 1ES F mal Report 1 AND 2 Drcet Nos 60 275 And 50 323(Pavtc Gas And Elect'c Cam Selem6e Network NUHEb>any)7 SOB SAf ETY EVALUATON REPORT RELATED TO THE e4 NUREG/CR 6779 V01 NEW YORK /NEW JEh5EY REGONAL SEISMIC OPERATON OF WATTS BAR NUCLEAR PLANT.VNITS 1 AND f4ETWOHK Arvwal Report For #sva 19n9 + Mwch 1990 2 Eu.ket Nos f.0-390 And 60-391 (Tennessee Va'ie Authorityl NUREG4647 607. SAIETY (VALVATON HE PORI bELAllD TO THE Solamic Prograrn OPERATON OF WATTS BAR f4UCLEAR PLANT. UNITS 1 AND NUREG.0676 S34 RAFETY EVALUATON REPORi k ELATf D TO THE 2 Docket Not W390 Ard 60091 (Tenrassee Vuhry Authomd OPERATION OF DIABLO CANYON NUCLE AR POWL R PLANT. UNITS NUREG 1232 V03 S02 SAf ETY EVALUATON REPORI ON 'TENNES-1 AND 2 Docket Noe 60 276 And 60 323(Pacste Gas Argi Electne

$EE VALLEY AUTHORfTY. BROWNS FERRY NUCLEAR PERFORM ANCE PL AN Browns Ferry Urut 2 Resta 1 Company)

NURIG 1369 FREAPPLICATION BAl ETY EVALUATION REPORT FOR THE SODIUM ADVANCED FAST RE ACTOR (SAFR) LtOUO MET AL g,g,g, 9,,ging NUREG/CR 5000 STATIC AND SIMULATED SEISMC TESTING OF NIL 1 2-SAFETY EVALUATON REPORT RELATED TO THE NyG/dI QT IN

^"

FUlt TERM OPERATING LICENSE FOR OYSTER CREEK NUCLEAR 67 O

I S

E CALCULA-GENERATING ST ATION Dodet No 60 219 (Geretal Puble Utilitet TlOH OF SMACS CODE WITH DAT A FROM SEISMO TESTING OF AN IN PLAN 1 PIPING SYSTEM NUIN14 3T FYTY EVALUAtlON REPORT RELATE D TO THE PRE-LIMINARY DESIGN OF THE STANDARD NUCLEAR STEAM SUPPLY REFERENCE SYSTEM,RESAR SP/90 Dodet No 600 4 Noting.

E CH $74rt 1ECTONIC DEFORMATON REVEALED IN BALDCY.

PRESS TREES At REELFOOT LAKE. TENNESSEE.

NU E 4Y3 LNTON REPORT RELATED TO THE Y

FULL. TERM OPERATING LICENSE FOR SAN ONOFRE NUCLEAR 0

GENERATING $f ATION. UNIT.1. Docket f40. b0406 (Southern Califor-CR 3145 V09 GEOPHYSICAL INVESilGATIONS OF THE nas Edrson Company And San thego Gas And Electne Company)

WESTERN OHIOINDIANA REGION 1.ntwal Report 0ctoter 1989 -

Saptemlet 1990 Estety Evaluation Revi3w NUREG INS V02 SAFETY EVALUATION REVIEW OF THE PROTO.

S*"*'tivity TYPE LICENSE APPUCATION SAFETY ANALY$lS NUFIEGICR4522 A COMPARISON OF PARAMETER ES11HATION REPORT B6bwg+ound VsJt AND SENSITlvtTY ANALYSIS TECHNIQUES AND THEIR IMPACT ON TIT UNCERTAINTY IN GROUND WATEft FLOW MODEL PREDIC-Batety issue llONh NUREG41436 Voi: STATUS OF SAFETY ISSUES $f LICENSED POWER PLANTS TMi Action fV Reaarements Seneltlastion NUREG 1435 V02. STATUS OF SAIETY ISSUES AT LICENSED NUREGrQRo002. CONTINUOUS COOLING THERMAL CYCLE EF.

POWER PLANTS UrvosoNed Safety lasues.

FECTS ON SENSITIZATON IN STAINLESS STEEL NUREC/GR 0003 EFFECT OF PROR DEFOHMATON ON SEN$lil2A-

) EG 1 VOS NRG SAFETY RESEARCH IN SUPPORT OF REGO-LATION FY 1990 q

Scaling Methodology IV' LI'8 NUHLG/CR 6803 DRF FC AN INTEGRATED STRUCTURE AND SCAL.

NUREGICR4269. MODELS OF TRANSPORT PROCESSES IN CON-ING METHOh0 LOGY FOR SEVERE ACCOENT TECHNICAL ISSUE CRETE-RESOLUTION Draft Rewr1 For Comment h@ W Wm Seal Fallure NUHEEe1421: REGULATORY ANALYS!S FOR THE RESOLUTON OF NUREG 1401 DRFT FO REGULATORY ANALYSIS FOR GENERIC GENERIC ISSUE 130 ESSENTIAL SERVICE WATER SYSTEM F AIL.

ISSUE 23 REACTOR COOT. ANT PUMP SEAL FAILURE Deatt Report URES AT MULTI UNIT SITES For Comanent NUREG/CR $$26' ANALYSIS OF RISK REDUCilON MEASURES AP.

NUREQ/CR 6167. COST / BENEFIT ANALYSIS FOR GENERIC ISSUE PLIED TO SHARED ESSENTIAL SERVICE WATER SYSTEMS AT 23 REACTOR COOLANT PWP SEAL FAILURE-MUL11-UNIT SITES Securtly Personnel Severe Accident NUREG/CA.56B9 MEDICAL SCREENING REFERENCE MANUAL FOR NUREG 1407; PROCEDURAL AND SUDMITTAL GUCANCE FOR INDI-SECURITY FORCE PERSONNEL AT FUEL CYCLE FACILITIES POS-VIOUAL PLANT EXAMLNAYlON OF EXTERNAL EVENTS (IPEEE) FOR SESSING FORMULA QUANTITIES OF SPECIAL NUCLEAR MATERi-SEVERE ACCOENT VULNERABILITIES Fmal Report ALM NUREG/CR 4551 V2R1P2: EVALUATION OF SEVERE ACCIDENT NUREG/CR 5600 phi SICAL FITNESS TRA!NING REFERENCE RISKS: OUANTIFICATON OF MAJOR INPUT PARAMETERS Emports' MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE FA-Evtornunation Of Containment Loads And Molten Core Containment CILITIES POSSESSING FORMULA QUANTITTS OF SPECIAL NU-Interaction issues.

CLEAR MATERIALS.

NUREG/CR-5331 MELCOR ANALYSES FOR ACCOENT PROGRES.

SON ISSUE S.

Security System NUREG/CR 6345: FISSION PRODUCT RELEASE AND FUEL BEHAV-NUREG/GR 5723 SECURITY SYSTEM SIGNAL SUPCRVl$ON' OR OF 1RRADIATED LtGHT WATER RE ACTOR FUEL UNDER Solam6c SEVEFE ACJ1 DENT CONDITIONS The ACRA ST 1 Entwiment NUREG/CR 4659 V04 SEISMIC FRAGILITY OF NUCLEAR POWER NUMEG/CR.5423. THE PROBABILITY OF LINER FAILURE IN A MARK 4

^

PLANT COMPONENTS (PHASE II) A Fraylity Handbook On Eighteen N

G AN ASSESSui OF BWR MARK lil CONTAIN.

NU 440. CRITICAL ASSESSMENT OF $EISMIC AND GEOME, MENT CHALLENGES, FAILURE MODES. AND PUTENTIAL IMPROVE-AS E ND GR NOR POS10RY' NAGC 8& A W W M M N AR REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS-Selene Effect MENT ANALYSES NUREG/CR-5585 THE HIGH LEVEL VIBR ATON TEST PROGRAM Final NUREG/CR 5561: ANALYSIS OF BELLOWS EXPANSON JOINTS IN Report THE SEOtOYAH CONT A!NMENT, NUREG/CR-5565 THE RESPONSE OF AWR MARK tl CONTAINMENTS Beltmic Fregility TO ST ATION BLACKOUT SEVERE ACCIDENT SEQUENCES NUREQ/CR-4659 V04. SEISMIC FRAGluTY Or NUCLLAR POER NUREG/CR 5571: THE RESPONSE OF BWR MARK I!! CONTAIN.

PLANT COMPONENTS (PHASE I!).A Frayliff Handbook On Eighteen MENTS TO SHORT TERM STATION BLACKOlJT SEVERE ACCOENT Componens SEQUENCES.

- ~. _

66 Subject inden NURE G/CR M23 TMH MARK 11 f rVESSI.L ConlUM IN1[ u AritnN Source Term ANALYbES NUHEG!CR 8>f f3 SEllC10N OF MDDE LS TO CALCULAIE THE LLW NUhlG/CR W% SUOM[RGE NCE AND HIGH Tl VPiRATURE Sif AM SOUPCE TEhM 11 STIN7 OF CL ASS 1E E t t CTHCAL CABLE S NUhlO/UR tNJ2 SPECIFIG TOPICS IN bEvt RE ACCIDENT MANAGE-Special Nuctent Metenal MINT NUREG/CR t734 DECOMMINDATONS TO THE NHC ON ACCEPT A NUhf G/04 fM1- (NSTRUVENT AllON AVAILABiLi1Y FOR A PHE S RLE $1 ANDARD FOHMAT AND CONTENT FOR THE F UNDAMf 4 SUHillO W ATL81 RE AC10R Wif H A LARGE DRV CONI AINMLNT T AL NUCLE AR MA1E HtAL CONih0L if 9 MCI PLAN HEOuiHf D FOR N E /

1 F

F t MANUAL FOH THE CONTAIN 11 Cf00 FOR CONT AINMENT St VEI4E ACCIDENT ANAL VS!S Spent Fuel NUHE G/CH 5132 D84 F FC IODlNF CHE MICAL FOAMS IN LWH NUDEG/CH 5343 M ADONUCllDE CHARACTERilATION Or RE AC-

[A Y

A b

ON SEVERE ACCI.

104 DECOMMISSONING W ASTE AND SPENT FUFL ASSlMBLY N l CR t)

DINT MANAGEMENT FOR BW43 HARDWAhl Peugens Hoport NUHE G/CH 6781-

SUMMARY

OF A WOhKSHOP ON SEVERE ACCI.

DE NT M ANAGE MF NT F ON PWR9 bP'"!

P**"I NUhEG'CH f.SJB CALCULAtlON OF ADSORBED DOSES TO WATER NUHE G 0725 R97. PUBLIC INrchVATION CIDCULAR F OR SHIP-POOL S IN SEVE RE ACCIDE NT Stout NCE$

MENTS OF thHADIATED HE ACTOR F UEL NURLQ/CH 5b09 DNF F C AN INILGHA1LD $14UCTUhl AND SM-ING METHODOLOGY FOR SEVEHE ACCIDENT TECHNICAL ISSUE Sl*I"I'88 Bl**l HE SOL UTON D'att Report F os Comment NURE G/04 4513 E SflM AT ON OF FRACTUHE TOUGHNE SS OF CAST ST AINLL SS STEELS DUhlNG THLRMAL AGING IN LWH SYS.

Severe Accident Risk 1 E MS NUNEO-1150 V03 SEVERE ACCOENT RISKS AN ASSE SSME NT FON NURLG/CR 4144 Vos N1 LONG TERM EMBR' sLEMLNT OF CAST FIVL U b NUCLEAR POWER PLANTS ApPordes D And E Final DUPLEX ST AINLE SS STEELS IN LWR SYSTE MS Semiannual Refwyt Dyrt Octoter 1989. March 1990 NUR.G/CR-4744 V05 NA LONG 1[hM [MBR!TTL E MENT OF CAST Severe Reactot Accident DUPL E X S1 AINLE SS STEELS IN LWR SYSif MS Semannual NUAEG/CH 5518 qualify ASSURANCE PROCfDUHES FOR THE Fi et.A vil September 1990 G/Gfl 0002. CONTINUOUS COOLING THERMAL CYCLE EF.

CONT AIN SEVE RE PE AC10R ACCIDE NT COMPUIC R CODE.

nut bhahow haw Ff C1S ON SENSITilATION IN B1 AINLESS STEEL NUHf G/CH4767 THE $EHAVIOR OF SHAl. LOW FLAWS IN RE ACTOR NUREG/GR 0003 EFFECT OF PRIOR DEFORMAllON ON SENSlfilA-PRESSunt VE SSE LS TION DEVELOPMENT IN ST AINLESS STELL DunlNG CONTitJUOUS COOttNG Shallow Land Bur 91 NURI G/CR-46m. P ADONUCLIDE DISTRIDUTONS AND MIGRATION an MLCHANISMd AT taAltOW LAND DURIAl, $11ES Final Heport O' UR 002 STANDARD FOhMAT AND CON?ENT OF A lb PNL Resesq h investigates On The Distriloton. Myrton. And Con-CENSE APPUCATION FOR A LOW LEVEL RADIOACTIVE WASTE ta,nment Of f edenucl. des At Masey F lats. kentucky DISPOSAL F ACIL!TY Shen Wall Structure Standard Review Plan NURE G/CR4660 ST ATIC AND $!MULAi[D SEISMIC 1ESTING OF NUHm m R02. ST ANDARD REVIEW PLAN FOR THE RE VlE W OF A THE TRG 7 THROUGH 16 SHE AR WALL STRUCTURES LICENSE APPLICATION FOR A L.OW LEVEL HAD:OACTIVE WASTE DISPOSAL FACILITY ShelfToughness NUREG-1429 DAFT FC ENVl40NMENT AL ST ANDARD REVIEW PLAN NUNEGICR 5577. E XT ENSON AND E x1R APOLATION OF 1R FOP. THE REVIEW OF LICENSE RENEWAL APPUCATIONS FOR NU-CURVES AND THEIR APPLICATION TO THE LOW UPPER SHELF CLEAR POWER PLANTS Draft Report f or Comment TOUGHNESS 3 SUE, Standard Technical Specificatene Sodlum Advanced Fast Fleactor NUREG 1430 VI DRF FC STANDARD TECHNICAL SPECIFICATIONS NUHEG 149 PRF APPUCATION SAFETY EVALUATON HEPCRT FOh DADCOCK AND WiLCOx PLANTS Spockahons Draft Report For THE SODIUM ADVANCED F AST RE ACTOR (SAFR) UOuiD MET AL Cornment.

REACTOR NoRf G-1430 V2 DHF FC-ST ANDARD TECHNICAL SPECIF CATONS Software Manuat 6ABCOCK AND WILCOx PLANTS Dates fSectons 2 0 - 3 3) Draft NUREG/CR 5595 FORECAST REGdLATORY EFFECTS COST ANAlb NUHbrt For Comnent h

i430 V3 DRF FC: STANDARD TECHNICAL SPECIFICATION 3 SIS !OFTWAHE MANUAL Vowon 3 0 DABCOCK AND WitCOX PLANTS Eisses (Sectent 3 4 3 9)P att Soll Cover System b fC: STANDARD TECHNICAL SPECIFICATIONS NU 1 1 NUHEG/CR-5432 VOt. RECOMMENDATONS TO THE NRC FOR SO!L COVER SYSTEMS OVER URANIUM MILE TA' LINGS AND LOW-MSTINGHOUSE PLANTS Speckatons Draft Report For Comment NUHEG-1431 V2 DFiF FC: STANDARD 1ECHNICAL SPECirlCAtlONS LEVEL RADCACTivE WASTES. Identification And Ranung Of Sods For Disposal FacMy Coves WESTINGHOUSE PLAN 1S Danes (Sectone 2 0 3 3) Dratt Report f or NUREGsH 5432 V02 RECOMMENDATONS TO THE NRC FOR SOlL en NUREG 1 V3 DRF FC ST ANDARD TECHNICAL SPECIFICATONS COVER SYSTEMS OVER URANIUM MILL T AILINGS AND LOW

• thel RADi0ACitVE WASTES. 'aboratory And Field Tests For Sod WESTINGHOUSE PLANTS Bones (Sectons 3 4 3 9) Draft Fleport For Come

[hCH 5432 V03 HECOMMENDATIONS TO THE NRC FOR SOlt

1. 32 b#

NL COVER SYSTEMS OVER URANIUM MILL TAILINGS AND LOW-O LEVEL RADCACTIVE WASTES Constructon MethyJs And Gedance g[g 'E D

1 2 2 DAF FC. STANDARD TECHNICAL SPECIFICATIONS F or Seahng Penettations in Sod Covers COMBUSTON E NGINE E RING PLANTS Bases (Sectens 2.0 Solenoto-Opersted Vatve 3 3) Orat a sport For Comment NUREG-1775 V06 OPERATING EXPERIENCE FEEDDACK REPORT.

NUHEG-1432 V3 DRF FC STANDAit0 TECHNICAL SPECIFICATONS SOLENOID-OPERATED VALVE PROBLEMS Commercial Power Reac-COMSUSTION ENGINEERING PLANTS Bases (Sectons 34 8

tors 3 97 Draft Report For Comment NUREG 1433 V1 DRF FC STANDARD TECHNICAL SPEC 1FICATONS Solid Waste Disposal GENERAL ELECTRIC UNITS, BWR/4 SMct'ons Draft Report For NUREG/CR 2907 V09 R ADOACTfVE MATERIALS RELEASED FROM Comment NUCL E AR POWE R PLANTS Annual Report 1998.

NUREG-1433 V2 DAF FC: ST ANDARD TECHNICAL SPECIFICATIONS GENERAL ELECTRIC UNITS, BvvR/4 Bases (Sechons 2 0 3 3) Draft SolldtfL;* ion Process Report For Comment.

NUREG/Ch ;672 V01 CHARACTERISTICS OF LOW-LEVEL RADIOAC.

NUREG-1433 V3 DRF FC: ST ANDARD TECHNICAL SPECIFICATIONS TivE WASTE. Decontawnaton Waste. Annual Report For Fmcal 1ea' GENER AL ELECTRIC UNITS, OWR /4 Bases (Sections 3.4 - 310l Draft 1990 Report For Comment

Subject index 87 NURLG 1434 VI DRr FC STANDARD TECHNICAL SPECIFICATIONS TLD GENERAL ELECTRIC PLANTS, BWR/6 Speoticoons Deatt RWatt I or NUREG-0837 V10 f404 NRC TLD DIRE C1 RADiAttoN MONIf ORING Comment NETWORK Proyess Repret Octoter-Decemtwr 1930 NuttEG 1434 V2 DRI~ FC STANDARD TECHNICAL SPECIFICATONS NUREGo037 Vit NOI: NRC TLD DIRECT RADIATON MONITORING GENERAL ELECTRIC PLANT s, BWR/6 Dases (Sections 20 NETWORK Prog'ess Repyt JanuavMarch 1991.

3 31 Dra't Rebon f or Comment NUREG-0837 V11 NO2 NRC TLD DIRECT RADIATON MONITORING NURtG 1434 V3 DRF FC: STANDARD TECHNICAL SPECIFOATONS NETWORK. Prog'eus Report AprilJune 1991 GENERAL ILECTRIC PLANTS, B AR/6 Dases (Sectons 34 NUREG-0837 Vit NO3 NRC TLD DIREC1 RADIATON MONITORING 310) Draft ReFut Few Corraient NETWORK Progress 9eport. JutrSortember 1991.

Station Blackout TMl Actawl Plan NUREG 1401 DAFT FC: REGULATORY At4ALYSIS FOR GENERO NUREG 1435 $01: ST ATUS OF SAFETY ' JUES AT LICENSED ISSUE 23 REACTOR COOLANT PUMP SE AL FAILURE Draft Report POWER PLANTS.TM1 Act.on Ptan Regurementa urvosolved talety For Comment issues Genenc Sately losues NUREGICR 6571 1HE RESPCNSE OF BWR MARK lli CONTAIN-NUREG.14*l5 V01: ST ATUS OF SAFETY ISSUES AT LICENSED MEN 1s TO SHORT TERM STATON BLACKOM SEVERE ACCIDENT POWER PLANTS TML Action Plan Requpements SE QUENCES Technetium Steam Generator NUREG/CR 5464 ANON RETENTON IN SOIL: POSSIBLE APPLICA+

NUREG 09v5 V08 COMPILATION O' CONTRACT RESEARCH FOR TlON TO REDUCE M;TGRATION OF BU%ED TECHNEilVM AND THE MATERIALS ENGINEE RING DRANCH.DIVISON OF IODINE.A Rewsw, ENGINEERING Annual Report For FY 1990 NUREG 14M V01; COMPILATION OF REPORTS FROM RESEARCH Technicalleeve Resolution SUPFORTED BY THE MATERIALS ENGINEERING NUREG/CR 5609 DAF f C: AN INTEGRATED S1RUCTURE AND SCAL-DRANCH. DIVISION OF ENGINEEtuNG 1965 1990 ING METHODOLOGY FOR SEVERE ACCOENT TECHNICAL ISSUF NUREG/CR-4993 TECHNICAL F NDINGS REPORT FOR GENERIC RESOLUTION Dratt Report For Comment ISSUE 135 Steam Onne'ator And Steam Une Ove< fill issued NUREG/CR $395 V01 MULTILOOP INT E GRAL SY8 TEM TEST Technical Poemon (MIST) FINAL REPORT Summa NUREG 1439 STAT F TECHNICAL POSITION ON REGULATORY CON-NUREG/CR-5670 MULTitOOP. TEGR AL SYSTEM TEST (VIST) MIST SOCRATONS IN THE DES 10N AND CONSTRUCTION OF THE Ex.

F ACILITY FUNCTIONAL SPECIFICATON PLORATORY SHAFT F ACluTY' NUREG/CR 5796 STEAM GENERATOR OPE R ATING LAPERIENCE. UPDATE FOR 198919m Technical Speelf6catione Strain Monitoring Network NUREG/CR-5742 VO1: FEASifMITY ASSESSMENT OF A RISK BASED NUREG/CR 5777. GLOBAL POSITIONING SYSTEM ME ASUREMENTS

^

^

NUR C 7 2 E SD TY SS A'RI ED OVER A STRAIN MONITORING NETWORK IN THE EASTERN TWO-TH:RDS OF THE UNITED STATES.

APPROACH TO TECHNICAL SPECIFOATIONS Main Report.

UI G/CR 3145 V09

""*"U**"*"

GEOPHYSICAL INVESTIGATONS OF THE NUREG/CH S677. A UNIFIED INTERPRETATION OF ONEJIFTH TO FULL ECALE THERMAL MI* LNG EXPEnlMENTS RELATED TO PRES-WESTERN CHIO-INDIANA REGION Annual ReportOctober 19fi9 -

SURIZED THERMAL SHOCK.

6'PI'" " #

Tecton6c Deformation NU EG 445 A G 10RY ANALYSIS FOR THE RESOLUTON OF NUREGrCR 5749 TECTONO DEFORMATION REVEALED IN BALDCd CENERIC SAFETY ISSUE-29 BOLTING DEGRADATON OR FAILURE PRESS TREES AT REELFOOT LAKE. TENNESSEE-IN NUCLEAR POWER Pt ANTS NURFG/CR-4667 V09. ENvlRONMENTALLY ASSISTED CRACKING IN UR O 628 PENNSYLVA.41A SEISMIC MONITORI:M NETWORK N E /C 7V0 O h NR AND FIELATED TECTONIC STUDIES Final Report Y

NG LIGHT WATER REACTORS Somannual Report, October 1989, March Tenelle N

/CR 4667 V11: ENVIONMENTALLY ASStSTED CRACKING IN N#

LIGHT WATER REACTORS Semiannual Report,Apr4 September 1990.

TENSILE PROPERTIES OF - LOW UPPER-SHELF - WELDS,HSSI NUAEG/CR 4667 V12. ENVIRONMENTALLY ASSISTED CRACKING IN SERIES 2 AND 3 LIGHT WATER REACTORS, Sernannual ReportOctober 1990 March T6nelle Strength NUREG/CR 5508 IMMERSION STUDIES ON CANDOATE CONTAINER NUREG/CR 5688 MECHANICAL CHARACTERl2ATON OF DENSELY ALLOYS FOR THE TUFF REPOSITORY' NU GCR57 A AT EMBRITTLEMENT OF THE NEUTRON Suppresolon Pool SHIELD TANK Fr40M THE SHIPPINGPORT REACTOR.

NUREG/CR.5765. SPARC 90- A CODE FOR CALCULATING FISSON PRODUCT CAPTURE IN SUPPRESSION POOLS, T'

2%:d TESier40 STANDARDS FOR PHYhtCAL SECURITY SYS-R Surge Line TEMS AT CATEGORY I NEL CYCLE FACILITIES. -

NUREG/CR4456: ANALYSIS OF FLOW STRAtlFICATION IN THE SURGE LINE OF THE COMANCHE PEAK REACTOR.

Thermal NUREG/CR 5620: THATCH A COMPUTER CODE FOR MODELLING Systemaue Assessment Of Licensee Performance THERMAL NETWORKS OF HIGH-TEMPERATURE GASCOOLED NU-NUREG 1214 R07. HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT.

CLEAR REACTORS.

O ASSESSMENT OF LICENSEE PERFORMANCE.

Thermal Aging TABLETOP Eserclee NURE G/CR-4513 ESTtMATON OF ~FRACTU9E TOUGHNESS OF NUREG 1441: LESSONS LEARNED FROM THE POST EMERGENCY CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-TABLETOP EXERCISE IN BATON ROUGE, LOUISIANA.ON AUGUST TEMS.

20 AND SEPTEMBER 18,1990-NUREG/CH-5546. AN INVESTIGATON OF THE EFFECTS OF THER.

NUREG 1442.

POST EMERGENCY RESPONSE RESOURCES MAL AGING ON THE FIPE DAMAGEABILITY OF ELECTRIC CABLES GUCE Based On The Post-Emergency TABLETOP Exercise m Baton.

NUREG/CR4619' THE IMPACT OF THERMAL AGING ON THE FLAM-Rouge.Lossiana,On August 28 And September it,1990.

MABILITY OF ELECTRIC CABLES.

THATCH Computer Code Thermal Miring NUREG/CR 5620. THATCH A COMPUTER CODE FOR MODELLING NUREG/CR-5677; A UNIFIED INTERPRETATION OF ONE FIFTH TO THERMAL NETWORKS OF HIGH-TEMPERATURE GAS COOLED NU-FULL SCALE THERMAL MIXING EXPERtMENTS RELATED TO l'RES-CLEAR REACTORS. -

SURIZED THERMAL SHOCK.

.k

)

88 Subjed Index Thermal riydraul6c TMrRepos:1ory NURIG/CR MA3 HELAP5 THE AMAL HfDRAULiC ANALYS6 Or 1HE NUMEG/CR %98 IMMI RSION STUD!f S ON CANDOATE CONI AINER WNP1 PRESSURV(D W ATER RE ACTOR ALLOfS LOR THF TUFF REPOSITORY Thermodyriamic Unresolved Safety issues NUREG/CH 5312 A THL AMODYNAMIC MODEL OF f ut L DISRUP.

NURE G 1435 V02 STATUS OF SAF E TY iSSut S AT LKtNSl0 110N IN $1 1 POWE R PL ANTS Unressved Saftety issues Thermoluminescent Dostmeter Untaturated Flow NUREG 0837 V10 N04 NRC 1LD D+ RECT RAD;ATION MONITORIN3 NUREG/CR 5530 DCV3D A DUAL-CON 11NUUM THRE E-DIMENSON-NE TWORK Provoss Report Octotew Decemt+r 1940 AL GROUND WATER FLOW CODE FOR UNSATURAtlD, F RAC-NURI G 083/ V11 N01 NRC TLD DMECT RADI ATON MONITORIN3 TURED. POROUS MID)A NETWORK Pfowest Report January Mao 1991 NUREG/CR 5743 APPROACHES TO L ARGE SCALE UNSATUHATED NURL0 0637 VII ND2 NHC TLD DIR(C1 RADIAtlON MONITORING F LOW lN HETE ROGENEOUS, STRATIFIED, AND F RACTURED GEO.

NETWORK Progress Report Aptd June 1991 LOQC MEDIA.

NUMEG-0837 VII NO3 NRC TLD DIRECT RADIATION MON 110RlNG NETWOHK Progress 9eport July September 1991.

Unnatursted Transport Thickness Reductlon NUREG/C4 5352 RO1 VAM2D - VARIADLY SAIURATED ANALYS*$

NUMEG/CR 5697. USE Or THICKNESS REDUCTION TO ESTIMATE MODEL IN TWO DiMENS ONS Verpon 6 2 With Hysteresis Ard Cten VALUE S OF K.

Decay Transport Oxumentaten And User s Gude Title Uet Unsaturated Zone NUREG4540 V12 N11. TITLE LIST OF DOCUMENTS MADE PUBLICI Y NUREG/CR 5795 VALIDATION AND TES11NG OF THE VAM2D COM-eviER CODE AVAILABLE November 1 30.1990 NUHEG 0540 V12 N12 TITLE LIST OF DocuMLNTS MADr Pi.ithiCLV Uranium Henafluoride AVAILABLE Deceber t-31,1990 NUF.E G 1391-CHEMICAL TOXICITY OF URANIUM HEXAF LUORIDE NUREG OMO V13 N01 TITLE LIST C' DOCUMENTS VADE PUBLICLY AVAIL ABLE January 131,1t191 COMPARED TO ACUTE LFFECTS OF RADiAT60N Final Report NUREG 0540 V13 NO2. TITLE Libi OF DOCUMENTS MADE PUUllCLY Uranium Will Talling AVMLAbit February 1 28. 1991.

NUREGOMO V13 NO3 TITLE LIST OF DOCUMINTS MADE PUBLICLY NUREG/CR 5432 V01 RECOMMENDATONS TO THE NRC FOR SOIL AV Alla0L E March 131,1991 COVE R SYSTEMS OVE R URANtUM MILL TAILINOS AND LOW.

NUPE40540 V13 N04 TITt E LIST C# DOCUMENTS MADE PUBLICLY LEVEL HADIOACTIVE VOSTES. Identificaton And Ranung Of Sosis t & Di NUREGb,w recSty Covers AVAILABLE Aprd 1-30,1991 5432 V02. RECOMMENDATONS TO THE NRC FOR SOlt NUnt G 0540 Vt3 N05 TITLE llST OF DOCUME NTS MADE PUBLICLY COVER SYSTEMS OVER URANIUM MILL T AILINGS AND LOW.

N 0V N T T E LIST OF DLOUMENTS MADE PUBLICLY AV AIL ABL E June 1 30,1991 NUREG 40 V13 N07 Ti1LE LIST OF DOCUMLNTS M ADE PUBUCLY NU CR $432 V03 SECOMVENDATIONS TO THE NRC TOR SOtt COVER SYSTL MS OER URANtVM MILL 1 AILINGS AND LOW.

NUREG 0540 V13 NOB TifLE LIST Or DOCUMENTS MADE PUOLICLY LEVEL RADIOACTIVE W8STFS. Constructon Methods And Gudance AVAtLABLE August 1 31.1991.

For Seahng Penetratons in Sod Covers NUREG 0M0 Via No9 TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE September 140,1991 Uranium Reprocessing NUREG 0540 V13 N10 fl1LE LIST OF DOCUMENTS MADE PUDUCLY NUREG-1450 POTENTIAL CRlilCAUTY ACCIDENT AT THE GENERAL AVAiLABLE Octater 1 31,1931.

ELECTRIC NUCLEAR FUEL AND COMPONE*ll MANUFACTURING F ACILITY, MAY 29,1991.

Tom 6c 3ases NUREG/CR Sf.9 EVALUATON OF EXPOSURE LIMITS TO TOxlO VAM20 Computer Code GASES FOR NUCLEAR RE ACTOR CONTROL ROOM OPERATORS.

NUREG/CR 5352 A01' VAM2D - VARIADLY SATURATED ANALYSIS Tosic Substanto MODEL IN TWO DIMENSIONS Version 5 2 Wiln Hysteresis And Chain Dway Transport Documentation And L ser's Gada NUREG/CR 5656 EK1HAN A COMPUTER CODE FOR ESTIMATING NUREG/CR 5795 VAUDATON AND TESTING OF THE VAM2D COM.

CONCENTRATION 3 OF TOxtC SUBSTANCES AT CONTROL ROOM PUTER CODE AIR INTAKES Vendor inspection Transformer Fallure NUREG-0040 V14 N04. LICENSEE CONTRACTOR AND VENDOR IN.

NUREG-1455 TRANSFORMER FAILURE AND COMMON MODE LOSS SPECTION STATUS REPORT. Qua'1erty ReportOctober-Docember OF INSTRUMENT POWER AT NINE MILE POINT UNIT 2 ON 1990 Mbite Book)

AUGUST 13,1991.

NUREG 0040 V15 N01 LICENSEE CONTRACTOR AND VENDOR IN-SPECTON STATUS REPORT-Quaserty ReportJanuary March Transport 1991 (White Book)

NURE G /CR-4269 MODELS OF TRANSPORT PROCESSES IN CON.

NUREG 0040 V15 NO2-LICENSEE CONTRACTOR AND VENDOR IN-CRETE.

SPECTON STATUS REPORT. Quarterty Report.Ap'd June 199t(White NUREG/CR 5561: UNSATURATED FLOW AND TRANSPORT Dook)

THROUGH CRACTURED ROCK RELATED TO HIGH LEVEL WASTE NUREG-0040 V15 NO3 LICEN3EF CONTRACTOR AND VENDOR IN-REPOSITORIES Final Report. Phase ill SPECTION STATUS REPORT. Qua1erty Report, July Septomter Transport Calcutation NUREG/CR-5648 T R ANSFOR T CALCULATIONS OF NEUTRON Venting TRANSMISSON THROUGH STEEL USING ENDF/D V. REVISED NURE G/CR-5654 CONTAINMENT VENTING ANALYSIS FOR THE ENDF/04AND ENDF/D VI1RON EVALUATIONS.

SHOREHAM NUC. EAR POWER ST ATION Transportation Package Vibration NUREG/CR-5717. PACKAGING GUPPUER INS"ECTION GUIDE.

NUREG/CR-5585 THE HOH LEVEL VlDRATON TEST PROGRAM Final Transverse titrmin NUREG/CR 5592' ANALYllCAL STUDIES OF TRANSVERSE STRAIN Video System EFFECTS ON FRACTURE TOUGHNESS FOR CIRCUMFERENflALLY NUREG/CR 5721: VIDEO SYSTEMS FOR ALARM ASSESSMENT.

ORiNTED CRACKS Weste Burial T'Jtse Rupture NUREG.1307 R02 REPORT ON WASTE DURIAL CHARGES Escalaton NUREG /CR-4893 TLCHNICAL FINDINGS REPORT FOR GENERIC Of Decommmsiorung Wasie Disposal Costs At Low-Level Waste Banal ISSUE 135 Steam Generator And Steam One Overht!lasuas Facdities it

Subject index 89 Wait. Disp.at weooo Gais vaNo NUREG/CH 57k4 GROUND W ATE R FLOW AND TRAt45POH! MDDi L-NUREG/CRt%8 GENERIC ISSUE Bt. f LE AtBLE WLDGE GATE ING N THE NRC-L CENEED W ASTE DISPOSAL F ACillTY WEST VALVE TEST PROGRAM Phase it Hesults Ana Ana'ysis V ALLE Y. NE W YO4K Weste Disposai Cost NUhEG/CR $$51 TWO NE'W NDT TECHNOUES FOR INSPECT 60N OF NUREG 1307 402 REPORT ON WASTE BUHlAL CHAHGL S Escafeten CON t AiNMENT WELDS BENEATH COATINGS Final Report.Octater i

Of De:omtmorung Weste Diapt4al Costs At Lon Level Weste Bunal p,e g,p, 1989. March 1990 Wette Package Welded Apache Eeap Tuff NUREG/CR 5037 v..vE RT AINT Y E v AL U ATION MET HODS FOR NUREG/CR M88 MECHANICAL CHARACTERl2ATION OF DENSELY WASTE PACKAGE PEnrOnMANCE ASSESSMENT.

WELDED APACHE LE AP TUFF.

Water flow Welded Tuff NUnEG/CR 5716 MODE L VAllDATON AT THF LAS CRUCES NUHEG/CR 4295 BOND STRENGTH OF CEMENTITIOUS DOREHOLE TRENCH SITE PLUGS IN wtLDED TUFF Water infiltrat6on NUREG/CR %83 LABORATORY 1ESTING OF CEMENT GROUTING NUHE G/CR-4918 VOS CONTROL OF WATER INFILTRATON INTO OF FRACTURES IN WELDED TUFF.

NEAR SURF ACE LLW PISPOSAL UN!TS Prorpens Repo<1 On Field Es-

• * "9 penments At A Humid Regen inte BeltsWile. Maryland p

Water Pool WESTINGHOUSE PLANTS Specifications Draft Report For Cornment NUHEG /CIL3916 PRESSURIZED MELT EJE CT.ON INTO WATER NUREG 1431 V2 DAF FC STANDARD TECHNICAL SPECIFICATIONS POOLS WESTINGHOUSE PLAN 1S Bases (Secteune 2 0-3 3) Draft Report For NUREG/CR 908 CALCULATON OF ABSOhBED DOSES TO WATER Comment.

POOLS IN SEVERE AOCOENT SEQUENCES NUREG 1431 V3 DNF FC STANDARD TECHNICAL SPECIFICATIONS WESTINGHOUSE PLANTS bases (sectons 3 4 3 9) Draft Repon For Water Fleactor Safety NUREG/CP-0114 Vol. PROCEEDINGS OF THE EIGHTEENTH WATER Comment DE ACTOR SAFETY INrORMATION ML ETING NUHEG/CP 0114 V02 PHOCEEDINGS OF THE EIGHTEENTH W ATEn Yucca Mountain FW AC1084 SAFETY INrOHMATON MEETING NUREG/CR 5743 APPROACHES TO LANGE SCALE UNSATURATED NUREG/CP-0114 V03 PROCEEDINGS OF THE ElGHTEENTH W ATER FLOW IN HETE HOGENCOUS, 51RATIFIE D, AND F R ACTUHED GEO-REACTOR SAF ETY INFORMATON MEETtNG.

LOGIC MEDIA _

e-m..-____-

NRC Originating Organization index (Staff Repony This index lists thoso NRC organizations that have published stall reports. Tho index is ar.

ranged alphabotically by ma or NRC organizations (e.g., program officos) and then by-sub-sections of those (e.g., divis ons, brancios) where appropriato. Each entry is followod by a NUREG number and title of the report (s). If further information is noodod, refer to the main citation by NUREG number.

ADVISONY COMMITTEE (S)

NUREG 0540 V13 Not. Ti1LE LIST OF DOCUMENTS MADE PUBLO ADylSORY COMMIT 1E E ON NUCl E AR WARTE LY AVA;L ABL E. January 1 31,1991 NUREG-ta23 V02 A COMPILATON OF MPORTS OF 1HE ADVISO-NUREG-Of 40 V13 NO2 TITLE LIST OF DOCUMEN1b MADE PUBUC-AY COMs.1TTEE ON NUCl E AR WASTE J 1990 June 1991-LY AVAIL.ADLE. f ebruary 1 28,1991, t4UREG 0540 Yt3 f403 TITLE LIST OF DOCUMENTS MADE PUBLC U

112 2A T 4 REPO sr i ADVISO-RY COMMIT 1E E ON REACTOR SAFEGUARDS 1990 Annel.

gk#YA Uh M"'Uhh3i(f 'y'y ggg pg g4 L

1 g4 3

OT0MIC BAFETY BOARivS) & PANE LiS1 LV AVAILADLE April 1,30,1991.

ATOMIC SAFETY & LIC&N5iN3 HOARD PANEL NUREG4540 V13 N05 llTLE LIST OF DOCUMENTS MADE PUBLC N' 'RE G-1363 V03. ATOMIC SAFETY AND LICENSING BOARD LY AVAILABLE. May 1 31, 1991 PANEL ANNUAL REPORT Fiscal Year 1920 NUREG 0540 Vt3 N0a TITLE tlST OF DOCUMENTS MADE PUBLO iOh5 O 1 E UTIE fECT Fr E

NUREG 14% POTEN16AL CRittCALITY ACCIDENT AT THE GENER-W AV AWLE. My W. M AL ELECTRIC NUCLEAR FUEL AND COMPONENT MANUF ACTUR-P4UREG 0540 V13 ND6 itTLE LtST OF DOCUMENTS MADE PUBLIC.

ING F ACIUTY, MAY' 29,1991 LY AVAILADLE. August 1 31,1991.

NUREG 14% T R ANSF ORME R F AtLURE AND COMMON MODE NUREG 0540 V13 P409 TITLE LIST OF DOCUMENTS MADE PUhtlC.

LOSS Or INS 1RUMENT POWER AT NINE MILE POINT UNIT 2 ON LV AVAILADLE. Septemter 1 30, 1991 AUGUST 13.1991.

NUREOC540 V13 N10 TITLE LIST OF DOCUMENT 1 MADE PUBLIC-REGION 1 IPOST e?0201)

LY AVAILADLE. Ocwher 1 31,1991.

NUREGoe37 V10 Nc4 NRC TLD DIRECT RADIATON MONITORtNG NUREG 0750 V32102' INDEXES TO NUCLE AR REGULATORY COM.

NETWORK Prosess Rewt October Decemter 1990 MISSION ISSUANCF.S.My December 1990 NUREG 0837 V1 f N01. NhC TLD DIRECT RADIATION MONITORING t40 REG-0750 V32 f405. NUCLEAR REGULATORY COMMISSION IS-NETWORK Progets Report January March 1991-NUREG 0837 Vit NO2-NRC TLD DIRECT RADIATION MONITORING SUANCE S FOR NOVEMBER 1990. Pages 333 303 NUREG 0750 V32 N06. NUCLEAR REGULATORY COMMISSION IS-NURE 837

$0 t

D C DIATION MONITORING SUANCES FOR DECEMBER 1990 Pages 395496 IFTWORK Progress Report Jufy bcptember,1991 NUREG4760 V33101. INDEXES TO NUCLEAR REGULATORY COM-REGION 4 (POST 820201)

MISSON ISSUANCES. January Maech 1991.

NUREG 1441; LESSONS LEARNED FROM THE POST EMERGENCY NUREG 0750 V33102: INDEXES TO NUCt. EAR REGULATORY COM-TABLE 10P EXERCISE IN DATON ROUGE.LOUISLANA.ON AUGUST MISSON ISSUANCES Jarwarydune 1991.

28 AND SEPTTMBER 18.1990 NUREG 0750 V33 N01: NUCLEAR REGULATORY COMMISSON IS NURE G 144L POST EMEFtGENCY RESPONSE RESOURCES SUANCES FOR JANUARY 1991. Pages 140.

GUOE Based On The Post Emergency TABLETOP Esercase en NUREG 0760 V33 NOT NUCLEAR REGULATORY COMMISSON IS-Daton Rouge. louisiana.On August 28 And September 18,1990 SUANCES 7 OR FEBRUARY 1991 Pages61-173 OFC OF ENFORCEMENT (POST 87U13l NUREG-07SO V33 NO3 NUCLE AR REGULATORY COMMISSON IS-NUREG 0940 V09 f404 ENFORCE JNT ACTIONS. SIGNtFICANT AC-SUANCES FOR MARCH 199$ Pages 176 232.

TONS RESOLVED ouarterty Progress Report.0ctote Decomter NUREG 0760 V33 ND4: NUCLEAR REGULATORY COMMISSON IS.

^

^

N G 0940 V10 N01: ENFORCEMENT ACTIONS. SIGNIFICANT AC-NUR G 50 V33 No P A

GU TORY COMMISSION is.

T AWONS

[t A T

'C-SUANCES FOR MAY 1991 Pages 295 459.

NU E O O t 2 N HE TIONS RESOLVED Quarterly Progress Report. April-June 1991.

V33 M N W M M M M M M M $

t. ' REG 0940 V10 NO3 ENFORCEMENT ACTIONS SIGNIFICANT AC.

SUANCES FOR JUNE 1991.Pages 481-619 TIONS RESOLVEDOuartedy Progress ReportJuly bertemtier 1991, NUREG 0760 V34 N01 f40 CLEAR REGULATORY COMMISSON IS-SUANCES FOR JULY 1991.Pages 1148.

EDO. OFFICE OF ADMINISTRATION (PRE 870413 & POST 690205)

NUREG 0750 V34 NO2. NUCtEAR REGULATORY COMMISSION IS-OFFICE Or ADMINISTRATON (POST 890?05) 60ANCES FOR AUGUST 1991. Pages 149-183 NUREG 1145 V07 U$ NUCLEAR REGULATORY COMM.SSON N';REGC760 V34 NO3: NUCLEAR REGULATORY COMMISSION IS-1990 ANNUAL REPORT-DIVISON OF FREEDOM OF INFORMATON A PUBLICATONS SERV' SUANCES FOR SEPTEMBER 1991, Pages 185 228.

NUREG4750 V34 N04= P4UCLEAR REGULATORY COMM!SSON IS-N EG O 04 Vi t 04 REGULATORY AND TECHNICAL REPORTS DA

"#' O #

(ABSTRACT INDEX JObRNAL) Annual Compilation For 1990 f4UREG 0936 V09 N04 NRC REGULATORY AGENDA.Quarle'iy WUREG 0304 Vt6 N01: REGULATORY AND TECHNICAL REPORTS Report,0ctober Decemter 1990 (ABSTRACT INDEX JOURNAL) Compilation For First Ouarte, NUREG 0936 V10 NOI. NRC REGULA10RY AGENDA Quartery 1991. January March.

Report.Jarluary March 1991.

NUREG 0304 V16 NO2 REGULATORY AND TECHNICAL REPORTS NUREG 0938 V10 NO2 NRC REGULA10RY AGENDA Quarterly (ABSTRACT INDEX JOURNAL). Compilation For Second Quarte, ReportApell-June 1991.

1991,Aprildune NUREG 0936 V10 NO3: NRC REGULATORY AGENDA Ouarterly NUREG4304 V16 NO3 REGULATORY AND TECHNICAL REPORTS ReportJu'y September 1991.

(ABSTRACT INDEx JOURNAL) Compilation For Thtd Quarter 1991. July Septemter EDO. OFFICE OF THE CONTROLEER (PRE 420414 & POST 890205)

NUREG-0540 V12 N11: TITLE LIST OF DOCUMENTS MADE PUBLO.

DIVISON OF BUDGET & ANALYSIS (POST 890205)

LY AVAILABLE. November 1 30,1990 t4UREG-1100 V07: BUDGET ESTIM ATES Fiscal Years 1992-1993.

NUREG4540 V12 N12. TITLE LIST OF DOCUMENTS MADE PUBLIC.

NUREG-1350 V03: NUCLEAR REGULATORY COMMISSON INFOR.

LY AVAILABLE. December 1 31,1990 MATON DIGEST.1991 Echten.

91

92 NRC Originating OrgentratlOn Index (Staff Reports)

EDO. OFFICE f OR ANALVEls & EVALUATON OF OPERATIONAL U S. NUCLE AR REGLtLATORY COMMIT $lON DATA OfflCE 08 IMt GLNERAL COURsu Wost h07DN OF FICE FOR ANALYSIS & EVALUATON OF OPERATONAL DAt A. DI.

NUREGem DOS A09 uni 1ED ST ATLs NUCLE AR REGULATORY F4ECTOR COMMISSON STAFF PRACTICE AND PROCEDURE NUREG 0090 V13 NO3 REPORT TO CONGRESS ON ABNORMAL DIGEST Comfrusmort Appeal Board And L6 tensing Board OCCURF4E NCE S Julv.Septemter 1990 Deosons Juiy 1972 Septomter 1930 feUREG 0090 V13 N04 RE POR1 TO CONGRtiSS ON ABNORM 4 NUREG-0386 D06 UNttE D bT A1ES NUCt EAR REGULATORY COM-OCCURRENCE S 0:tober December 1990 MiSSON

$1AFF PRACTICE AND PROCfDURE NUREGWO V14 9401-REPORT TO CONGRESS ON ABNORMAL DIGEST Commetraon. Appeal Doord And lxonting Decmons July OCCURRENCES January March 1991-1972 Decemtser 1990.

NUREG 0090 Via t02. REPORT TO CONGRESS ON ABNORMAL t4UREG o980 V01 Not:

NUCLEAR REGULATC9Y OCCURRENCES Aprildune 1991.

LE W$LAT ON 101st Congress f4UREG.On90 Via NO3 REPORT TO CONGRESS ON ABNONMAL NURE G 0900 V02 No t.

NUCLEAR F4EGULATORY OCCURRENCES Ju'.y Septemter 1991 t EGiSt ATON 101st Co.ncress NUREGa022 Ho DR F C: EVENT REPORTING SYSTEMS 10 CFR OFFICE OF THE INSPECTOfl GENf RAL FOST $90417) 6032 AND $0 73 Cianicaton Of NRC Systems And Gudehnes for NURE G 1415 V03 N07 OF FICE OF THE INSPEC10R Reporting Droft Report For Comment GE NERAL Semiannual Report Ocipe 1990. March 1991..

HURLG-1272 VOS N01 OF FICE FOR ANALYS13 AND EVALUATON NUREG-1416 V04 Not OF F ICE OF THE INSPECTOR OF OPERATIONAL DAT A 1990 Annual Report. Power Reactors GENERAL Sewannual Report Arni.Septemter 1991-NUREG 1272 VOS NO2 OFFICE FOR ANALYSIS AND EVALUATON NRC. NO DETAllED AFFILIATON GIVEN OF OPERAflONAL DAf t. M90 Annual Report. Nonreactors NUREG/CR 4061 AN It4VESTIGATION OF CORE L10080 LEVE.L DE.

NUREG tF76 "06 OPER!NO EXPERIENCE FEEDBACK REPORT -

PRESSON IN SMAll BREAK LOSS.0F4 COOLANT ACCIDENTS ENOC-OPERATED M1 PROBLEMS Commercial Power Re.

EDO. OFFICE OF NUCLE AR REQULATORY RESE ARCH (POST 820406)

NUREG 1303 RO1' INCIDENT INVE$ilGATION MANUAL.

OFFICE OF NUCLEAR nrCULATORY Rt SEARCH (POST ti607201 INCIDENT RESPONSE BRANCH NUREG 1266 V05 NRC NAFETY RESEARCH IN buPPORT OF REG-NUREG 144t: LESSONS LEARNED f ROM THE POST EMERGENCY ULATION. F Y 199u T ABLETOP EXERCibE IN BATON ROUGEAOUlstANA,0N AUGUST NUREG 1309 PREAPPLICATION SAFETY EVALUATION REPORT 28 AND SEPTEl+ DER 18,1900 FOR THE SODlutA ADVANCED rAST REACTOR (SAFR) LIOul0 NUREG 1442 POST. EMERGENCY RESPONSE RESOURCES METAL REACTOR GUIDE Dased On the Post. Emergency TADLETOP Exercise en NUREQ/CP.0037; PROCEEDINGS OF THE St MINAR ON ASSESS.

Daton Rougelouisiana On August to And Septamter 18.1990_

MENT OF FHACTURE PREDICTON TECHt40 LOGY; PIPING AND PRESSURE VI SSELS EDO

• OFFICE OF IPFORMATION RESOURCES MANAGEMENT & ARM NUREG/CP-0110 TRANSACTON4 OF THE NINETEENTH WATER (POST 841109)

REACf 0A SAFETY INFORMATION MEETING.

DIVISON OF COMPUT ER & TELECOMMUNICATONS SERVICES DIVistON OF ENGINEERING (POST 870413)

(POS180205)

NUREG4976 V08 COMPILATION Or CONTRACT RESEARCH FOR NUREG.0020 Vt$ LICENSED OPERATING RE ACTORS STATUS THE MATE RIALS ENGINEERING BRANCH,DIVISON OF

SUMMARY

REPORT Data As Of December 31,1990 (Gray Book 1)

E NGINEERING Annual Repor1 For FY 1990.

NUREG 1144 R02, NUCLL AR PLANT AGING RESEARCH (NPAR)

EDO. OFFICE OF NUCLE AR WATERIAL SAFETY & SAFEQUARDS PROGRAM PLAN Status And Accomphshments Of FICF OF NUCLE AR MATERIAL SAFETY & SAF EOUARDS NURE41377 R02. NRC RESEARCH PROGRAM ON PLANT AGING NUREG 0430 V10.

LICENSED FUEL F ACILIT Y STATUS LISTING AND SUuMARIES OF FIEPORTS ISSUED THROUGH REPORT.mventory Ditterence DatsJuly 1989 June 1990(Gray JUNE 1991.

ON" Ill NUREG 1426 V01: COMPILATON OF REPORTS FROM RESEARCH DIVISION OF SAFEGUARDS & TRANSPORT ATION (PUST 8704131 SUPPORTED BY IHE MATERIALS - ENGINEER:NG NUREG-03B3 V01 R14. DIRECTORY OF CERTIFICA1E S OF COMPLi*

BRANCH DIVISION OF ENGINEERING 114 5 1990 ANCE FOR RADIOACTIVE MATERIALS PACKAGES Report Ot NRC DIVISON OF REGULATORY APPLICATONS (POST 870413)

Approved Packages.

NUREG 0713 Vio OCCUPATIONAL RADIATION E APOSURE AT NUREG-0383 V02 H14 DIRECTORY OF CERTIFlCATES OF COMPLl' COMMERCIAL NUCLEAR POWER REACTORS AND OTHER ANCE FOR RADCACTIVE MATERIALS PACKAGESCortificales Of F ACILITIES 1988 Twent et Annual Report NU E 03)3 V03 R11. DIRECTORY OF CERTIFICATES OF COMPLt-gg ANCE FOR RADCACTIVQ MATERIALS PACKAGES Report Of NRC NUREG-0933 S13 A PRORIT12ATION OF GENERIC SAFETY Approved Quahty Assurante Progran.s For Radioactive Materues ISSUES Packages NUREG 1307 R02.

REPORT ON WASTE - DURIAL NURE G-0525 R17: SAF EGUARDS

SUMMARY

EVENT LIST CHARGES Escalatiert Of Decommissioning Weste D:sposal Costs At (SSEL) Pre NRC Through Decemter 31,1990 Low, Level WMie Banal Fac*tes.

NUREG4726 ROF; PUDLtC $NFORMAtlON CIRCULAR FOR SHIP-NUREG 1391; CHEMICAL TOxlCITY OF URANIUM HEXAFLOORIDE MFNTS OF IRRADtATED REACTOR FUEL COMPARED TO ACUTE EFFECTS OF RADI ATION Final Report i

NVAG 1321 TESTING ST ANDARDS FOR PHYSICAL SECURITY NUREG-1400 DRVT FC: AIR SAMPLING IN THE WORkPLACE. Draft SYSTEMS AT CATEGORY I FUEL CYCLE FACtLITIES-Report For Comenont NUREG-1322, ACCEPT ANCE CRITERIA FOR THE EVALUATON OF NUREG-1448. ST ANDARDS FOR PROTECTON AGAINST RADI-CAT EGORY I FUEL CYCLE FACILITY PHYSICAL SECURITY ATION.10 CFR PART 20. A Compa%on Of The Existmg And Re.

PLANS vined Rules.

DIVISION OF HIGH4 EVEL WAS1E MANVE MENT (POST 870413)

WASTE MANAGEMENT BRANCH (POST 910830)

NUhEG-1430 STAFF TECHNICAL F JSITON ON REGULATORY NUREG/CR 4918 V05 CONTROL OF WATER INFILTRATION INTO CONSOERATONS IN THE DESIGN AND CONSTRUCTON OF NEAR SURFACE LLW D!$POSAL UNITS Progress Report. Ori held THE EXPLORATORY SHAFT F ACILt1Y.

Emenments At A Humid Rmon Site Bottavole. Maryland.

NUREGICR 4735 VDE EVALUATON AND COMPILATION OF DOE DIVISidN OF SAFETY ISSUE RISOLUTION (POST 880717)

WASTE PACKAGE TEST DATA. kannual Report Fetruaryduly

~ NUREG4933 S0110 A F'HORITi2ATION O' GENERIC SAFETY 1991 ISSUES DIVISION OF LOWLEvtl VvASTE MANAGEMENT & DECOMMISSION.

NUREG 1362: REGULATORY ANALYSTS FOR FINAL RULE ON NU-ING (POST 870413)

CLE AR POWER PLANT LICENSE RENEWAL Final Re, ort.

NUREG 1199 R02, STANDARD FORMAT AND CONTENT OF A Ll-NUREG 1374; TECHNICAL FINDINGS RELATED TO OcNERIC ISSUE CENSE APPLICATON FOR A LOW LEVEL RADIOACTIVE WASTE 79 An Evaluaton Of PWR Reactor Vessel Thermal Stregs Dunng DISPOSAL FACILITY.

Naturd Convection Cooldown NUREG 1200 R02: ST ANDARD REVIEW PLAN FOR THE REVIEW OF NUREG 1398: ENVIRONMENTAL ASSESSMENT FOR FINAL ROLE A LICENSE APPLICATON FOR A LOW-LEVEL RADIOACTIVE ON NUCLE AR POWER PLANT LICENSE RENEWAL Rnal Report.

WASTE DISPOSAL F ACILITY.

NUREG 1401 DRFT FC: REGULATORY ANALYSIS FOR GENERIC NUREG 1293 RO1: QUALITY ASSURANCE GUIDANCE FOR A LOM ISSUE 23 REACTOR COOLANT PUMP SEAL FAILURE. Draft Report LEVEL RADOACTIVE WASTE DISPOSAL F ACILITY.

For Comment.

NUREG 1375 V02: Saf ETY EVALUATON REVIEW OF THE PROTO-NUREG-1407. PROCEDURAL AND SUBMITT AL GUIDANCE FOR IN-TYPE LICENSE APPLICATON SAFETY ANALYSIS DIVOUAL PLANT EXAMINATON OF EXTERNAL EVENTS (IPEEE)

REPORT Belowgrouad Vault FOR SEVERE ACCIDENT VULNERABILITIE$ hnal Report

NRC Originating OrgtnitatlOn Index (Staff RepoFts) 93 NUREG 1421 AtGULATORf ANALYS!$ FOR THE RESOLUTION OF DtvisiON OF OPE RATONAL LVENTS ASSESSME NT (PO91670411)

OtNE RIC ISSUE 130 E S$f NTIAL SERVICE Vv ATER SYSTLM NVHLG 14M Vt DRF FE 6T ANDARD TLLHNCAL SPLCJ CATONS P AltVRES AT MULTI-UNIT sites BABCOCK AND WitCOK PLANTS Spoofwatons Draft Repo4 For NURE G 1428 ANALYtas Of PVDLIC COMME NTS ON THE PRO-Cornment POstD RULE ON NUCLE 488 POWE R PLANT LICENSE AENiiWA(

NUREG 1433 V2 DRF FC ST ANDARD TECHNICAL (,PECIFICATONS NUREG 1437 Vt DRF FC 6f NC RfC ENVIRONME N1 AL IMPAC*

BAfiCOCK AND WILCOx PLANTS Deses (Secbons k 0. W 3) Drah ST ATE ME NT FOR LICE Nbt RENEWAL OF NUCL E Ae neport f or Comment PL ANTS Main Ret.M Dra t Repor1 f or Comment NURlG 1430 V3 DRF FC STANDARD TECHNCAL SPECIFICATONS r

NUREG 1437 V2 D4F FC. GE NERC f NVIRONMENT AL IMPACT BABCOCK AND WILCOX PLANTS Bases (Srtons 3 4 3 9) Draft ST ATE MENT FOR LtCENSE RENEWAL OF NUCLEAR Reprt For Comrunt PL ANT S Atiperv$ces Dren Repor1 F or Comment NURtG 1431 VI DAF FC ST ANDARD TECHNICAL SPECIFICATIONS NUREG-1440 DRFT FC REGULAlonY ANALYS'S OF PROPOSED WE911NGHOUSE PLANTS. Specrficatons Draft Report For Com.

AME NDMENTS TO REGUL ATONS CONCERNING THE ENv.?ON.

rnent MENT AL REVIEW FOR RENEWAL Or f4UCLEAR POWE R PLAJT NURE G 1831 V2 DAF FC: ST ANDARD 1ECHNCAL SPECIFCATIONS OPERAtlNG LicENbEB DraN Report For Comment WESTINGHOUSE PLANT S Basca (S6 : tons 2 0 3 3) Dra't Retort For NUREG 144$ HEGVLAtORY ANALYSIS FOR THE RESOLUTION OF Comment.

GENERIC SAFETY ISSUEJ9 BOLTING DEGRADATON OR F All.

t@t G.1431 V3 DRF FC: STANDARD TECHNICAL SPECIFCATONS UAE IN NUCL E AR POWE R PLANTS WEONGHOUSE PLANT S Bases (Sectons 3 4-3.9). Draft Report For DIVISON OF SYSTEMS RESE ARCH {ENT R13KS )AN ASSESSVENT OST 880717 Comment NUREG 11h0 v03. SEVERE ACCI NUREG 1432 Vt DAF FC ST ANDARD TECHNICAL SPECIFICATIONS FOR FIVE U S= NUCLEAR POWER PLAN 1S Appendeces D Arvf COMDUSTION ENGINEERING PLANTS Specifvahons Drttt Retort E Tmai Report For Comment PROBAfilLISTIC RISK ANALYS'S httANCH (880717 910R?9)

NUnt G 1432 V2 DRF FC: ST ANDARD TECHNICAL SPECIFICATONS f4UREG/CR 6639 UNCE R f AN f f EVAL UATION METHODS FOR COMBUSTON ENGINE.ERING PLANTS Bases (Sectone 2 0 WASTE PACK AGE PERFOWM4CE ASSESSMENT, 3 3; pg,q poport F or Comment NUREG 1432 V3 DAF FC. STANDARD TECHNCAL SPECIFICATONS U LEA FEA ECUL Di T

COMBUSTON ENGINEE RING PLANTS Bases (Sectons 3 4 q

3 9) Drah Hoport For Comment N

O O ?? R06 OWNERS OF NUCLE AA POWER PL ANTS NUREO.1433 V1 DRF FC STANDARD TECHNCAL SPECIFICATONS NURIG-1$69 PREAPPUCATON SAFETY EVALUATION REPORT GENERAL ELECTRC UNITS, BWR/4 Specstcahons DrnN Report Fi THE UM ADVANCED FAST REACTOR (SAFR) UOulD NU EG V2 DRF F C. ST ANDARD TECHNCAL SPECiclCATIONS NUREG 1412 FOUNDATION FOR THE ADEOUACY OF THE LICENS, GENERAL ELECT RIO UNITS, BWR/4 Dates (Sections 2.0

• ING BASES A Supplement To The Statement Of Cor+darttsons For 3 3) Daft Regert For Comment.

The Rule On Nuclear Power Plant License Renewal (10 CFR Part NUREG 1433 V3 DAF FC: ST ANDARD TECHNICAL SPECIFICATIONS

$4, r,nal Report GENERAL ELECTRIC UNI 18, BWR/d Danes (Sectons 34 PROGRAM MANAGEMENT POUCY DEVELOPMENT & ANALYSIS 310) Draft Report For Comment ST AFF (POST 870411)

NUREG 1434 V1 DRF FC: STANDARD TECHNICAL SPECIFICATONS NUREG.1436 S01-ST ATUS OF SAFETY ISSUES AT LICENSED GENERA' ELECTRIC P ANTS, BWR/6.SpecatcphonsDaft Report L

POWER PLANTS TMi Acton Plan Requirements Unresolved Safety For Comment issues Ger. enc Safety Isans NUREG 1434 V2 DRF FC STANDARD TECHNCAL bPECIFICATONS NUHEG 1436 V01 ST ATUS OF SAFET" ISSUES AT LCENSED GENERAL ELECTRIC PLANTS, BWR/6 Dases (Souore 70 POWER PLANTS TMI Action Plan Requirements 3 3) Draft Report For Comment 4UREG 1436 V02: STATUS OF SAF ETY ISSUES AT LICENSED NUREG 1434 V3 DRF FC. ST ANDARD TECHNICAL SPECIFICATONS POWER PLANT 8 Urresolved Safety issues GENERAL ELECTRIC PLANTS, BWR/6 Danes (Sections 3 4 NUREG-1435 V03. ST ATUS OF SAFETY ISSUES AT LICENSED 310) Drah Retort For Comment POWER PLANTC Genanc Safety issues DIVISION OF REACTOR INSPECTON & SAF EGUARDS (POST DIVtt DN OF REACTOR PROJLCTS.141 (POST 870411) 8704 t1)

NUREG 0847 S06 SAFETY EVALUATION REPORT BELAFED TO huREG 0040 V14 N04 LICENSEE CONTRAC10R AND VENDOR IN-THE OPERATON OF WATTS BAR NUCLEAR PLANT UNITS 1 AND SPEC 180N STATUS REPORT. Qarierty Report, October-December 2 Dor +et Nos 50 390 And S0-391(Tennessee Valiev Authont '

itigo (WNte Book)

NUREG 0547 507; SAFETY EVALUATON REPORT RELATED TO NUREG 0040 V15 N01: LICENSEE CONTRACTOR #ND VENDOR IN-THE OPERATION OF WATTS DAR NUCLEAR PLANT, UNITS 1 AND SPECTION STATUS REPORT. Quarter'y Report, January-March 2 Docket Nos 60 390 And 50491 (Tennessee Valley Authonty) 1991 (WNte Book)

NUREG 1232 V03 S07 SAFETY EVALUATION REPORT ON TEN-NUREG 0040 V15 NO2. LICENSEE CONTRACTOR AND VENDOR IN-NESSCE VALLEY AUTHORITY. BROWNS FERRY NUCLEAR PER-SPECTION STATUS REPORT, Quaderly Report,Apnt-June FORMANCE PLA. Arowns Ferry Unit 2 Restart 1991 (White Book)

NUREG 1382. SAFE'Y EVALVATON REPORT RELATED TO THE NUREG 0040 V15 NO3 LICENSEE CONTRACTOR AND VENDOR IN-FULL. TERM OPERATING LICENSE FOR OYSTER CREEK NUCLE-SPECTION STATUS REPORT Qaarterly Report.JulPSeptember AR GENERAflNG ST ATION Docket No 50 219 (Genera! Public Ubla 1991 (WNte Book) tes Nuclear Coro et al)

NUREG 1307. AN ASEESSMENT OF DESIGN CONTROL PRACTICES DIVISION OF RE ACTOR PROJECTS. IlUV V (POST 901216)

AND DESIGN RECONSTITUTION PROGRAMS IN THE NUCLEAR NUREG-0675 $34: SAFETY EVALUAtl6N REPORT RELATED TO POWER (NDUSTRY.

THE OPERATON OF DlADLO CANYON NUCLEAR POWER DIVISON OF RADIATION PROTECTON & EMERGENCY PREPARED-PLANT, UNITS 1 AND 2. Docket Nos to276 And 50 323(Pacific Gas NESS (POST 670411)

And Electric ComF.anvl NUREG 1301: OFFSITE DOSE CALCULATON MANUAL GUIDANCE:

DIVISlON OF ADVANCEb REACTORS & SPECIAL PROJECTS (POST STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR PRES-NU EG 413-SAFETY EVALUATON REPORT RELATED TO THE PRELIM' NARY DESIGN OF THE STANDARD NUCLEAR STEAM NUREG-1302 OFFSITE DOSE CALCULATION MANUAL GVIDANCE:

SUPPLY REFERENCE SYSTEM,RESAR SP/90 Docket No. 60-STANDARD RADOLOGICAL EFFLUENT CONTROLS FOR Boll.

601 (West nghouse Electnc Corporation, Inc )

ING WATER REACTORS. Generic Letter 69-01, Supplement No 1.

NUREG-1429 DAFT FC. ENVIRONMENTAL STANDARD REVIEW RISK APPUCATON BRANCH PLAN FOR THE REVIEW OF LCENSE RENEWAL APPLICATONS NU*tEGICR-6692 GENERIC RISK INSIGHTS FOR GENERAL ELEC-FOR NUCLE AR POWER PLANTS Dra't Re For Comment TRIC BOILING W ATER RE ACTORS DIVISION OF REACTOR PROJECTS IlVVl & SPECIAL PROJECTS DIVISON OF Lt ENSEE PERFORMANCE & QUALITY EVALUATION (870411 9012 (post $704gt NUREG-1443 SAFETY EVALUATION REPORT RELATED TO THE NUREG-1214 R07; HISTORICAL DATA

SUMMARY

OF THE SYSTEM-FULL TERM OPERATING LCENSE FO9 SAN ONOFRE NUCLEAR ATIC ASSESSMENT OF LICENSEE PERFORVANCE GENERaiTING STATON, UNIT 1. Docket Nn 50-206 (Souths:n Cak-NUREG-1214 Roe HISTORCAL DATA

SUMMARY

OF THE SYSTEM-tome Edisoh Company And San Diego Gas And Electnc Company)

ATIC ASSESSMLNT OF LICENSEE PERFORMANCE.

&%W!6 D tib% p (IL F e

A e

l 1

NRC Originating Organization index (International Agreements)

This index lists those NRC organi2ations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s). If further information is j

cseded, refer to the main citation by NUREG number.

There were no NUREG/lA reports for 1991 D

(

95

M La B

1 I

l NRC Contract Sponsor index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropria'e. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) pre 3ared by that organi-2ation. If fmher information is needed, refer to the main citation by the MUREG/CR number.

EDO. OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG'CR 4735 V07: EVALUATION AND COMPILATION OF DOE OATA WASTE PACKAGE TEST DATA. Biannual Report February July OWICE FOR ANALYSIS & EVALUATON OF OPERATIONAL DATA. 01-198g RECTOR NUREG/CR 5522: A COMPARISON OF PARAMETER ESTIMATION NUREG/CR 2000 V09N12: LICENSEE EVENT REPORT (LER)

AND SENSITIVITY ANALYSIS TECHNIQUES AND THEIR IMPACT ON NE EERTAW W @M WAM M GR N NU EG/

V10 N1 L EN E E ENT REPORT (LER)

CNEE EVENT REPORT (LER)

NL E C 10 2 NU C 553L APPROACHES FOR THE VALIDATION OF COMPILATION For Month Of Febru 1991.

MODELS USED FOR PERFORMANCE ASSESSMENT OF HtCH-NUREGICR-2000 V10 N3. LICENS E EVENT REPORT (LER)

LEVEL NUCLEAR WASTE REPOSITORIES.

COMPILATION For Month Of March 1991.

NUREG/CR5639' UNCERTAINTY EVALUATON METHODS FOR NUREG1CR-2000 V10 N4. LICENSEE EVENT REPORT (LER)

WASTE PACKAGE PERFORMANCE ASSESSMENT.

COMPILATION For Month Of Apnl 1991.

DIVISION OF LOW-LEVEL WASTE MANAGEMENT & DECOMMISSION-NUREGICR2000 V10 N5 LICENSEE EVENT REPORT (LER)

ING (POST 870413)

COWILATON For Montn Of May 1991 NUREG/C45432 V01: RECOMMENDATIONS TO THE NRC FOR NUREG/CR-2000 VIO N6 LICENSEE EVENT REPORT (LER)

SOIL COVER SYSTEMS OVER URANIUM MILL TAILINGS AND NU E /

10 7

N EVENT REFVRT (LER) p NU G/ N 10 8 CENSEE EVENT REPORT (LER)

S S

06 WM m MWE N COMPILATION For Month Of A-ust 1991 NUREG/CR-2000 V10 N9 LIC NSEE EVENT REPORT (LER)

LOW-LEVEL RADtOACTIVE WASTES. Laboratory And Feld Tem COMPILATION For Month Of Septernher 1991.

For Soil Covers.

NUREG/CR-2000 V10N10: UCENSEE EVENT REPORT (LER)

NUREG/CR 5432 V03: RECOMMENDATONS TO THE NRC FOR COMPILATION For Month Of October 1991.

SOIL COVER SYSTEMS OVER URANIUM MILL TAIUNGS AND NUREG/CR4000 V10N11. LICENSEE EVENT REPORT (LER)

LOW-LEVEL RADIOACTIVE WASTES. Constructen Metrods And COMP LATON For Month Of November 1991.

Guidance Cor Seahng Penetrations in Sod Covert OlVISION OF SAFETY PROF. RAMS (POST 870413)

NUREG/C45539: A SELF-TEACHING CURRICULUM FOR THE NRC/

NUREGICR-4674 Vl3: PRECURSORS TO POTENTIAL SEVERE SNL LCW-LEVEL WASTE PERFORMANCE ASSESSMENT METH-CORE DAMAGE ACCIDENTS 1990 A STATUS REPORT. Main OOOLOGY.

R - And Appenda A-NUREGICR5713. A REVIEW OF ENVIRONMENTAL CONDitlONS NUR.GiCR-4874 V14: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS 199U A STATUS REPORT.Appandixes AND PERFORMANCE OF THE COMMERCIAL LOW LEVEL RADIO-ACTIVE WASTE DISPOSAL FACluTY NEAR SHEFF!ELDlLLINOIS.

- NURE 45456-ANALYSIS OF FLOW STRATIFICATION IN THE SURGE L!NE OF THE COMANCHE FEAK REACiOR' A

S T

C E A O CT W DS POCAL FACILITY NEAR SHEFFIFLD ILLINOIS.

EDO OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM NUREG/C45737: HYDAOGEOLOGIC PERFORMANCE ASSESS-(POST 861109)

MENT ANALYSIS OF THE COMMERCIAL LOW LEVEL RADOAC-OFFICE OF INFORMATION HESOURCES MANAGEMENT (POST TIVE WASTE DISPOSAL FACILITV NEAR WEST VALLEY,NEW 890205)

YORK.

NUREG/CR4907 V09: RADIOACTIVE MATERIALS RELEASED FROM NUREG/CR-5773 SELECTON OF MODELS TO CALCULATE THE NUCLEAR POWEF, PLANTS Annual Report 1988 LLW SOURCE TERM.

EDO. OFFICE OF HUCLEAR MATERIAL SAFETY & SAFEGUARDS EDO. OFFICE OF NUCLEAR REGUuTORY RESEARCH (POST 820405)

DIVISON OF SAFEGUAROS & TRANSPORTATON (POST 870413)

OFFICE OF NUCLEAR REGUMTORY RESEARCH (POST 860720)

NUREG/CR56B9. MEDtCAL SCREEffNG REFERENCE MANUR NUREG/C45550: PASSIVE NONDESTRUCTIVE ASSAY OF NUC8 E FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE FACIUTIES AR MATERIALS POSSESSING FORMULA QUANTITIES OF SPECIAL NUCLEAR MA-TENALS.

OlV)SION OF ENGINEERING (POST 87041M tiUREG/C43145 VOS GEOPHYSIC# AVESTIGATONS OF THE NUREG/CR-5690. PHYSICAL FITNESS TRAINING REFERENCE WESTERN OHIOlNDIANA REGIC mual Report October 1989 MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE Sectember 1990 FACILITIES POSSESSING FORMULA QUANTITIES OF SPECIAL NUREG/C442'9 V07 N1. HEAVY SECTON STEEL TECHNOLOGY

^

• NUP /CR 5 7P K GING SUPPUER INSPECTION GUIDE ggg NUREd/C44219 V07 N2: HEAVY SECTION STEEL TECHNOLOGY

/

I N USION E TO SY T S.

NUAEG/C45723: SECURITY SYSTEM SIGNAL SUPEFu/IStON.

PROGRAM. Semiannual Progress Report for Apnt-September 1990.

NUREG/CR-5734: RECOMMENDATIONS TO THE NRC ON ACCEPT, NUREG/CR-4231 SELECTON OF SILICEOUS AfMREGATE FOR ABLE STANCARD FORMAT AND CONTENT FOR THE FUNDA.

CONCRETE.

MENTAL NUCLEAR MATERIAL CONTROL (FNMC) PMN R E, NUREL CR-4269-MODELS OF TRANSPORT PROCESSES IN CON-QUIRED FOR LOW ENRICHED URAN)UM ENRICHMENT FACIU, CRETE.

TIES.

NURdG/C4429i BONO STRENGTH OF CEMENTITIOUS BOREJ DIVISON OF HIGHLEVEL WASTE MANAGEMENT (POST 8W13)

HOLE PLUGS IN WELDED TUFF.

NUREG/C43964 V02-TECHNIQUES FOR DETERMINING PROB-NUREG/CR-4302 V02: AGING AND SERVICE WEAR OF CHECK ADIUTIES OF ENENTS AND PROCESSES AFFECTING THE PER.

VALVES USED IN ENGINEERED SAFTTY FLATURE SYSTEMS OF FORMANCE OF GEOLOGIC RLr'OstTORIES.SuoQested Approach-NUCLEAR POWER FLANTS Agmg Assessments And Monttonng es Method Evaluations.

97

98 NRC Contract Sponsor Index NUREG/CR4469 V10 NONDESTRUCTIVE Ex AMINATION (NDE) RE.

NURE,DCR.56te USER S MANUAL FOR THE NEFTRAN 11 COM-UABILITY FOR INSERVICE INSPECTION OF LIGHT WA1ER PUTER CODE RE ACTORS 6emi-Annual Report Aprd September 1989 NUREG/CR-561k THE IMPACT OF THERMAL AGING ON THE NUREG/CR4513. ESitMAT ON OF FRACTURE TOUGHNESS OF FLAMMABluTY OF ELECTRIC CABLES CAST STAINLESS STEELS DUP NG THERMAL AGING IN LWR NUREG/CR5628 PENNSYLVANIA SE!SM C MON 110 RING NET-SYSTEMS.

WORK AND RELATED TECTONIC STUDiLS Final Report NUREG/CR 4599 V01 Nt SHORT CRACKS IN PIPING AND PIPING NUREGICR 5645: ACOUSTIC EM:SSION/ FLAW RELATIONSHIPS WELDS Samannual Report March September 1990 FOR INSERVICE MONITORING OF LWAS.

NUREG/CR4659 VD4. SEISMIC FRAGluTY OJ NUCLEAR POWER NUREG/CRS648, TRANSPORT CALCULATIONS' OF NEUTRON PLANT COMPONENTS (PHASE 11) A Frag *ty Handtook On E$t-TRANSMISSION THROUGH STEEL USING ENDF/B V.REVISEO sen Components.

ENDF/B-V,AND ENDF/B-VI 1RON EVALUATIONS NUREG/CR 4*67 V09 ENVIRONMENTALLY ASSfSTED CRACKING NUREG/CR-5651 AN INVESTIG ATION OF CHACK Tip STRESS IN LIGHT WATER REACTORS Semiannual Report Apr4 September FIELD CRITER A FOR PREDICTING CLEAVACECRACK INtTI-1983 ATION NUREG/CR 4667 V10. ENVIRONMENTALLY ASSISTED CRACKING NUREG/CR-5655: SUBMERGENCE AND HtGH TEMPERATURE IN UGHT WATER PEACTORS Semannual ReportOctober 1989 -

STEAM TESTING OF CLASS 1E ELECTRICAL CABLES.

March 1990 NUREG/CR-5660 STATIC AND SIMULATED SEISMIC TESTING OF NUREG/CR 4667 ir - : ENVIRONMENTALLY A%ISTED CRACKING THE TRG-7 THROUGH 16 SHE AR WALL STRUCTURES 11 LIGHT WATER REACTORS. Semiannual ReportnprtSeptember NUREG/CRS672 V00 CHARACTERISTICS OF LOW-LEVEL RADIO-1990.

ACTIVE WASTE. Ducontamination Wsste Annual Report For Fiscal NUREG/CR4667 V12. ENVIRONMEN4LLY ASS:STED CRACKING Year 1940 IN UGHT WATER REACTORS. Sem@,nual ReportOctober 1990 -

NUREG/CR 5681: LOW-LEVEL WASTE SOURCE TERM MODEL DE, March 1991.

VELOPMENT AND TESTING NUREG/CR4670- RAD'ONUCLIDE DISTRIBUTIONS AND MiGRA-NUREG/CRS683; LABORATORY TESTING OF CEMEhT GROUTING TION MECHAN!SMS AT SHALLOW LAND BURIAL SITES FKal OF FRACTURES lN WELDED TUFF.

~

Report Of PNL Research inveshgations On The Distnbution, Mgra-NUREG/CR-5684: ANALYSES AND FIELD TESTS OF THE HYDRAU-tion. And Containment Of Radionuchdas At Maxey Flats. Kentucky.

UC PERFORMANCE OF CEMENT GROUT BOREHOLE SEALS-NUREG/CR4744 V04 N1, LONG TERM EMBRITTLEMENT OF CAST NUREG/CR 5686. EFFECTIVENESS OF FRACTURE SEALINu WITH DUPLt x STAINLESS STEELS IN LWR S fSTEMS Semiannual BENTQNTTE GROUTWG.

A ReportOctober 1988 March 1909 NUREG/CR 5688: MECHANICAL CHARACTER 12ATION OF DENSELY G

NUREQ/CR-47A4 V04 N2 LONG TERM EMBWTLEMENT OF CAST WEl.DED APACHE LEAP TUFF.

DJPLEX STAINLESS STEELS 1N LWR SYSTEMS Semannua!

NsHEG/CR-569& IRRADIATION EFFECTS ON CHARPY IMPACT ReportApni-September 1989 AND TENSILE PROPERTIES OF LOW UPPERSHELF WELDS,HSSI NUREGICR4744 V05 Nt LONG-TERM EMBRITTLEMENT OF CAST SER!ES 2 AND 3 DUPLEX STAINLESS STEELS IN LWR SYST EMS SerWannual NUREG/CR5697: USE OF THICKNESS REDUCTION TO EWMATE Report, October 1989. March 1990 VALUES OF K.

NUREG/CR-4744 V05 N2: LONG-TERM EMBRITTLEMENT OF CAST NUREG/CR-5701 A PERFORMANCE ASSESSMENT METHOOOLO-DUPLEX STAINLESS STEELS FN LWR SYSTEMS Sermannual GY FOR HIGH-LEVEL RAC;OACTIVE WASTE DISPOSAL IN ReportApnt September 1990 UNSATURATED'FRACTUAED TUFF.

NUPtG/CR4816 Rot: PR-EDB: POWER REACTOR EMBRITTLE-NUREGICR5703= LOWER-ROUND INITIATION TOUGHNESS WITH a MENT DATA BASE, VERSION 1. Program bescnption MODIFIED CHARPY SPECIMEN NUREG/CR4867. RELAY TEST PROGRAWSenes t Vibration Tests NUREG/CR5706: POTENTIAL SAFETY RELATED PUMP LOSS: AN NUREG/CR5128: EVALUATION AND AkFINEMENT OF LEAlbRATE ASSESSMENT OF INDUSTRY DATA.NRC Dulletin 88-04.

I NU

/CR 4 RI ICAL ASSESSMENT OF SELWC AND Gio.

NUREG/CR-5711 ASSEMMENT OF LWCERTAINTIES IN MEASURE-MECHANICS UTERATURE RELATED TO A HIGRLEVEL NUCLEAR MENT OF Ph IN HOSTILE ENVIRONMENTS CHARACTERIST;C OF,

WASTE UNDERGROUND REPOSITORY NUCLEAR REPOSITORIES.

EW NSM WDEL MAM AT NE W GM NUREO/CR5495-CONCEPTUAUZATION - OF A HYPOTHETICAL T

^

EPOS M SITE W ggRE / R 27: CHLORIDE lON DIFFUSION P' LOW WATERTO-SA R TEDF ACTURED UFF S

M P ST DCM3D' A DUAL CONTINUUM, THREE-OlMEN.

ggh D NUREG/CR 5536:

StONAL, GROUND WATER FLOW CODE FOR UNSATURATED' FRACTURED. POAOUS MEDIA.

VESSEL AND 31 PING J-R DATAc NUREG/CR-5546 AN INVESTIGATION OF THE EFFECTS OF THER-NUREG/CR5T. APPROACHES TO LARGE SCALE UNSATURATED MAL AGtNG ON THE FIRE DAMAGEABILITY OF ELECTRIC.

FLOW IN METEROGENEOUS, STRATIFIED, AHD FRACTURED CABLES OEOLOGIC MEDIA-NUREQ/CR 5550 TWO NEW NOT TECHNCUES FOR INSPECTION NUREG/CR 5748. RADIATION EMBRITTLEMENT OF THE NEUTRON OF CONTAINMENT WELDS BENEATH COATINGS Final SHIELD TANK FROM THE SHIPPINGPORT RE ACTOR.

- ReportOctober 1989 March 19%

NUREG/CR5749: TECTONIC DEFORMATION REVEALED IN BALD-NUREG/CR5555: AGING ASSESSMENT OF THE WESTINGHOUSE CYPRFSA TREES At REELFOOT' LAKE. TENNESSEE.

PWR CONTROL ROD DRIVE SYSTEM NUREG/CR 5'57; VERIFICATION OF PIPING RESPONSE CALCULA.

NUREG/CR-5558: GCNERIC IS3UE 87: FLEXIBLE WEDGE GATE TION OF SMAf;S CODE WITH DATA FROM SEISMIC TESTING OF VALVE TEST PROGRAM. Phase il Results And Analysis.

AN IN PLANT PIPlNG SYSTEM.

NUREG/CR 556t ANALYSIS OF BELLOWS EXPANSION JOINTS IN

.NUREG/CR5760 REPORT ON ANNEALING OF THE NOVOVORON-THE SEQUOYAH CONTAINMENT.

EZH UNIT 3 REACTOR VESSEL IN THE USSR NUREG/CR 5577; EXTENSION AND EXTRAPOLATION OF J-R NUREWCR576L THE BEHAVIOR OF 3 HALLOW FLAWS IN REAC-CURVES AND THEIR APPLICATION TO THE LOW UPPER SHELF TOR PRESSURE VESSELS.

YOUGHNESS ISSUE NUREG/CR-577A GLOBAL POSIT:ONtNG SYSTEM MEASURE-8 'G/CR 5580- UNSATURATED - FLOW AND TRANSPORT MENTS OVER A STRAIN MONITORING NETWQRK IN THE EAST-

'iUGH FRACTURED ROCK RELATED TO HIGH-LEVEL W ASTE ERN TWO-THl9DS OF THE UNITED STATES.

heWOSITORIES. Final Report Phase til NUREG/CR-5778 V01. NEW YOPK/NEW JERSEY REGIONAL SElS-NUREG/CR5585: THE - HtGH LEVEL VlBRATION TEST MIC NETWOAK. Annual Recort For Apnl 1909 - March 1990.

PROGRAM Firial Report.

' DIVIS:ON OF REGULATORY APPLICATIONS (POST 870413)

NUREG/CR-5592 ANALYTICAL STUDIES OF TRANSVERS5 STRAIN NUREG/CR3444 V08. THE IMPACT OF LWR DECONTAMiNATIONS EFFECTS ON FRACTURE 10VGHNESS FOR CIRCUMFERENilAL.

ON SOLIDIFICATION. WASTE OtSPOSAL AND ASSOrlATED OC-LY ORIENTED CRACKS CUPATIONAL EXPOSURE. Effects.- Of Campositen On The NUREG/CR5598: IMMER3 ION STUDIES ON CANDIDATE CONTAIN-Strer.gth.Swemng. And Water. immersion Properties of Cernent-Solidt-ER ALLOYS FOR THE (UFF REPOSITORY.

hed lonOchange Resen Wastes NUREG/CR5600 EFFECTS OF PH ON THE RELEASE OF RAD!ON.

NUREGICC 3469 V00: OCCUPATIONAL DOSE REDUCTION AT NO-UCUDES AND CHELATING AGENTS FROM CEMENT-SOUDHED CLEAR POWER PLANTS: ANNOTATED BibuGGRAPH" OF SE-DECONTAMINATION ION-EXCHANGE RESINS CN.LECTED FROM LECTED READINGS IN RADIATION PROTECTION AND ALARA.

OPERATING NUCLEAR POWER STATIONS NUREG/CR-4214 R192At HEALTH EFFECTS MODELS FOR HU-NUREG/CR 5614: PERFORMANCE OF INTACT AND PARTIAll v ET-CLEAR POWER PLANT ACCIDENT : CONSEQUENCE GRADED CONCRETE BARRIERS IN UMITING FLUID FLOW ANALYSTS Moofcations 01 Models Resutting Frorn Recent Reports

t NRC Contract Sponsor Index 99 On Health Ettocts Of lonizing Radiation. Low LET RadiahonPart 11' DIVISION OF SYSTEMS RESEARCN (POST BB071M Scentific Bases For Hoarth-NUREG/CR3916: PRESSUHt2ED MELT LJECTION INTO WATER NUREG/CR4444: RADIAff0N SAFETY ISSUES RELATED TO RA-POOLS DiOLABELED ANTIBODtES NUREG/CR-4063: #N INVEShGATON OF CORE UOUfD LE' VEL DE.

NUREG/CR-4918 V05: CONTROL OF WATER INFILTRATON INTO PRERSION IN SMALL BREAK LOSS-OF COOtANT AOCIDENTS.

NEAR SURFACE LLW DISPOSAL UNITSProgress Report On Field NUREG/CR-4551 V2 RIP 2: EVALUATION OF SEVERE ACCIDENT ExPentnents At A Hurmd Region Site.Beltsville. Maryland RISKS.

QUANTIFICATION OF MAJOR INPUT NUREG/CR-5'39: DOSE.REDUCTON TECHNiOVES FOR HIGH' PARAMETERS Experts' Deteranate Of Containment Loads And 9

s DOSE WORAER GROUPS IN NUCLEAR POWER PLANTS MoPen Core Containment 6nterneten issues NUREG/CR 5343-RADONUCUDE CHARACTER 12ATION OF REAC-NUREG/CR-5282: ESTIMATON OF CONTAINMENT PRESSURE p

TOR DECOMM!SSIONING WASTE AND SPENT FUEL ASSEMBLY LOADING DUE TO DnECT CONTAINMENT HEATING FOR THE HARDWARE Progren RepM ZION PLANT NUREG/CR 5352 H01: VAM20 VARIABLY SATU9ATED ANALYSIS NUREG/CR-5300 V01: INTEGRATED RELIABILITY AND RISK ANAL.

MODEL IN TWO DIMENSIONS, Vermon 6.2 With Hysteresis And YSIS SYSTLM (IRRAS) VERSION 2 5 Reference Manual.

Chain Decay Transport Documentahon And User's Guid*

NUREG/CR-530t RADIONJCLIDE BEHAVOR IN THE ENVIRON-NUREG/CR 5464 ANION RETENTION IN SOll: POSSIBLE APPLICA-MENT TION TO REDUCE MITGRATION OF SURIED TECHNETIUM AND NUREGICR-5312: A THERMODYNAMIC MODFt OF FUEL DISRUP.

IOOiNE A Review-TION IN ST 1.

NUREG/CR 5595 FOHECAST: REGULATORY EFFECTS COST NUREG/CR-5331: MELCOR ANALYSES FOR ACCIDENT PROGRES-ANALYSIS SOFTWARE MANUAL Version 3 0 SION ISSUt S I

NUREG/CR-5620: THATCH A COMPUTER CODE FOR MODELUNG THERMAL NETWORKS OF HIGRTEMPERATU"E GASCOOLED NUREG/CR 5345: FISSION PROObCT MLEASE AND FUEL BEHAV.

10A OF IRRADIATED UGHT WATER REACTOR FUEL UNDER NURE /CR S ON PRODUCT PLATEOUT AND UFTOFF IN N RE CR 77 R V TECR tC X SA ATH-NU G 5 SYST MA A R TO REPETITIVE FAIL-WAY MODELS IN MACCS AND SFVERAL OTHER WELL-KNOWN URES PROBABILISTIC RISK ASSESSMEfd MODEL!L NUREG/CR-5866: PROGRAMMATIC ROOT CAUSE ANALYSIS OF NUREG/CR-5395 VU1: MULTILOOP INT EGRAL SYSTEM TEST MAINTENANCE PERSONNEL PERFORMANCE PROBLEMA (MIST). FINAL REPORT.Surnmary.

NUREr/CRS695: A PROCESC FOR RISK FOCUSED MAINTE.

NUREG/CR5423. THC PROBABluTY OF UNER FAILURE IN /,

NANCE MARK.I CONTAINMENT, NUREG/CR-5712: MORECA: A COMPUTER CODE FOR SIMULATING NUREG/CR-5481 DATA

SUMMARY

REPORT FOR FISSION PROD-

/

MODULAR HiGH-TEMPERATURE GAS-COOLED REACTOR CORE UCT RFLEASF TEST Vb4.

\\

HEATUP ACCIDENTS, AJREG/CR 5518. QUAUTY ASSURANCE PP~CEDURES FOR THE NUREG/CR-5740: NEW GAMMA RAY BUILDUP FACTOR DATA FOR CONTAIN SEVERE REACTOR ACCIDENT COMPUTER CODE.

POINT KERNEL CALCULATONS: ANS-6.4.3 STANDARD REFER.

NUREG/CR-5525: HYDROGEN-AIR-DILVENT DETONATION STUDY ENCE DAin FOR NUCLEAR REACTOR SAFETY ANALYSES NUREG/CR-5765: SPARC-90 A CODE FOR CALCULATING FISSION NUREG/CR-5531: MELCOR 18 0: A COMPUTER CODE FOR NUCLE-PRODUCT CAPTURE IN SUPPRESSION POOLS AR REACTOR SEVERE ACCIDENT SOURCE TERM AND RISK AS-NUREG/CR5768 ICE CONDENSER AEROEOL TESTS SESSMENT ANALYSES.

NUREG/CR5794. GROUND-WATER FLOW AND TRANSPORT MOD-NUREG/CR-5538 VO1: INFLUENCE OF ORGANIZATIONAL FACTORS ELING OF THE NRC LICENSED WASTE DISPOSAL FACIUTY, ON PERFORMANCE REUABluTY.Overviaw Ard Letailed Methodo-WEST VALLEY, NEW YORK-logcal Developrnent NUREG/CR5795-VAUDATION AND TESTING OF THE VAM20 NUREG/CR$543: A SYbTEMAllC PROCESS FOR DEVELOPl J COMPUTER CODE.

AND ASSESSING ACCOENT MANAGEMENT Pl.ANS.

NUREGiCR-5798: PILOT PROGRAM TO ASSESS PROPOSED BASIC NUREG/CRS60s-A REVIEW OF THE SOUTH TEXAS PROJECT QUALITY ASSURANCE REQUIREMENiS IN THE MCDICAL USE PROBABluSTIC SAFETY ANALYSIS FOR ACCIDENT FREQUENCY OF DYPRODUCT MATERIAL ESTIMATES AND CONTAINMENT B!NNING OtV!SION OF SAFETY ISSUE RESOLUT'ON (POST 880717)

NUPEG!CR-5611: ISSUES AND APPROACHES FOR USING EQUIP-NUREC!CR-4893: TECHNICAL FINDINGS REPORT FOR GENERIC x

MENT REUABluTY ALERT LEVELS.

$hEF At A YS O

!YRIC ISSUE NW G/

5612: MRADATON MODEUNG W WCAMN N EG/ 5 67 23: RcACTOR COOLANT PUMP SEAL F AILURE A NG A MENEE WWdES MWmi NUREG/CR-5182: SCREENING OF GENERIC SA' ETY ISSUES FOR NUREG/CR 5634: IDENTIFICATON AND ASSESSMENT OF CON +

F UCENSE RENEWAL CONSOFRATIONS TAINMENT AND RELEASE MANAGEMENT STRATEGIES FOR A NUREG/CR 5522 PROCEDUdES GUIDE FOR EXTRACTING AND BWR MARK t CONTAINMENT.

LOAE1NG PROSABluSTIC RISK ASSESSMENT DATA INTO MARD NUREG/CRS641: STUDY OF ODCRATIONAL RnSK4ASED CONFIG.

USING IRRAO 2.5.

UAATION CONTROL NUREG/CR5526: ANALYSIS OF RISK REDUCTON MEASURES AP.

NUREG/CR-5654: CONTAINMENT VENTilvG ANALYSIS FOR THE PUED TO SHARED ESSENTIAL SERVICC WATER SYSTEMS AT SHOREHAM NUCLEAR POWER STATION.

MULTI UNIT SITES.

NUREGICR-5683: RELAP5 THERMAL HYDRAULIC ANALYSIS OF NUREC1CR 5529: AN ASSESSMENT OF BWR MARK 111 CONTAIN.

THE WNP1 PRESSURIZED WATER REACTOR.

MENT CHALLENGES, FAILURE MODE & AND POTENTIAL IM, NUREG/CR-566h INEL PERSONAL COMPUTER VERSION OF PROVEMENTS IN PERFORMANCE.

MACCS 1.5.

NJREG/CR-5565: THE RESPONSE OF BWR MARK lt CONTAIN.

NUREG/CR E368: DATA

SUMMARY

REPORT FOR FISSON PROD-MENTS TO STATION BLACKOUT SEVERE ACCIDENT SE.

UCT RELEASE TEST V1-5.

QUENCES.

NUREG/CR 5670: MULTILOOP INTEGRAL SYSTE8.1 TEST NUREG/CR5571: THE RESPONSE OF BWR MARK til CONTAIN.

(MIST): MIST FACILITY FUNCTIONAL SPECIFICATON.

BENTS TO SHORT TERM STATON BLACKOUT SEVERE ACCp NUREG/CRS677: A UN!FIED INTERPRETATION OF ONE FIFTH TO DENT SEQUENCES.

FULL SCALE THERMAL MlXING EXPERIMENTS RELATED TO NUREG/CR-5623 BW 'JARK li hX VESSEL CORIUM INTEP ACTION PRESSURIZED THERMAL SHOCK.

ANALYSES.

NUREG/CR-5682; SPECIFIC TOPICS IN SEVERE ACCOENT MAN, NUREG/CR-56n PWR DRY CONTAINMENT PARAMETRIC STUC.

AGEMENT.

IES.

NUREG/CR569t: INSTRUMENTATION AVAILADILITY FOR A PRES-NUREG/CR-565& EXTRAN: A COMPUTER CODE FOR ESTIMATING SURIZED WATER REACTOR WITH A LARGE DRY CONTAINMENT CONCENTRATIONS OF TO500 SUBSTANCES AT CONTROL DURING SEVERE ACC'OENTS.

ROOll' AIR INTAKES.

NUHEG/CR5702: ACCIDENT MANAGEMENT INFORMATION NEEDS NUREG/CR5658: FPFP 2: A CODE FOR FO* LOWING AIRBORNE FOR A BWR WITH A MARK I CONTAINMENT.

FISSION PRODUCTS IN GENEr% NUCLEAR PLANT FLOW NUREGICR5707. APPUCATON OF CONTAINMENT AND RELEASE PATHS.

MANAGEMENT TO A PWR ICE CONDENSER PLANT.

NUREG/CRS662-HYDROGEN COMBUSTION. CONTROL,AND NUREG/CR5715-REFEHENCE MANUAL FOR THE CONTAIN 1.1 VALUSIMPACT ANALYSIS FOR PWR DRY CONTAINMENTS CODE FOR CONTAINMENT SEVERE ACC) DENT ANALYSIS.

NUREG/CRS669: EVALUATION OF EXPOSURE UMlTS TO TOX1C NUREG/CR 5728. EXPERIMENTS TO INVESTIGATE THE EFFECT CASES FOR NUCLEAR REACTOR CONTROL ROOM OPERA-OF FUGHT PATH ON DIRECT CONTAINMENT HEATING (DCH)IN TORS-THE SURTSEY TEST FACluTY.The Omited Flight Path (LFP) Tests.

I

(

100 NFIC Contract Sponsor Index NUREU/CA-S732 DAF FC: ODINE CHEMCAL FOAVS IN !WR NUREGICR 5742 V02 FEAS!BluTY ASSESSMENT OF A RISK.

SEVERE ACCIDENTS Draft Report For Comment BASED APPROACH TO TECHNICAL SPECtFICATIONS Main NUREG/CR-5'It: PROBABluTY AND CONS ~OVENCES OF MIS Report LOADING FUEL "I A PWR NUREG/CR-57BO.

SUMMARY

OF A WORKSHOP CN SEVERE ACCl-DIVtSION OF ENGINEERING TECHNOLOGY (POST 890827)

NUREG/CR-5796.

STEAM GENERATOR OPERATING DENT MANAGEMENT FOR BWRS NUREC/CR 5781;

SUMMARY

OF A WORKSHOP ON SEVERE ACCI-EXPERIENCE. UPDATE FOR 1989-1990' &

O! VISION OF REACTOR INSPECTON SAFEGJARDS (POST DENT MANAGEMENT FOR PWRS NUyEG/ R-5758 V01:

NUREG/CR4808. CALCULATON OF ABSORBED DOSES TO FITNESS FOR DUTY IN THE NUCLEAR WATER POOLS IN SEVERE ACCOENT SEOUENCES NUREGICR 5809 DRF CC: AN INTEGRATED STRUCTURE AND POWER INDUSTRY. Annual Summary Of Program Performance SCALING METHODOLOGY FOR SEVERE ACCOENT TECHNICAL Reports.CY 1990 ISSUE RESOLUTION Draft Repor1 For Comment NUREG/CR 5764 FITNESS FOR DUTY IN THE NUCLE AR POWER INDUSTRY.A Review Of The i'nt Year Of Program Performree EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80)

And An Update Of The Techncallasues PHOGRAM MnNAGEMENT, POLICY DEVFLOPMENT & ANALYSlS DIVISION OF RADIATION PROTECTION & EMERGENCY PREPARED-

~

STAFF (POST 8k411)

NESS (POST 8704115 f4UREG/CR-4911: INCENTIVE REGULATION OF NUCLEAR POVTR NUREG/CR-4427. AUXIUARY FEEDWATFR SYSTEM RISK. BASED PLANTS BY STATE REGULATORS-DIVISION OF OPERATIONAL EVENTS ASSESSMENT (POST 87041 INSPECTION OUCE FOR THE BYRON AND BRACWOOO NU^.LE.

NUREG/CR-4666-CLOSEOUT OF IE BULLEllN 84 02. F AILURES OF AR POWER PL ANTS GENERAL ELECTRIC TYPE HFA RELAYS IN USE N CLASS 1E NUREG/CR-4757; UNE LOSS DETERMINATION FOR AIR SAMPLER SYSTEMS NURE R 46 Y"1 Al-GENE RIC COMMUNICATIONS NUREG/CR-5467: RISK-DASED INSPECTION GUCE FOR CRYSTAL RA'F.A UNIT 3 NUCLEAR POWER PLANT.

57t 5 N

G SO O IE DULL E 79-13 CRAC, KING IN NU% L*s-5392; GENERIC RISK INSIGHTS FOR GENERAL ELEL-FE EDWATER SYSTEM PIPING.

lak. P'MUNG WATER REACTORS.

NUREG/CR 5288 CLOSEOUT OF IE BULLETIN 80-06 ENGINEERED NUREG/CR 5761: AUXILIARY FCEDWATER SYSTEM RISK-BASED SAFETY FEATURE (EST) RESET CONTROLS.

INSPEGTION GUIDE FOR THE SALEM NUCLEAR POWER PLANT.

NUREG/CR-5309 CLOSEOUT OF IE DULLETIN 83-07; APPARENTLY NUREG/CR 5763: AUXILIARY FEEDWATER SYSTEM RISK-DASED FRAUDULENT PRODUCTS SOLD BY RAY MILLER.lNC, INSPECTION GUOE FOR THE CALLAWAY NUCLEAR POWER NUREG/CR-5742 V01. FEASiblUTY ASSESWF.NT OF A RISK-PLANT.

BASED APPROACH TO TECHNICAL SPECIFICATIONS Executive NUREG/CA-5764 AUXILIARY FEEDWATER SYSTEM RISK-BASED Summary.

INSPECTION GUIDE FOR THE GINNA NUCLEAR POWER PLANT.

I

Contractor Index T

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

81ST CENTURY INDUSTRIES lM::.

LEVEL RADCACTIVE WASTES. Identification And Ranking Of Soils NLIAEG/C45734: RECOMMENDATONS TO THE NRC ON ACCEPTA, For Disposal Facility Covers.

BLE STAND #

FORMAT e ~ wtENT FOR THE FUNDAMEN.

NUREG/C4b432 V02. RECOMMENDATIONS TO THE NRC FOR SOlt T AL NU' LEAh MATERIAL FNMC) PLAN REQUIRED FOR COVER SYSTEMS OVER URANIUM MILL TAILINGS AND LOW-LOW ENRICHED URAN 1UM L ENT FACILITIES LEVEL RADIOACTIVE WASTES. Laboratory And Field Tests For Sod Covers APPLIED PHYSICS lNC.

NUREG/C45432 V03 RECOO1ENDATIONS TO THE NRC FOR SOIL NUREG/CR-5536 DCM30- A DUAL CONTINUUM. TH"EE-DIMENSON-COVER SYSTEMU OVER URANIUM MILL' TAILINGS AND LOW-AL, GRCJND-WATER FLOW GODE FOR UNSATURATED, FRAC-LEVEL RADIOACTIVE WASTES. Construction Methods And Guidance TURED. POROJS MEDlA.

For Seahng Penetrations in Soil Coers.

ARGONNE NATIONAL LADORATOAY BABCOCK & WILCOX CO.

NUREG/CR4513-ESTIMt. TION OF FRACTURE TCUGHNESS OF NUREG/CR 5395 VOL MULTILOOP INTEGRAL SYSTEM TEST CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-(MIST) FINAL REPORT. Summary N

G/CR-4667 V09-ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS Semannual ReportApnt-September 1989 FAC I Y F N T ON L CCI GATO 1 NUREG/CR4667 VIO-ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTOF4 Semiannual ReportOctober 1989 March BATTELLE HUMAN AFFAIRS RESE ARCH CENTERS NUREG/C44910 INCENTIVE REGULATON OF NUCLEAR POWER P

^

NU G/CR4667 '/11: ENVIRONMENTALLY ASE'STED CRACKING IN NUR R 57 VO F NE DUTY IN THE r40 CLEAR POV/ER N E/R 67 V 2 RO $ ALLY WE R7C INDUSTRY. Annual Summary Of Program Performance Repor%CY GN LIGHT WATER REACTOR 1 Semannual ReportOcwber 1990

• M rch NU G/C4 5784: FITNESS FOR DUTY IN THE NUCLEAR NWER NUREG/CR4744 V04 N1: LONG-TERM EMBRITTLEMENT OF CAST, INDUSTRY.A Review Of the First Year Of Program Performance And DUPt EX STAINLESS STEELS IN LWR SYSTEMS Semannua An upctate Of The Techrucalissues.

Report Ocl0ber 1988 March 1989 NUREG/CR4744 V04 N2: LONG-TERM EMBRITTLEMENT OF CAST BATTELLE MEMORIAL INSTITUTE DUPLEX ETAINLESS STEELS IN LWR SYSTEMS.Semannual NUREG/C44599 V01 NL. SHORT CRACKS IN PIPING AND PIPING Repc%A_ p4eptember 1989 WELD 1Semannual Report March-September 1990.

NUREG/CR4/44 VOS N1; LONG TERM EMBRITTLEMENT OF CAST NUFEG/C46128. EVALUATICN AND REF NEMENT OF LEAK-RATE OUPLEX STAINLSSS STEELS IN LWR SYSTEMS Semant'ual ESTIMATION MODELS.

NRCC

~

CJTTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST N

ERM EMBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semannual LABORATORY ReportApn'i-So;)tember 1990 NUREG 1400 DRFT Frt a!a SAMPt 'NG IN THE WORKPLACE. Draft NUREG/CR-5456 ANALYSIS OF FLOW STRATIFFATON IN THE Repor1 For Com.Tct.

SURGE LINE OF THE COMANCHE PEAK REACTOR.

NUREGICR 4214 RJiAL HEALTH EFFECTS MODELS FOR NUCLE-NUREG/CR.5748, RADIATION EMBRITTLEMENT OF THE NEUTRON AR POWER PLANT ACCIDENT CONSEQUENCE SHIEt 7 TANK FROM THE SHIPPINGPORT REACTOR.

ANALYS6S.MadificatL)r.s Of Models Resulting from Recent Reports On NUREL/CR 5757; VERIFICATON OF PIPING RESPONSE CALCULA-Health Effects Of foreng Radiation. Low LET Radiat.on Part It Scientif.

TON OF SMACS CODE WITH DATA FROM SEISMIC TESTING OF ic Bases For Healtn._

AN IN-PLANT PtPING SYSTEM.

NUREG/CR4427: AUXILIARY FEEDWATER SYSTEM RISK-BASED IN.

ARIZONA, UNIV. OF, TUCSON A2 SPECTON GUIDF FOR THE BYRON AND BRAIDWOOD NUCLEAR POWER PLANTS.

NUREG/C814295: BOND STRENGTH OF CEMENTITOUS LOREHOt.E NUREG/CR-4460 V11. NONDESTRUCTIVE EXAMINATION (NDE) REll-PLUGS IN WELDED TUFF AdlLITY FOR aNSERVICE - INSPECTION OF LIGHT WATER NUREG/CR-5581: UNSATURATED FLOW AND TRANSPOPT THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL WASTE REACTOR $.SemeAnnuai Report ApnLSeptemtrer 1989 NUREG/CR4670: RADIONUCLlDE DISTRIBUTIONS AND MIGRATION N $5fiNC OF CEMENT GROUTING NURE /

3 Nam @ h NWM Wa% W M OF FRACTURES IN WELDED TUFF' ELD TESTS OF THE HYDRAULIC NUREG/CR-5684: ANALYSES AND FI a

R

^

PERFORMANCE OF CEMENT GROUT BOREHOLE SEALS g

57 SS T MN K FOR AIR SAMPLER NUREG/C 86 FEGTIVENESS OF FRACTURE SEALING WITH S

ggRE CR 5343; RADONUCLIDE CHARACTERl2ATlnN OF REAC.

NUREG/CA-5688 MECHNNtCAL CHARACTER 12ATION OF DENSELY TOR DECOMV!SSON!NG WASTE AND SPENT FUEL ASSEMBLY WELDED APACHE LEAP TUFF HARDWARE Progress Report.

NUREG/CR 5716: MODEL VAllDATION AT THE LAS CRUCES NUREG/CR 5467: RISK BASFD INSPCCTON GUIDE FOR CRYSTAL TRENCH SITE.

RIVER UNIT 3 NUCLEAR POWER PLANT.

NUREG/C4E645: ACOUSTO EMISSION / FLAW RELATONSHIPS FOR ARKANSAS. UNIV. OF, FAYETTEVILLE, AR

• GMVICE MONITORid

• i LWRS.

NUREG/CA-5749: TECTONIC DEFORMATION REVEALED IN BALDCY.

NURE6/CR-5656 EXTRAN.

COMPUTER CODE FOR ESTIMATING PRESS TREES AT REELFOOT LAKE.TEHriESSEE.

CONCENTRATONS OF TOXO SUBSTANCES AT CONTROL ROOM air INTAKES. -

ARMY, CEPT. OF, ARMY ENGINEER WATERWAYS EXPERIMENT NUREG/CR-5652 FPFP 2-A CODE FOR FOLLOWtNG AIADORNE FIS-STAGON SON PRODUCTS IN GENERIC NUCLE AR PLANT FLOW PATHS NUREG/C45432 V01: RECOMMENDATONS TO THE NRC FOR SOfL NUREG/CR-56f9 EVALUATION OF EXPOSURE LIMITS TO TOXIC COVER SYSTEMS OVER URAN 1UM M!LL TAILINGS AND LOW-GASES FOR NUCLEAR REACTOR CONTROL ROOM OPERATOR 1 101

/

11

_U

102 Contractor Inder NUREGICR 5713 A REVIEW OF ENVIRONMENT AL CONDITIONS AND NUREG/CR4692: GENERIC RISK INSIGHTS FOR GENERAL ELEC-PERFORMANCE OF THE COMMERCIAL LOW-LEVEL RADiCACilvi TRIC BOtuNG WATER RE ACTORS.

W ASTE DISPOSAL FACIUTY NEAR SHEFFIELD3LUNOIS NUREG/CR 5707: APPUCATION OF CONTA!NUENT AND RELEASE NUREG/CR $714 HYDROGEOLOGIC PERFORMANCE ASSESSMENT MANAGEMENT TO A PWR ICE CONDENSER PLANT.

ANALYSIS OF THE LOW-LEVEL RA00 ACTIVE WASTE DISPOSAL NUREG/CR 5771. PROB AB10TY AND CONSEQUENCES OF M!SLOAD-FACtuTY NEAR SHEFFIELD ILUNOIS ING FUEL IN \\ PWR NUREG/CR4737 HYDROGE6 LOGIC PERFORMANCE ASSESSMENT NUREG/CR 5773 SELECTION OF MODELS TO CALCULATE THE LLW ANALYSIS OF THE COMMERC%L LOW LEVEL RADIOACTIVE SOURCE TEAM WASTE DI$POSAL FACluTY NEAR WEST VALLEY NEW YORK.

NUREG/CR-5798 PILOT PROGRAM TO ASSESS PTIOPOSED BASIC NUREG/CR 5758 V01: FITNESS FOR DUlf IN THE NUCLEAR POWER OUAUTY ASSURANCE FiEOl'IREMENTS IN THE MEDICAL USE OF INDUSTRY. Annual Sumrery Of Program Performance Reports,CY BYPRODUCT MATERLAL 11690 NUREGICR 5761: AUXiUARY F EEDWATER SYSTEM RISK-BASED IN-CALIFORNIA STATE LWlV., HAYW ARD FOUNDATION, INC., HAYWARD, SPECTION GUOE FOR THE SAIFM NUCLEAR POWER PLANT.

c4 NUREG/CR $N3 AUXIUARY FEEDWATER SYSTEM RISK. BASED IN-NUREG/CR 5609 MEDICAL SCREENING AEFERENCE MANUAL FOR SPECTON GUIDE /Oh THE CALLAWAY NUClJ AR POWER PLANT-SECURITY FORCE PERSONNEL AT FUEL CYCLE F#01UTIES POS-NUREG/CR 5764. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SES$1NG FORMULA QUANTPIES OF SPECIAL NUCLEAR MATERh SPECTION GUIDE FOR THE CINN A NUCLEAR POWER PLANT.

NUREG/CR 57165 SPARC 90 A CODE FOR CALCULATING FISSION ALS NUREG/CR4690 PHYSICAL FITNESS TRAIN!NG REFERENCE PRODUCT CAPTURE IN SUPPRESSON POOLS FVREG/CR 5760, ME CONDENSER AEROSOL TESTS.

MANUAL FOR SECURITY FORCE PERSONNEL AT FUEL CYCLE FA-CILITIES POSSESSING FORMULA QUANTITIES OF SPECIAL NU-BE, INC.

CLEAR MATERIALS.

NURFG/CR-5/21. VOEO SYSTEMS FOR ALARM ASSFCSMENT NUH1G/CR-5722. INTERIOR INTRUSON DETECTION SYSTEMS CALIFORN) A, UNIV OF, BERKELEY, CA NURIG/CR4723 SECUR'TY SYSTEM SIGNAL SUPERVISON-NUREGICR-4918 V05-CONTROL OF WATER INFILTRATION INTO NEAR SURFACE LLW DISPOSAL UNITS Progre.a Fleport On Field Ex.

BROOKHAVEN NATIONAL LABORATORY NU AN ON ETE T N IN SO L POSSIBLE APPUCA-REACTOR FETYlt O T

MF G

NUREG/CP.0114 V02. PROCEEDINGS OF THE ElGHTEENTH WnTER TK N TO REDUCE M;TGRATION OF BURIED TECHNETIUM AND RE ACTOR SAFETY INFORM ATION MEETING.

lODtNE.A Review.

NUHEG/CP4)114 V03. PROCEEDINGS OF THE EIGHTEENTH WATER REACTOR SAFET% INFORMATON MEETING.

CAllFORNIA, UNIV. OF, LOS ANGELES, CA NUREG".R-2907 V09' RADIOACTIVE MATERIALS RELEASED FROM NUREG/CR-3964 V02. TECHNIQUES FOR DETERMINING PROBABIL-NUCLEAR POWER PLANTS. Annual Report 1988, ITIES OF EVENTS AND PROCE8SES AFFECTING THE PERFORM-NUREGICR 3444 V08: THE (MPACT CF LWR DECONTAM!NATONS ANCE OF GEOLOGIC REPOSITORIES Suggested Approache.

ON SOUDiFICATON, WASTE DISDGSAL AND ASSOCIATED OCCU-MUREG/CR 5700:

SUMMARY

OF A WORMOP ON SEVEHE ACCl-PATIONAL tiXPOSURE. Effects Of Composition On The DENT MANAGEMENT FOR BWRS.

Strength,Swelkry And Watenimmersion Properties of Cement-Solnh.

NUREG/CR 5781.

SUMMARY

OF A WORKSHOP ON SEVERE ACCl-fied lor Exchange Rese Westes DENT MANAGEMENT FOR PWAS.

NUREG/CR 3469 V06. OCCUPATiONA.. DOSE REDUCTION AT NU-CLEAR POWER PLANTS. ANNOTA1ED BIBLOGRAPHY OF SELECT CALIFORNIA, UNIV. OF, SANTA BARBARA, CA ED READINGS lN RADIATION PROTECTION AND ALARA NUREG/CR-5423: THE PROBABluTY OF UNER FAILURE IN A MARK-1 NUREG/CR4214 R1P2A1: HEALTH EFFECTS MODELS FOR NUCLE-CONTAINMENT.

AR POWER PLANT ACCOENT CONSEQUENCE NUREG/CR4677, A UNIFIED lNTERPRETATION OF ONE-FtFTH TO M \\ LYSIS Adihcations Of Models Resulting From Recent Reports %

FULL SOALE THERMAL MIXING EXPERIMENTS RELATED TO PRES-Health Effects Of lonmng Rachahon.Lew LET Radiahon.Part 11: Scentif-SURIZED THERMAL SHOCK c Bases For Health....

NUREGICR-4444 RADIATON SAFETY ISSUES RELATED TO RADIO.

f' ENTER FOR NUCLEAR WASTE REGULATORY ANALYSES LABELED ANTIBODIES.

NUREG/CR-5440: CRITICAL ASSESSMENT OF SEISMIC AND GEOME-NUREG/CR-4659 V04. SEISMIC FRAGPITY OF NUCLEAR POWER CHANICS LITERATURE RELATED TO A HiGH-LEVEL NUCLEAR PLANT COMPONEWS (PHASE II) A Fragshty Handbook On Eighteen WASTE UNDERGROUND REPOSITORY.

Components NUREGICAM~s UNWRTAINTY EVALUATION METHODS FOR NUREu!CR4967. RELAY TEST PROGRAM. Series i Vibration Tests.

vv45TE MCKAGE PERFORMANCE ASSESSMENT.

NUREG!CR 5139 DOSE-REDUCTON TECHNtQUES FOR HIGH DOSE NUREG/CR4743 APPROACHES TO LAGGE S" ALE UNSATURATED WORKER GROUPS IN NUCLEAR POWER PLANTS-FLOW IN HETEROGENEOUS, STRATIAED AND FRACTURED GEO-NUREG/CR.5282 ESTIMATON OF CONTAINMENT PRESSURE LOAD-LOGIC MEDtA~

ING DUE TO DlHECT CONTAINMENT HEATING FOR THE ZION NU R 5526 ANN" SIS OF RISK REDUCTION MEASURES AP-A N TR T ON PtlED TV SHARED cSSENTIAL SERVCE W ATER SYSTEMS AT NUREGICR-5777; GLOBAL POSITIONING SYSTEM MEASUREMENTS

^

^

NUREG/ R 55 1: INFLUENCE OF ORGAN 12ATICNAL FACiORS ON PEHFORMANCE REUABluTY. Overview And Detwled Methodo-N A N A SESSMENT OF THE WESTINGHOUSE NU EG/ 5598 MER ION STUDIES ON CANDCATE CONTAINEl; NUREG/CR4585 THE HIGH LEVEL VlBRATIO" TEST PROGRAM Final ALLOYS FOR THE TUFF REPCJTORY.

OAVID W,. TAYLOR PAVAL RESEARCH & DEVELOPMENT CENTER NU L CR 5611: ISSUES AND APPROACHES FOR USING EOUtP-MENT REllABILITY ALERT LEVELS NUREG/CR-5577-EXTENSTON AND EXTRAFOLATION OF J-R i

' NUREG/CR-5612. DEGRADATION MODEUNG WITH APPUCATON TO CURVES AND THEIR APPLtCATION TO THE LOW UPPER SHELF AGING AND MAINTFNANCE EFFECTIVENESS EVALUATIONS

. TOUGHNESS ISSUE NUREG/CR-5E20- THATCH A COMPLr"ER CODE FOP OODELUNG THERMAL NETWORKS OF HIGH-TbAPERATURE GASCOLED NU-EG&G IDAHO, INC. (SUBS. OF EG&G, INC.)

Cll'AR REACTORS NUREG!CR 4063: AN INVESilGATION OF CJRE UGUIC LEVEL DE-NUREG/CR634; IDENTIFICATON AND ASSESSMENT OF CONTAIN.

PRCSSON IN SMALL BREAK LOSS-OF. COOLANT ACCIDENTS MENT AND RELEASE MANAGEMENT STRATEGIES FOR A BWR NUREG/CR43CO V01: INTEGRATED HEUABillTY AND RISK ANALY.

MARK t CONTAINVENT.

SIS SYSTEM (!RRAS) VERSION 2.6 Reference Manual NUREG/CR-5641: STUDY OF OPERATIONAL RIS40ASED CONFIGU.

NUREG;CR-5520- PROCEDURES GUOE FOR EXTRACTING AND RATION CONTROL LOADING PROOABluSTIC RIL. ASSrSSMEMT DATA INTO MAR D NUREG/CR-5662: HYDROGEN COMBUSTON. CONTROL.AND VALUE.

USING IRRAS 2.5.

IMPACT ANALYSIS FOR PWR DRY CONTAINMENTS NUREG/CR4529: AN ASSESSMENT OF BWR MARK til CONTAIN-NUREG/CR-568t LOW-LEVEL WASTE SOURCE TERM MODEL DE-MENT CHALLENGES, FAILURE MODES, AND POTENTIAL IMPROVE-VELOPMENT AND TESTING MENTS IN PERFORMANCE l

l 1

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

l i

l Contractor Index 101 NUREG/bk5543 A SYSTEMATIC PROCEdS FOR DEVELOPING AND INTER A TECHNGLOGIES. lhC.

ASSESSING ACCIDENT MANAGEMENT PLANS NUREG/CR-5539 A SELF-TEACH!NG CURRICULUM FOR THE NRC/

NUREG/CR5558: GENERtC ISSUE 87: FLEXIBLE WEDGE GATE SNL LOW-LEVEL WASTE PERFORMANCE ASSESSMENT METHOD-VALVE TEST PROGRAM Phase 11 Resutts And Anatyvs.

OLOGY' NUREG/CR 5601' EFFECTS OF PH ON lHE RELEASE OF RADONU-CLOES AND CHELATIN0 AGENTS FROM CEMENT-SOLIDIFIED DE-INTERCR, DEPT. OF, GEOLOGICAL SURVEV 0 ATAMINATON BON-EXCHANGE RESINS COLLECTED FROM OP-NUREG/CR 5522: A COMPARISON OF PARAMETER ESTIMi, TION Ee aTING NUCLEAR POWER C1 ATIONS.

NUREG/CR5614 PERFORMANCE OF IN1.ACT AND PARTIALLY DE-AND SENSITIVITY ANALYSIS TECHNIOuES AND THEIR IMPACT ON GRADED COP nETE BARR!ERS IN LIMITING FLUID FLOW, THE UNCERTAINTY IN GROUND WATER FLOW MODEL PREDPC-NUREG/CR-5654-CONTAINMENT VENTING ANALYSIS FOR THE TIONS.

SHOREHAM NUCLEAR POWER STATION NUREG/CR-5663. RELAP5 THERMAL-HYDRAULIC ANALYSIS OF THE lOWA STATE UNIV., AMEst,iA WNP1 PRESSURl2ED WATE'I REACTOR NUREG/CR556t: A*JALYSIS OF BELLOWS EXPANSION JOINTS IN NUREG/CR5667: INEL PERSONAL COMPUTER VERSION OF MACCS THE SEOl>OYAH CONTAINMENT.

1. 5.

NUREG/CR 5672 V01. CHARACTERISTICS OF LOW LEVEL RAD 10AC-ITASCA CONSULTING GROUP, INC.

TIVE WASTE Decontamination Waste _ Annual Report For Fiscal Year NUREG/CR-5440: CRITICAL ASSESSMENT OF SElSMIC AND GEOME.

1990, CHANICS LITERATURE RELATED TO A HIGH LEVEL NUCLEAR NUREG/CR5691: INSTRUMENTATION AVAILABluTY COR A PRES-WASTE UNDERGROUND REPOSITORY.

SURIZED WATER REACTOR WITH A LARGE ORY CONTAINMENT DURING SEVERE ACCIDENTS JACK TILLS & ASSOCIATES,INC.

NUREG/CR5702: ACCIDENT MANAGEMENT INFORMATION NEEDS FOA A BWR WITH A MARK I CONT AINMENT-NUREG/CR-5343: FISSION PRODUCT RELEASE AND FUEL BEHAV-IOR OF IRRADIATED LIGHT WATER REACTOR FUEL UNDER C

i G

STR TUR A O SCAL-SEVERE ACCIDENT CONDITION

• The ACAR ST 1 Expentnent.

ING METHODOLOGY FOR SEVERE ACUXNT TECHNICAL ISSUE RESOLUTION Draft Repott For Commer.L KANSAS, UNIV. 0F, LAWRENCE, KS NUREGICR5767: THE BEHAVOR OF SHALLOW FLAWS IN REACTOR FEDERAL EMERGENCY MANAGEMENT AGENCY PRESSURE VESSELS.

NUREG-1441: LESSONS LEARNED FROM THE POST EMERGENCY TABLETOP EXERCISE IN BATON ROUGE,LOUiStANA,0N WJGUST KOREA ATOMIC ENERGY RESEARCH INSTITUTE 28 AND SEPTEMBER 18.1990.

NUREG/CRf282: ESTIMATON OF CGNTAINMENT PRESSURE LOAD-NUREG 1442:

POST EMERGENCY

RESPONSE

FGSOURCES ING DUE TO DIRECT CONTAINMENT HEATING FOR THE 2ON GUIDE. Based On The Post-Emergency TABLETOP Exercise in Baton PLANT.

Rouge.Loursiana,On Aupst 28 And 4ptember 18,1990.

KTECH CORP, ORAM. lNC.

NUREG/CR3916: PRESSURIZED MELT EJECTON INTO WATER NUREG/CR3964 V02: TECHNIQUES FOR DETERMINING PROBABIL.

poots' ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-ANCE OF GEOLCGIC REPOSITORIES Suggested Approaches LAMONT-DOHERTY GEOLOGICAL 00SERVATORY NUREG/CR5522: A COMPAR! SON OF PARAMETER ESTIMATION AND SENS;TIVITY ANALYSIS TECHNIQUES AND THEIR IMPACT ON NUREG/CR5778 VO1: NEW YORK /NEW JERSEY REGONAL SEISMIC THE UNCERTAINTY IN GROUND WATER FLOW YODEL PREDIC-NETWORK. Annual Report For Apnl 1989 - Much 1990.

N G CR5536. DCM3D A DUAL-CONTINUUM, THREE-DIMENSON-AL, GROUND-WATER FLOW CODE FOR UNSATURATED, FRAC.

TURED, POROUS MEDIA PRESSION IN SMALL OREAK LOSS-OF-COOLANT ACCIDENTS.

NUREG/CR 5537: APPROACHES FOR THE VALIDATION OF M@O $

NUREG/CR5550: PASSIVE NONDESTRUCTIVE ASSAY OF NUCLEAR USED FOR PERFORMANCE ASSESSMENT OF HIGH-L. 'fEL NUct.E-MATERIALS, AR WASTE REPOSl10 RIES.

NUREG/CR$660- STATIC AND S!MULATED SEISMIC TESTING OF THE TRG-7 THROUGH 16 SHEAR WALL I aVCTbRES.

H ARV ARD SCHOOL OF PUBLIC HEALTH, BOSTON, MA NUREG/CP-0116 V01. PRJCEEDINGS OF THE 21ST DOE /NRC NU.

LOS ALAMOS TECHN! CAL ASSOCIAihS,!NC, CLEAR air CLEANING CONFERENCE. Sessions 1 8.H#d in San NUHtsGR5715. REFERENCE MANUAL FOR THE CONTAIN 1.1 Diego, California, August 13 16,1990.

CODE FOR CONTAINMEN' SEVERE ACCIDENT ANALY*lS.

NUREG/CP 0116 V02: FROCEEDINGS OF THE 21ST DOE /MC NU-CLEAR AIR CLEANING CONFERENCE SESSIONS 9 - 16 Hold in %n LOUISlANA STATE UNIV., BATON ROUGE, LA Dwgo. Cahfornia. August 13-16, 1990.

NUREG/CR5648; TRANSPORT CALCULATIONS OF NEUTRON TRMMISSON THROUGH STEEL USING ENDF/B-V, REVISED HYDROGEOLOGIC, INC-

%f 5 bV AND ENDF/8-VI 1RON FVALUATONS.

I UREG/CR5352 RO1: VAM2D. VARIABLY SATURATED ANALYSIS MODEL IN TWO DIMENSONS Verson 5.2 With Hysterests And Chain.

MNWE CONSULTING, LTD..

Decay Transport Documentation And User's Guide NUREG/CRM94. GROUND-WATER FLOW ANO TRANSPORT MODEL' NbM J/CRS282: ESTIMATION OF CONTAINMENT P3 ESSURE LOAD.

ING OF THE NRC-LICENSED WASTE DISPOSAL FACILITY, WEST lNG DUE TO DIRECT CONTAINMENT HEATING FOR THE ZION PLANT.

VALLEY, NEW YORK.

NUREG/CR-5795: VAUDATION AND TESTING OF THE VAM2D COM-PUTER CCDE' MARYLAND, UNIV, OF, COLLEGF PARK, MD NUREG/CR 49'8 V05. CONTROL 03 WATER INFILTRATION INTO INHALATION TOXICOLOGY RFEEARCH INSTITUTE NEAR SURFME LLW DISPOSAL UNITS. Progress Report On Field Ex-NUREG944214 RIP 2A1: HEALTH EFFECTS MODELS FOR NUCLE-penments At A Humd Regen Sde,Bdsde#aMand AR POWER Pi*NT ACCOENT CONSEQUENCE NUREG/CR 569 USE OF THICKNESS REDUCTON TO ESTIMATE ANALYSIS Modif:cahons Ce Models Resutting From Recent Reports On VALUES OF K.

Health Effects Of lonmng Radiatiortlow LET Radiation.Part IL Scientif-NUREG/CR-5703. LOWER-80VND INITIATION TOUGHNESS WITH A ic Bases For Heaith..,

MODIRED-CHARPY SPECIMEN.

INSTITUTT F0F ENERGITEKNIKK MICHIGAN, UNIV. OF, ANN ARBOR, MI NUREG/CRM77: REVIEW OF THE CHRONIC EXPOSURE PATHWAY NUREG/CR3145 V09: GEOPHYSICAL INVEST;GATONS OF THE MODELS IN MAOCS AND SEVERAL OTHER WELL KNOWN PROB-WEST'ERN OHIO.lNDIANA REGON Annual ReportOctober 1989 ABillSTIC RISK ASSESSMENT MODELS, September 1990.

INSTITVTT FOR ENERGITEKNIKK (INSTITUTE FOR ENERGY MITRE CORP.

' TECHNOLOGY)

NUREG/CRS382 SCREENING OF GENERIC SAFETY ISSUES FOR LI-NUREG/CR-5304-RADIONUCUDE BEHAVIOA IN THE ENVIRONMENT.

CENSE RENEWAL CO;4SIDERATONS

4 104 Contractor Index PODELING & CJMPUTER SERVICr$

NUREG/CR-559' ANALYTICAL STUDIES OF TRANSVERSE STRAIN NUREGIC45729 MULTIVARIAAE MODEUNG OF PRESSURE EFFECTS ON. RACTURE TQUGHNESS FOR CIRCUMFF1ENTIALLY VESSEL AND PIPtNG J R DAT A.

OR:ENTED CRACKS.

NUREG/C45623. BWR MARK !! ELVESSEL LORIUM INTERACTON MPR ASSOCIATES,INC.

ANALYSES.

NUREGICR 5760: REPORT ON ANNEAUNG OF THE NOVOVORON-NUREG/C45647: FISSON PRODUCT PLATEOUT AND LIFTOFF IN EZH UNIT 3 REACTOR VESSEL IN THE USSR.

THE MHTGR PRIMARY SYSTEM A REVIEW NUREG/C45648. TRANSPORT CALCULATIONS OF NEUTRON NtTIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERLY NATIONA6 BUAEAU OF TRANSMIS$10N THROUGH STEEL USING ENDF/B V REVISED L.0F/B-V.AND ENDF/B-V1 IRON EVALUATIONS.

NUREG/CR 4235 SELECTION OF SILICEOUS AGGREGATE FOR NUREG/CR 5051: AN INVESTIGATION OF CRACK TIP STRESS FIELD CR TE E C NG EAVA N1 EG/CR 4269-MODELS OF TRANSPORT PROCESSES IN CON-wp G,RlA eq A

y pg ODUCT Nt.RE /CP-4735 V07: EVALUATION AND COMPILADON OF DOE N RE f6 ADIATON EFFECTS ON CHARPY IMPACT AND NU EG C 5 : S E

ER INT ES I

SUR TENSlLE PROPERTIES OF LOW UPPER-SHELF WELDS.HSSI MENT P

LE EWV1RONMENTS CHARACTER!STIC OF SER ES O 3.

NURE 3/CR-5727: CHLCMOE N DIFFUSION IN LOW WATER-TO.

VALUES OF K.

SOLID CEMENT PASTES.

NUREG/CR 5703: LOWER-BOUND INITIATION TOUGHNESS WITH A MODIPED CHARPY SPECIMEN NEW MEXICO 3 TATE UN1Y. LAS CRUCES, NM NUREGeC45706: POTENTIAL SAFETf RELATED PUMP LOSS. AN AS.

NUREG/CR-5716-MODEL VALOATON AT THE LAS CRUCES SESSMENT OF INDUSTRY DATA.NRC Eunetin 88-04.

TRENCH $!TE, NUREG/CR 5712: MORECA A COMPtlTEP CODE FOR SIMULATING MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR CORE NEW MEXICO, UNIV. OF, ALBUQUEROUE, NM HEATUu ACCOENTS.

NUREG/CR-5660: STATIC AND SIMULATED SEISMIC TESTif4G OF NUREG/CR 5732 DRF FC: IODINE CHEMICAL FORMS IN LWR THE TRGJ THROUGH 16 SHEAR WALL STRUCTURES SEVET-E ACCIDENTS Draft Report For Cornment NUREG/CR-5740: NEW GAMMA-RAY BUILDUP FACTOR DATA FOR OAK RIDGE K 25 SITE POINT - KERNEL CALCULATIONS: ANS-6.4.3 STANDARD REFER-GUREG/C45734: PECOMMLNDATIONS TO THE NRC ON ACCEPTA.

ENCE DATA.

BLE STANDARD FORMAT AND CONTENT FOR THE FUiOAVEN' NUREC/C45767: THE BEHAVOR OF SHALLOW FLAWS IN REACTOR TAL NUCLEAR MATERIAL CONTROL (FNMC) PLAN REQUIRED FOR PRESSURE VESGELS LOW-ENR!CHED URANIUM ENRICHMENT FACILITIES.

NUREG/C45808 CALCULATION OF ABSORBED DOSES TO WATER OAK RIDGE NATIONAL LABORATDRY b

NUREG/C42000 VO9N17 LICENSEE EVENT REPORT (LER)

OREGCN ORADUATE INSTITUTE OF SCIENCE & TECHNOLOGY, COMPILATION For Month Of Decemos 1990-BEA/ERTON,OR

)

COMPIL For onth Of a 1931^

HUREG/G40002: CONTINUOUS COOUNG THERMAL CNCLE EF-NUREG/C42000 V10 N2. LICENSE E EVENT REPORT (LER)

FECTS ON SENSITIZA10N IN STAINLESS STEEL COMPILATON For Mmth Othebruh1991.

NUREG/GR 0003. EFFECT OF PRIOR DEFORMATION ON SENSITIZA-Ni' REG /G42000 V10 N3. k LICE 5 EVENT RZPORT (LER)

TON DEVELOPHENT IN STAINLESS STEEL DURING CONTINUOUS COMPILATONJor Month Of Mar::h 1,91, COOUNG.

NUREG/CR 2000 V10 N4.

LICENSEE - EVENT REPORT (LEF)

COMPILATION For Month Of Apnl 1991.

PAR AMETER, INC, NUREG/CR 2000 V10 N5 UCENSEE EVENT REPORT (LER)

N'JREG/CR 4666: Ca.OSEOUT 1 E ZLLETIN 84-07 FAILURES OF COMPILATION For Month Of May 1991 GENERAL ELECTRIC TYPE NFA RELAYS IN USE IN CLASS 1E NUREG/CR2000 V10 N6: UCENSEE EVENT REPORT (LER)

SAFETY SYSTEMS.

COMPtLATION For Month Of June 1901 NUREG/C452% CLOSEOUT OF IE BULLETIN 7913: CRACKING IN NUREG/C42000 VW N7: - LICCNSEE EVENT REPORT (LE P)

FEEDWATER SYSTEM PtPtNG. -

COMPILATON For Month Of July 1991, NpErPCWes: CLOSEOUT OF IE BULLETIN 60-06 ENGINEERED NUREGIC42000 V10 N6 LICENSEE EVENT PEPORT (LER)

SAFETY FEAlunE tESF) RESET CONTROI L LXJMotLATON cor Venth Of Aum**' inot MUREG/CR 5309: CLOSEOUT OF IE BULLETIN 83-07. APPARENTLY NUREG/CR 2000 V10 N9. LtDENSEE EVENT REPORT (LER)

FRAUDULENT PRODUCTS SOLD BY RAf MILLER,1NC.

COMPILATION For Month Of September 1901.

NUREG/CR.2000 V10N10- LICENSEE EVENT REPORT (LER)

PENNSYLVANIA (tTATE UNIV., UNIVERSITY PARK, PA COMPtLATICh For Month Of October 1931-NUREG/CR562B-PENNSYLVANIA SEISMIC MONITOiiNG NETWORK NUREG/CR 2000 91pN1t UCENSEE E'/ENT REPORT (LER, AND RELATED TECTONC STUDIES. Final Report.

COMPILATION for Month Of Novemt>er 1991.

NUREG/CM219 V07 N1: hEAVYMCTION STEEL TECHNOLOGY PROGRAM.Semaannual Progress 47 port For October 19t'9 March PHYEIC At RESEARCH,1NC.

NUREG/C45651: TWO NE'N NDT TECHNtOUCS TOR INSPECTION OF N R G/CR4219 V07 h2: HEAVY-SECTION STEEL TECHNOLOGY

^

0 PROGR AM.Senuannual Progtess Report For Apni September MO 1989 March W NUREG/CR-430; V02: AGING AND SERVICE WEAR OF CMECK VALVES USED IN ENGINEERED MFETY FEATURE SYSTEMS OF PROFESSIONAL ANALYSIS, INC.

NUCLEAR POWER PLANT 3 Agq Aar.ewnents And Morutomg NUREG/C44674 V13; PREC1IRSOAS TO POTENTML SEVERE CORE Method Evaluations.

DAMAGE ACCOENTS;1990 A STATUS REPORT Mam Report And Ap.

NUREG/C44674 V13: PRECURSORS TO POTENTIAL SEVERE CORE pendix A.

DAMAGE ACCIDENTS.1990 A STATUS REPORT. Main Report And Ap-NUREG/C44674 VI A FRECURSORS TO POTENTIAL SEVERE CORE pendia A.

DAMAGE ACCICENTS1990 A STATUS REDORT Appendmes B And NUREGICR-4674 V14. PRECURSORS TO POTENTIAL SEUERE CORE C.

DAMAGE A'CIDENTS:1990 A $1 ATUS REDORT.Appendmes B Arwt RAF AEL BRAS CONSTA.11NG ENGINEERS NUREG/CR e816 R0t; PR-EDB: POWER REACTOR EMBRITTLEMENT NUREG/CR-3964 V02: TECHNIOUES FOR DETERM!NING PROBABIL-DATA BASE.VERSON 1. Program Descnptort -

ITIES OF EVENTS AND PROCESSES AFFECTING THE PE"tFORM-NUAEG/C45481' DATA SUMMAR) R2 PORT FOR FISSION PRODUCT ANCE OF GEOLOGIC REPOSITORIES Suggested Approach <es RELEASE TEST VI-4.

NUREG/C45565 THE RESPONSE OF BWR M?84K ll CONTAINMENTS SANDIA NATIONAL LABORATORIES TO STATION BLACKOUT SEVERE ACCIDENT SEOVENCES NUREG/CP-0115: PROCEEDINGS OF THE CSNI WORKbriOP ON PSA NUREGIC45571-THE RESPONSE OF BWR MARF M CON AtN-APPuCATIONS ANO UMIT ATIONS.

MENTS TO SHORT TERM STATON BLACKOUT SEVERE ACCIDENT NUREG/CR3916. 'PRESSUAIZED MELT EJECTION _ INT 9 WATER SEQUENCES POOLS.

6 e_

l Contractor Index 105 NUREG/CR 3964 V02. TECHNIQUES FOR DETERMINtNG PROBABIL.

SCIENCE APPLICATIONS INTERNATIONAL CORP.(FCRHERLY lites OF EVENTS AND PROCESSES AFFECTING THE PERFORM-SCIENCE APPLICATIONS, ANCE OF GEOLOGIC REPOSITORIES Suggested Approaches.

NUREG-0713 V10' OCCUPATONAL RADIATON EXPOSURE AT COM-NUREG/CR4551 V2R t P2: EVALUATON OF SEVERE ACC1J d MERCIAL NUCLEAR POWER REACTORS AND O'HER RISKS QUANTIFICATION OF MA,,OR INPUT PARAVETERS Experh' FACillTIES.1988 Tnenty Frst Annua! Aeport 5

Determinaton Of Containment Loads And Moltso Core Containment NbREG/CR-4551 V2R112. EVALUATION OF SEVERE ACC10ENT interaction issues R:SKS: OU*.NTIFICATION OF MAJOR INPUT PARAMETERS Expectf NUREG/CR$304. RADIONUCUDE BEHAVIOR IN THE ENVIRONMENT, Deterrmneon Of Uontamment Loads And Molten Core Containment NU EG/CR 5312: A THERMODYNAMC MODEL OF FUEL DISRUP-d"y*E C$4 13: PRECURSORi T') POTENTIAL SEVERE CORE F ~1EG/CRh131: MrLCOR ANALYSES FOR ACCIDENT PROGRES-DAMAGE ACCIDENTS 1990 A STATUa REPORT Main Repo1 And Ap-SiON ISSUES N

/CR4674 V14: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR5345: FISSION PRODUCT RELEASE AND FUEL BEHAV' IOR OF IRRADIATED LIGHT WATER REACTOR FUEL UNDER DAMAGE ACCIDENTS 1990 A STATUS REPORT. Appendixes B And C

SEVERE ACCIDENT CONDITIONS The ACRR ST 1 Expenment NUREG/CR-4690 V01 R1:

GENEHC COMMUNICATIONS NUREG/~R 5495: CONCEPTUAll2ATION OF A HYPOTHETICAL HIGH INDEX Listings Of Cetmuncahons 1971 19tt9.

LEVEL NUCLEAR

%ASTE REPOSITORY SITE IN NUREG/CR5et ). ISSUES AND APPROACHES FOR USING EQUIP-UNSATJRATED, FRACTURED TUFF.

"ENT RELIABILITY ALERT LEVELS NUREG/CR-5518. QUALITY ASSORANCE PROCEDURES FOR THE NVREG/CR5641: STUDY OF OPERNflONAL RISK-BASED CONFIGU-CONTAIN SFVERE REACTOR ACCIDENT COMPUTER CODE.

RATION CONTROL d

NUREG/CR 5622: A COMPARISON OF PARAMETER ESTIMATION

]//

0 F S 11 A SES TO B ED AND SENSITIVITY ANALYSIS TECHNIQUES AND THtaR IMPACT ON THE UNCERTAINTY IN GROUND WATER FLOW MODEL PREDIC-ng M ^ky A

T 2 FE BLT SES b

R SEAIED -

NU EG CR5525. HYDROGEN-AIR.) FLUENT DETONATICN STUDY FOR NUCLEAR REACTOR SAFETY ANALYSES.

SC'E NTECH, INC, NUREG/CR5531: MELCOR 1.80: A COMPUTER COOC FOR NUCLEAR NUREG/CR-4893: IECHNICAL FINDINGS REPGAT FOR GDIERIC REACTOR SEVERE ACCIDENT SOURCE TERM AND RICK ASSESS-ISSUE 135 Slea.n Generator And Steam Line Overfill issues.

VENT ANALYSES.

NUREG/CR-5167: COST /BENEHT ANALYSG FOH Ot'NERIC ISSUE NUREG/CR5536: DCM30: A DUAL-CONTINUUM, THREE DuJENSION-23 REACTOH COOLANT PUMP SEAL FAILURE.

AL, GROUND-WATER FLOW CODE FOR UNSATURATED. FRAC.

NUREG/CR-5682: SPECIFIC TOPICS IN SEVERE ACCIDENT MANAGE-TURED. POROUS MEC'A.

MENT.

NUREG/CR 5537: APPROACHES FOR THE VAllDATION OF MODELS USED FOR PERFORMANCE ASSESSMENT OF HIGH LEVEL NUCLE' SON ALYSTS, INC NUREG/CR50$L A SYSTEMATIC APPHOA*H TO RPETITIVE FAIL-AR WASTE REPOSITr) RIES URES' NUREG/CR-5539 A SELF TEACHING CURRICULUM FOG THE NRC/

SNL '.OW-LEVEL WASTE PERFOPHANCE ASSESSMENT METHOO-STANi ORD UNW., STANFORD. CA OLOGY.

NUREO/CR-5639. UNCERTAINTY EVALUATION NETHOUS FOR NUREG/CRb546. AN INVESTIGATION OF THE EFFECTS OF THER-W4TE PACKAGE PERFORMANCE ASSISSMENT.

MAL AGING ON THE FIRE DAMAGEABILITY OF ELECTRIC '%BLES NUREG/CR556t: ANALYSIS OF BELLOWS EXPANSION.K,.1TS IN TECHNADYNE ENGINEERING CONSULTANTS,1NC.

THE SEQUOYAH CONTAINVENT.

NUREG/CR4551 V2 RIP 2: EVALUATION OF SEVERE ACCOENT NUREG/CR5606. A REVIEW OF THE SOU ' EXAS PROJECT PROB.

RISKS: QUAN"FICATION OF MAJOR INPUT PARAMETERS Experts' ABILISTIC SAFETY ANALYSIS FOR ACCIDENT FREQUEf# Y EST).

Detarrnmaton Of Containment Loads Avf Molten Core Containrrent MATES AND CONTAINMEbT BihNING.

Interacton issues.

NURE CR 5618-USER'S MANUAL FOR THE NEFTRAN 11 COMPUT.

TEXAS A&M UNIV., COLLEGE STATION, TX NUREG/CR$5619. THE IMPACT OF THERMAL AGING ON THE FLAM-MABILITY OF ELECTAC CABLES ITIES OF EVENTS ANO PROCESSES AFFECTING THE PERFORM-NUREG/CRt M PWR DRY CONTAINMENT PARAMETRIC STUDIES-NUR /

F IT N CAL l*:ULATE NUREG/CR-5655: SUBMERGENCE AND HIGH TEMPERATURE STEAM PARTICLE PENETRATION T&fROUGH AEROSOL TRANSPORT RSIING OF CLASS 1F ELECTRICAL CABLES NUREG/CR5701: A PEA ORMANCE ASSES $t4ENT METHODOLOGY LINES Drai' Report For Comment' FC"1 HIGH-LEVEL BAE:OACTIVE WASTE DISPOSAL IN U.S. NAVAL ACADEMY. ANNAPOLi$, MD UNSATURATED, FRACTURED TUFF NUREG/CR-5577: EXTENSION AND EXTRAPC-ATION OF J-R NUREG/CR-5715' REFERENCE MANUAL FOR THE CONTAIN 1.1 CURVES AND THEIR APPLICATION TO THE LOW UPPER SHELF COCE FOR CONTAINMENT SEVERE ACCIDENT AAALYSIS.

TOUGHNESS ISSUE.

NUREG/CR 5721: VIDEO SYSTEMS FOR ALARM ASSESSMENT.

NUREG/CR-5722: INTERIOR INTRUSION DETECTICN SYETEMS_

VIKING SYSTEMS INTERNATIONAL NUREG/CR-5723. SECURITY SYSTEM SIGNAL SUPERVISION.

NUREG/CR 5796:

STEAM GENERATOR OPERATING

'y NUREGICA-5728. EXPERIMENTS TO INVESTIGATE THE EFFECT OF EXPERIENCE, UPDATE FOR 198919iKL FLIGHT PATH ON DIRECT CONTAINMENT HEATING MH) IN THE SURTSEY TEST FACILITV.The Limited Fisght Path (LFP) Tests WISCONSIN, UNIV. OF, MADtSON, WI NUREGICR-5748 RADIATION EMBRITTLEMEN' OF THE NEUTRON NUREU/CR3964 V02: TECHNIQUES FOR DETERMINING PROOABIL-SHIELD TANK FROM THE SHIPPINGPORT REACTOR.

ITIES OF EVENTS AND PROCESSES AFFECTlW' THE P5RFORM-ANCE OF GEOLOGIC REPOSITORIES

.ted nn SCIENCE & ENGINEER!NG ASSOCIATES INC

^ " "

NUREG/CR5595: FORECAST: REGUL TORY EFFECTS COST AN iLY*

ALYS1 M catens odets R ng From de R

s NU EG A VE O T E SOUTH TEXAS PROJECT MOS-

[8 For b it ~

ABILISTIC SMETY ANALYSTS FOR ACCILdNT FREQUENC' i 3TI-MATES AND CONTAINMENT DINNtNG.

XYZYX INFORMATION CORP.

NUREG/CR5655: SUBMERGENCE AND HIGH TEMPERATURE STEAM NUREG/CR 566tr PROGRAMMATIC ROOT CAUSE ANALYSIS OF TESTING OF CLASS tE ELECTR! CAL CABLES MAINTENANCE PERSONNE/ 'EGORMANCE PROBLEMS.

t h

i

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

There were no NURfG/lA reports for 1991 b

107

)

h 3

Licensed Facility index This index lists the facililes that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. Tney are preceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

Si450456 Broowaod Sta'on. UM 1. Commorweae Eesy NUrEGICR4427 O 206 San Onohe Nuttes Stahon, UM 1, Southe's NUREG1443 Co.

Canforma Edison Co.

% 260 Broe4 Faey Nucles Poww Slam D'ut 2.

NUREG-1232 v03 S:2

% 327 Seouoyah Nucles Plart Urst 1 Tese NUREG/CR 5%t Tenressee Valley Aumon Nahey Aumonly ST4%454 Byron Stanon. UM 1 Commonwese E6 son Co. NUREGICR44;"

B328 W oyah Nucisar Rant, UM 2, Tennessee NUREG/CR-5561 ST4%455 Bwan Stabon. VM 2. Commonweee Edson Ca NVAEd/CR. C 4

he saa t tabu, UM 1,

% 322 S

m Nuc a Power Stabon, Long latand NUREG/CR 5654 Texas Utkbes Oecti Lghtmg Ca W46 Comanche Pee Steam Electne Stabon, Unit 2.

NUREGICR5456 STN-%436 South Te ss Pqect, VM 1. Houston tqhting & NURcG/CR-5606 Texas " tabes Eirt Po** Uo 54302 Crysai RMs Nuder l' Ant Unit 3 Flanda Pour NUREG/CR 5467 ST4%439 f wth Texas Praect, Unit 2 Houston Lghting & NUREG/CRM4 Corp Power Co.

50 '

Dat90 Canyon Nucks Power Plant Urvt 1, NUREG475 $34 50-400 WPPS. Nuclear Pqect VM 1, WasNngton NURF.G!CR 5661 Pacht Gas & Onctnc Co Putk Power 'supc9y System 5

50 323 Datdo Canyon Nucier Power Plant, Urvt 2.

NUREG 06'S %

% 390 Watts Ba Nuclear Ptant. VM 1. Tennessee NURE40647 SC4 Pactr Gas & Decinc Co Vaney Authenty

% 410 Nre We Poet Nucma Sta% Urut 2, hagara NUREG-1455 54390 Watts Br Nuclear PV t, Urut 1, Tennessee NUREG0647 S07 Mohawn Power Corp

^"

B2) een Nuclear Rant ie%

NUREG t?l2 g

g M W L Tm WWW 50401 RESAR SP/3tt Westograse Electnc Corp NUREG 1413 Vaney Au1hnety

% 244 Rotert Emmer Gmna Nuciear tant, Jm t, NUREG/CR-5764

% 391 Watts Ga Nuclear Rant. Urst 1 (ennesseo NUREG447 $07 a

Rochesta Gas & Ewtoc C Valley Authonty 542??

Saw Nuctow Genwavy Staten, Unit 1.Putk NUREG/CR 5761

% 295 Zon Nucws Power Station, Urst 1.

NUREGICR-5282 Serms Oectne & G Commor'weem Emsca Co.

K311 Sam kries Generstrd tancA Urut 2, Putk NUREG/CR5761

% 304 lxx1 Nucivar Powur Stanen, Umt 2, NREG/CR-5282 S

Srece Et & Gas Commonweat Edson Co.

1 109

l l

l NRC FORM 335 U. 8, NUCLEAR REGULATORY COMMISSION 1 REPORT NUMBEn (2-89)

(Assigned by NRC. Add Vol.,

I NRCM1 W, Sug:o., Rev., and Addendien Num-3201. 3N BIBUOGRAPHIC DATA GHEET b"' * - " "'14 (See instructus on tne reverse)

NUREG-0304

a. Tu a m D Suuta a

.Vol.16, No 4

3. DAll HLPOHf PUUUGHLD Reguhtory and Technical Repons (Abstract index Jonrnal)

MONTH YtAn Annual Compilation for 1991 March

'992

4. FIN OR GRANT Nt3ADER

~

6.AvinOHtbl

6. TYFt Of REPOHT Reference

7. PERIOD COVEP.ED (inclusive Detes)

{.

1991

8. FtRFORMING OHGANiZAllON - NAME AND ADDRESS (If NRC, prov6do Olvision, Ofhce or Region, U.S. Nuclear Regulatory Commission, and mamng address; if contractor, pr e Jde name and malling address.)

Division of Freedoin ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 0, 6PONSORING ORGANIZATION = NAME AND ADDRESS {it NRC, type *Same as ateve l if contractor, provude NRC Division, - llce or Region, U.S. Nuclear Regulatory Commission. and mailing address.)

a Same as 8, above.

~

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

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

12. KEY WORDS/DESCRFrORS (List words or Dhrases th.st will assist researchern 6n locating tre report )

13. AVALA81UTY ST ATEMENT Unlimited compilation

" SECUHW MSWAMs abstract index Unclassified (This Report)

Unclusified 15 NLNUh8 OF PAGLS

16. 'rmsCE NRC FORM PS (2-80)

__.a-m,-_.-

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w b

THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER

1 UNITED STATES NUCLEAR REOULATORY COMMCSION WASHINGTON, D.C. FJ!%

FIR $T 5 M AI J'?"Jan'0! a.

j"*

Main Citations and Abstracts gosygiU 1-1 1ANIACIA51cv1 IN bod #.gt;pg8LICATtoNS 8

SVCS p-223 WASHINGTON DC 20555 Secondary Report Number Index Personal Author Index Subject frdex NRC Originating Organization index (Staff Reports)

NRC Originating Organization Index (International Agreements) s NRC Contractor Sponsor index 2

x r

Contractor index International Organization Index 1

Licensed Facliity

Index

_ _..