ML20082C711

Regulatory and Technical Reports (Abstract Index Journal). Compilation for First Quarter 1991,January-March

ML20082C711
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Issue date:	06/30/1991
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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NUREG-0304, NUREG-0304-V16-N01, NUREG-304, NUREG-304-V16-N1, NUDOCS 9107220276
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NUREG-0304 Vol.16, No.1

=

Regula~ory anc Tecanical Recor:s (Abstrac~ Inc ex Journal)

Compilation for First Quarter 1991 January - March U.S. Nuclear Regulatory Commission OITice of Administration

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W 2E8Rie ' 'PDR 0304 R

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

Single copies of this publication are availLble from National Techrtical Information Service, Springfield, VA 22161 4

1 NUREG-0304 Vol.16, No.1 P

Regulatory and Technical Reports (Abstract Index Journal)

Compilation for First Quarter 1991 January - March Date Published: June 1991 Regulatory Publications Branch Division of Freedom ofInformation and Publications Services Office of Administration l

U.S. Nuclear Regulatory Commission

. Washington, DC 20555

1 CONTENTS Preface.

.. v index Sb Main Citations and Abstracts.

1

• Staff Reports

• Conference Proceedings

• Contractor Reports

• International Agreement Reports Secondary Report Number index.

.2 Personal Author index.,...,

.3 Subject index....

.4 NRC Originating Organizatinn index (Staff Reports).

.5 NRC Originating Organization index (Internatioital Agreements).

6 NRC Contract Sponsor Index (Contractor Reportm.

.7 Contractor index..........

.8 International Organization Index.

9 Licensed Facility index.

... 10 iii

PREFACE This compilation consists of bibliographic data and abstracts for the fortnal regulatory and 19chnical reports issted 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 comrnants will be ap-preciated. Please send them to:

Technical Publications Section Regulatory Publications Branch Division of Freedom of Information and Publications Services P-223 U.S. Nuclear Regulatory Commissbn 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 Indux Personal Author index Subject Index NRC Ori,J nating Organization Index (Staff Reports) i NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor Index (Contractor Reports)

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

T he bibliographic elements of the tuain citations are the following:

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

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

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

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

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled 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 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 number, (2) report title, (3) report authors, (4) organiz-tional unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the or:ginating organization (if given), and (9) the microfiche address (for NRC internal use).

v

_r.___

I l

l International Agieement Report.

NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL.

DATA. NEUMANN, U. Kraftwerk Union. August 1986. 223 pp. 8608270424. 37659:138.

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

^ The following abbreviations are us<,d to n. >ntify the document status of a report:

ADD' - addendum APP appendix DRFT. draft ERR

- crrata N

number R

revision S

supplement V

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

Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013 7082

.You may charge any purchase to your GPO Deposit Account, MasterCard charge ca:d, or VISA charge card by calling the GPO on (202)275-2060 or (202)275-2171. Non-U.S. customers must make payment in advt. ace either by international Postal Money Order, payable to the Superintendent of Documenis, or ty draft on a United States or Canadian bank, payable to the Superintendent of Documents.

NRC Report Codes -

. The NUREG designation, NUREG-X.XXX, indicates that the document is a formal NRC staff-generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of ider,tification 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 ana NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is used for international agreement reports.

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

vi l

Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is an NRC staff originated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CH XXXX is an NRC contractz-prepared report, and NUREG/lA XXXX is an inter-national agreement re1 ort, The bibliographic information (see Preface for details) is followed by a brief abstract of tais report.

sub oct. NRC organslation for staff and international agree-NUFIEGOO40 V14 N04: LICENSEE CON'i R ACT OR AND l

VENDOR INSPECTION STATUS REPORT. Quaqorly monts contractor, international organization, and hconsed facih-Report. October-December 1990.(White Book)

• Division of Ro-ty.

NUREG-0366 DOS R09: UNITED STATES WCLEAR REGULA.

2 pp 910 075 2 12 TORY COMMISJION STAFF PRACTICE AND PROCEDURE T his penodical covers the results of inspections periormed by DIGLST Commisson, Appeal Doard At d Licensing Board the NRC's Vendor Insooct,on Branch that have been distnbuted to the inspected organt28tions during the penod from October Decisions. July 1972 - September 1990

• Office of the Genoral Counsel (Post 860701). February 1991 573pp. 9103200069.

1990 through December 1990.

57064 001.

NUREG 0090 V13 NO3: REPORT TO CONGRESS ON ABNOR.

This Revision 9 of the fifth editon of tro NRC Practico and MAL OCC RRENCES. July-Soptember 1990.

• Office for Analy-Procedure Digest contains a digest of a nu nber of Commission, sis & Evaluation of Operational Data, Director. January 1991.

Atomic Safety and Licensing Appeal Boarti, and Atomic Safety 35pp 9102250192. 56789 010 and Licensing Board decisions issued dunng the penod of July Section 208 of the Energy Reorganization Act of 1974 ident

1,1972 to September 30,1990, interpreting it e NRC's Rules of hes an abnormal occurrence as an unscheduled incident or Practico in 10 CFR Part 2 ovent which the Nuclear Regulatory Commisson determnes to Do sigruficant from the standpoint of public health and saloty NUREG-0430 V10: LICENSED FUEL MACILITY STATUS and requires a quarterly report of such events to be made to P.EPORT. Inventory D'fference Data July 1909 June 1990 (Gray Congrnss. This report covers the portod July 1 through Septem-Dook 11) OROWN.C.; JOY,0 Office of Nucle ar Matonni Safety &

bor 30,1990. The report discusses six abnormal occurrences.

Saieguards February 1991.18pp. 9103200116 57066152-none of which involved a nuclear power plant. There were twe NRC in committod to the ponodic pubitct tion of licensod fuel abnormal occurrences at NRC licensed f acilities one involved a facil,tios inventory differenco data, followirg agency review of medical therapy misadministration; three involved modical diag-the information and completion of any rol.nted NRC investiga-nostic misadministrations; and one involved a squficant break-tions. Information in this report includes 4nventory difference down in management and procedural controls at a medical facil-data for active fuel fabncaton facilities pcssessing more than ity. The sixth abnormal occurrence was repor1ed by an Agroe-one effectwo kilogram of high enriched ur tnium, low ennched mont State (Anzona); the event involved a medical therapy mis-uranium, plutonium, or uranium.233 administration.

NUHEG-0540 V12 N11: TITLE LIST OF 0")CUMENTS MADE NUREG 0090 V13 N04: REPORT TO CONGRESS ON ADNOR-PUBLICLY AVAILABLE November 1-30,1990

• Divtsion of MAL OCCURRENCES.Octobor-DecemMr 1990.

• Office fo' Freedom of Intwmaten & Publicahons Sonicos (Post 890205).

Analysis & Evaluation of Operatonal Cata, Director March January 1991. 293pp. 9102040312. 56570 2 79.

1991. 24pp. 9104040281. 57260 302.

This document is a monthly publication containing desenp-Section 200 of the Energy Reorganaation Ac' of 1974 idanti-tions of information received and generated by the U S. Nuclear fios an abnormal occurrence as an unscheduled incident or Regulatory Commission (NRC). This infor nation includes (1) event which the Nuclear Regulatory Commission determines to dockelod matonal associated with civilian ruclear power piants be signiftcant from the standpoint of public health and safety and otner uses of radioactive matenals, aid (2) nondocketod and requires a quarterly report of such events to be made to material tocowed and generated by NRC pe rtinent to its role as Congress. This report covers the pered October 1 through De-a re ulatory agency The following indenei are includod Per-cember 31, 1990. The repor1 discusses five abnormal occur-sonal Author, Corporato Sourco, Report IJumber, and Cross rences, none of which involved a nuclear power plant. Two in-Reference to Principal Documents.

volved signihcant overeuposures to the hands of two radio-graphets, two involved medical therapy misadministrations, and NUREG 0540 V12 N12: TITLE LIST OF DJCUMENTS MADE one invetvod a rnedical Ngnostic mmadministratior: No abnor-PUBLICLY AVAILABLE. December 131, 1990

• Division of mal occurrences were reported by the Agreement States The Freedom of Information & Publications Soruices (Post 890205) report also contains information that updates a prevlCJSly re-February 1991,337pp 9102280245 56835.269.

ported abnormal occurrence See NUREG 0540,V12.N11 abstract.

NUREG-0304 V15 N04: REGULATORY AND TECHNICAL RE' NUREG-0540 V13 N01: TITLE LIST OF EOCUMENTS MADE PORTS (ADSTRACT INDEX JOURNAL). Annual Compilation PUBLICLY AVAILABLE. January 131,199'

• Duision of Froo-For 1990.

• Division of Freedom of information & Publications dom of nformaton & Pubhcatons Servcos (Post 890205).

Services (Post 890205) March 1991 137pp 9104040288-March 199 t. 330pp. 9103260124. 57153 00 5, 57261:003-See NUREG-0540,V12,N11 abstract.

This journal includes all formal reports in the NUREG senes prepared by the NRC staff and contractors, proceedings of con-NUREG-0725 R07: PUBLIC INFORMATION CIRCULAR FOR fernnces and workshops; as well as international agrooment rm SHIPMENTS OF IRRADIATED REACTOR FUEL

• Dwision of ports. The entnos in this compilat,on are indexed for access by Safeguards & Transportation (Post 870413) January 1991, title and abstract, secondary report number, personal author.

32pp 9102060142. 56593.209 1

2 Main Citations and Abstracts This circular has been prepared to provide information on the This report contains the fiscal year budget justifications to shipment of irradiated reactor fuel (spent fuel) subiset to regula.

Congress. The budget provides estimates for satanes and ex-tion by the Gclear Regulatory Commsssion (NRC), and to moet penses and for the Office of the inspsctor General for fiscal the requirements of Public Law 96-295. The report provides a years 1992 - 1993-bnef desenption of NRC authority for Certain aspects of trans-porting spent tuel. It provides desenptive stabstics on +. pent fuel NUREG 1150 V03: SEVERE ACCIDENT h!SKS: AN ASSESS-shipments regulated by the NRC from 1979 to 1989. It also lists MENT FOR FIVE U.S. NUCLEAR POWER PLANTS. Appendices detailed highway and railway segments used within each state D And E.hnal Report.

• Division of Systems Resea ch (Post trom October 1.1987 through December 31,1989, 880717). January 1991. 93pp. 9102200273. 56744:039.

NUREG-0750 V32 N05: NUCLEAR REGULATORY COMMISSION This report summanzes an assessment of the risks from ISSUANCES FOR NOVEMBER 1990, Pages 333-393.

• Division severe accidents in five commercial nuclear power plants in the of Freedom of Information & Publications Services (Post United States. These risks are measured in a number of ways, 890205). January 1991, 69pp. 9102040314, 56571:212.

Including' the estimated frequencies of core damage accidents Legalissuances of the Commission, the Atomic Safety and U-from internally initiated accidents, and ertemally initiated acci-censing Appea! Panel, the Atomic Safety and Ucenstng Board dents for two of the plants; the performance of containment Panel, the Administrative Law Judges, and NRC Program Of, structures under severe accident loadings; the potential magni-fices are presented.

tude of radlonuchde releases and offsite consequences of such accidents, and the overall NSk (the product of accident frequen.

NUREG-0750 V32 N06: NUCLEAR REGULATORY COMMISSION cies and conseauences). Supporting this summary report are a ISSUANCES FOR DECEMBER 1990. Pages 395-496.

• Division large number of reports wntten under contract to NRU which of Freedom of informaton & Publicatons Sennces (Post provide the detailed discussion of the melnods usod and resufts 890205). February 109 t.109pp. 9102280236. 56837:023-obtained in these nsk studies. Volume 3 of this report con *ains See NUREG-0750,V32,N05 abstract-two appendices. Appendix D summartzes comments received NUREG-0750 V33 N01: NUCLEAR REGULATORY COMMISSION and staff responses on the first (Fobruary 1987) draft of ISSUANCES FOR JANUARY 1991. Pages 1-60.

• Division of NUREG-1150. Appendix E provides a similar summary of com-Freedom of information & Publicatons Services (Post 890205).

ments and responses, but for the second (June 1989) version March 1991. 67pp. 9103270034. 57158:181.

of the repo *,

See NUREG 0750,V32,N05 abstract.

NUREG-1199 R02: STANDARD FORMAT AND CONTENT OF A NUREG 0933 S12: A PRIORITIZATION OF GENERIC SATETY LICENSE APPLICATION FOR A LOW-LEVEL RADIOACTIVE ISSUES. EMRIT.R.; RIGGS R.; MILSTEAD,W.; et a!. Division of WASTE DISPOSAL FAMLITY,

• Division of Low Level Waste Regulatory Applications (Post 870413). January 1991, 265pp.

Management & Decomnnsioning (Post 870413). January 1991, 9101300169. 56536:018-30pp. 9102200275. 56744.132.

The report prosants the pnonty rankings for genene safety The Standard Format and Content of a License Application issues related to nuclear power plants. The purpose of these for a Low Level Radioactive Waste Disposal Facility, NUREG-rankings is to assist in the bmely and efficient allocation of NRC 1199, discusses the information to be provided in the Safety resources for the resolution of those safety issues that have a Analysis Report and establishes a uniform format for presenting significant potential for reducing r:sk. The safety prionty rankings the information required to meet the licensing requirements for are HIGH, MEDtVM, LOW, and DROP and have been assigned land disposal of radioactive waste as required by 10 CFR 61, on the basis of risk significance estimates, the ratto of risk to The use of the Standard Format will (1) help ensure that the costs snd other impacts estmated to result if resolutions of the Safety Analysis Report (SAR) contains the informabon required safety issues were implemented, and the consideration of un-by 10 CFR 61, (2) aid the applicant in ensunng that the informa-certainties and other quanttative or qualitative factors. To the extent practical, estimates are quant tative.

tion is complete, (3) help persons reading the SAh to locate in-formabon, and (4) contribute to shortening the time required for NUREG-0936 V09 N04: NRC REGULATORY AGENDA.Ouarterly the review process. The Standard ' Format and Content

Report, October December 1990.

• Division of Freedorn of Infor-(NUREG.1199) ensures that the information required to perform mation & Publicahons Services (Post 890205). January 1991.

the review is provided, and in a usable format while the Stand-149pp. 9102250195. 56789.215.

ard Review Plan, NUREG-1200, defines the technical review The NRC Regulatory Agenda is a compilation of all rules on

process, which the NRC has proposed or is considenng action and all peut ons for rulemaking which have been received by the Com.

NUREG 1200 R02: STANDARD REVIEW PLAN FOR THE mission and are pending disposition by the Commission. The REVIEW OF A LICENSE APPLICATION FOR A LOW LEVEL Regulatory Agenda is updated and issued each quarter.

RADIOACTIVE WASTE DISPOSAL FACILITY,

• Division of Low-Level Waste Management & Decommissioning (Post NUREG-0940 V09 N04: ENFORCEMENT ACTIONS: SIGNIFI' A70413). January 1991,185pp. 9102200281. 56743:214.

CANT ACTIONS RESOLVED.Ouarterfy Progress Report. October December 1990.

• Ofc of Enforcement (Post The Standard Review Plan (SRP) is prepared for the guld-ance of staff reviewers in the Office of Nuclear Material Safety 870413). February 1991. 389pp. 9103050496. 56876:354.

.This compilation summarizes significant enforcement actions and Safeguards in performing safety reviews of applications to construc* and operate a lowlevel waste disposal facility. The that have been resolved dunng one quarterty period (October -

December 1990) and includes copies of letters, Notices, and rincipal purpose of the SRP is to assure the quality and uni-Orders sent by the Nuclear Regulatory Commission to licensees formity of staff reviews and to present a well-defined taso from which to evaluate proposed changes in the scope and require-with respect to,hese enforcement actions,11 is anticipated that ments of reviews. It is hiso a purpose of the SRP to make infor.

t the information in this publication will be widely disseminated to mation about regulatory matters widoty available and to improve managers and employees _ engaged in actnnties heensed by the NRC, so that actions can be taken to improve safety by avoid-communication and understanding of the staff's review process by interested members of the public and the nuclear industry.

ing future violations similar to those desenbed in this publica-NUREG 1200 consists of 11 chapters containing approximately I

bon.

60 individual SRP sectons. Each secton identifies who per-NUREG-1100 V07: BUDGET ESTIMATES Fiscal Years i992-forms the review, the matters that are reviewed, the basis for 1993.

• Division of Budgei & Analysis (Post 890205). February review, how the review is performed, and the conclusions that 1991.185pp. 9102110174. 56653:037.

are sought.

Ma5 Citations and Abstracts 3

NUREG-1214 R07: HISTORICAL DATA

SUMMARY

OF THE SYS-Central Power & Light Company for the Oyster Creek Nuclear TEMATIC ASSESSMENT OF LICENSE E PERFORMANCE.

Generahng Station has toen prepared by the Office of Nuclear ALLE NSPACH.F Dwison of Lkensee Performance & Quality Reactor Regutation of the U.S. Nuclear Regulatory Commission Evaluation (Post 870411) February 1991 117pp. 9103120085.

The facihty is located in Ocean County, New Jersey. The staff concludes that the facibty can continue to be operated without

$6948152 The Histoncal Data Summary of the Systematic Assessment endangenng the health and safety of the pubhc.

of Licensee Performance (SALP)is produced penodical'y by the NUREG 139 t: CHEMICAL TOxlCITY OF URANIUM HEXA-U.S Nuclear Regulatory Commission This summary provides the results of the assessment for 6ach facility by NRC region FLOORIDE COMPARED TO ACUTE EFFECTS OF and is further divided into the folhwing sections Sect on 1 pre-RADIATION Final Report. MCGUIRE.S.A. Division of Regulatory sents the most recont SALP report ratings for facilities in oper.

Applications (Post 870413) February 1991.17pp. 9103f 10209.

ation and under construct on. Section 2 presents a chronologi-56942;190.

The chemical effects from acute exposuies to uranium hexa-cal listing of all SALP report ratings for each operating facility.

Section 3 presents a chronological listtag of all SALP report rat-fluonde are compared to the nonstochastic effects from acute radiation doses of 25 rems to the whole body and 300 rems to ings for each f ac6tity under construction. For histoncal purposes, the thyroid The anafysis concludes that an intake of about 10 past constructiori ratings for facihties that recently have been h.

consed also are listed in Section 3.

mg of uranium in soluble form is roughty comparable, in terrns

'}

U' NUREG-1232 V03 S02: SAFETY EVALUATION REPORT ON

' ' "'9" TENNESSEE VALLEY AUTHORITY: BROWNS FERRY NUCLE.

'* * "" "# 8 "Y ' 9""

AR PERFORMANCE PLAN Browns Ferry Unit 2 Restart CU"# "

ROSS.T.M. Division of Reactor ProIects 1/11 (Post 870411)'

ble because there would be no significant nonstochastic effects.

January 1991.123pp. 9102110178. 56652:274-For times t other than 30 minutes, the concentration C of hydro-This safety evaluation report (SER) was prepared by the U S~

gen fluonde considered to have the same effect can be calcu-Nuclear Regulatory Commission (NRC) statt and represents the lated using a quadratic equation C = 25 mg/m(3) (30 min /

second and last supplement (SSER 2) to the staff's original t)(0 5) The purpose of these analyses la to provide information SER published as Volume 3 of NUREG 12% in Apol 1989 Sup-for developing design and siting guidehnes based on chemical piement 1 of Volume 3 of NUREG 1232 (SSER 1) was pub' todcity for ennchment piants using uranium hexafluonde. These lished in October 1989, Uke its predecessors, SSER 2 is com' guidehnes are to be similar, in terms of stochastic health et-posed of numerous safety evaluations by the stati regarding facts, to entena m NRC regulations for nuclear power plants, specite elomonts contained in the Browns Ferry Nuclear Per-which are based on radetion doses formance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the NUREG-1397: AN ASSESSMENT OF DESIGN CONTROL PRAC-Browns Ferry Nuclear Plant (BFN) The Browns Fer'y Nuclear TICES AND DESIGN RECONSTITUTION PROGRAMS IN THE Plant consists of three boiling-water reactors (BWRs) at a site in NUCLEAR POWER INDUSTRY. IMBRO.E.V. Devision of Reactor Umestone County, Alabama. The BFNPP descnbes the correc-Inspection & Safeguards (Post 870411)- February 1991,109pp.

tive action plans and commitments made by TVA to msolve de-9103120091. $M61.249.

ficiencies with its nuclear programs before the startup of Unit 2-This document summanzes the results of a survey of nuclear The staff has inspected and will continue to inspect TVA's im-power plant design control practices and design reconstitution piementation of these BFNPP corrective action plans that ad~

efforts conducted dunng 1989 at six utilities and with one nucle-dress staff concoms about TVA's nuclear programa SSER 2 ar steam supply vendor. Conclusions and observations resulting docurrents the NRC staff's safety evaluations and conclusions from the survey assessments are provided so that utilities and for those elements of the BFNPP that were not prevously ad" the NRC can consider actions to improve these programs.

dressed by the staff or that remained open as a result of unre-solved issues identified by the staff in previous SERs and in-NUREG 1430 V1 DRF FC: STANDARD TECHNICAL SPECIFICA-TIONS BABCOCK AND WILCOX PLANTS. Specificatons Draft spections.

Report r'or Comment.

• Division of Operational Events Assess-NUREG 1275 V06: OPERATING EXPERIENCE FEED 8ACK ment (Post 870411) January 1991. 421pp. 9102190210.

REPORT SOLENOID-OPERATED VALVE 56755 013 PROBLEMS Commercial Power Reactors. ORNSTEIN.H L.

This dratt report documents the results of the NRC staff Office for Analysis & Evaluation of Operational Data. Director.

review of new Standard Teci nical Specifications (STS) pro.

February 1991.116pp. 9103040388. C90-01. 568S0:174.

posed by the Babcock and Wilcox Owners Group The new STS This report highhghts significant operating events involving were developed based on the entena in the intenm Commission observed or potential common mode failures of so(enoid-operat_

Pokcy Statement on Technical Specification improvements for ed valves (SOVs) in U S. plants These events resulted in deg.

Nuclear Power Reactors, dated February 6.1987. The new STS radation or malfunction of multiple trains of safety systems as will be used as bases for individual nuclear power plant owners well as of multipio safety systems On the basis of the evalua-to develop improved plant specific technical specifications. The tion of these events, the Office for Anatysis and Evaluation of NRC staff is issuing this draft new STS for a 30 working day Operatonal Data (AEOD) of the U.S Nuclear Regulatory Com.

comment penod. Following the comment period, the NRC stati mission (NRC) concludes that the problems with solenoid.oper-will analy2e comments received, finalize the new STS. and ated valves are an important issue that needs additional NRC issue them for plant-specific implementation. This report con-and industry attention This report also provides AEOO's recom.

tains three volumes. Volume 1 contains the Specifications for all mendatsons for actions to reduce the occurrence of SOV sections of the new STS. Volume 2 contains the Bases for Snc.

common mrMe failures _

tions 2 0 - 3 3 of the new STS and volume 3 contains the NUREG-1382: SAFETY EVALUATION HEPORT RELATED TO Bases for Sections 3 4 - 3 9 of the new STS.

THE FULL TERM OPERATING LICENSE FOR OYSTER CREEK NUCLEAR GENERATING STATION Docket No 50-NUREG-1430 V2 DRF FC: STANDARD TECHNICAL SPECIFICA-219 (General Public Utilities Nucinar Coro et al)

• Division of Re-TIONS BABCOCK AND WILCOX PLANTS Bases (Soctons 2.0 actor Projects - 1/It (Post 870411) January 1991. 161pp 3.3). Draft Acport For Comment

• Division of Operationaf 0101300226. 56534:121 Events Assessment (Post 870411) January 1991. 370pp.

The Safety Evaluation Report for the full-term operating h-9102199212 56756 074.

cense apphcaton filed by GPU Nuclear Corporation and Jersey See NUP.EG 1430 V01.DAFJC abstract.

4 Main Citations and Abstracts i

NUREG-1430 V3 DRF FC: ST ANDARD TECHNICAL SPECIFICA-NUREG-1432 V3 DRF FC: STANDARD TECHNICAL SPECIFICA.

TIONS B ABCOCK AND WILCOX PLANTS. Bases (Sections 3 4 TIONS COMBUSTION ENGINEERING PLANTS Bases (Sec.

3 9) Draft Report For Comment Dmson of Operatona!

tons 3.4 3 9) Draft Report For Comment

• Dmson of Oper-Events Assessment (Post 870411) Jant,ary 1991 471pp.

atonal Events Assessment (Post 870411) January 1991.

9102190214, 56757:084, 528pp 91022002C6 56750.012.

See NUREG-1430,V01,DRF,FC abstract See NRUEG-1432,V01,DRF,FC abstract NUREG 1431 V1 DRF FC: STANDARD TECHNICAL SPECtFICA.

NUREG 1433 V1 DRF FC: STANDARD TECHNICAL SPECIFICA.

TIONS WESTINGHOUSE PLANTS. Specificahons Draft Report TIONS GENERAL ELECTRIC

UNITS, BWR/

For Comment

• Division of Operational Events Assessment

4. Specifications Draft Report For Comment.

• Division of Oper.

(Post 070411). January 1991. 4B4pp 9132140299. 56696 057.

atonal Events Assessment (Post 870411) January 1991.

This draft report documents the results of the NRC staff 485pp 9102140324. 56704 290.

review of new Standard Technical Specifications (STS) pro-This draft report documents the results of the NRC statt posed by the Westinghouse Owners Group. The new STS were review of new Standard Technical Specificalons (STS) pro-developed based on the critena in the intenm Commission posed by the BWR Owners Group for the DWR/4 design. The Pohey Statement on Technical Specification Improvements for new STS were developed based on the critena in the intenm Nuclear Power Reactors, dated February 6,1987. The new STS Commission Policy Statement on Technical Specificaten Im-will be used as bases for ind'viotal nuclear power plant owners provements for Nuclear Power Reactors, dated February 6, 1987. The new STS wil! be used as bases for Individual nuclear to oevelop improved plant-specific technical specifications The NRC statt is issuing this draft new STS for a 30 working-day power plant owners to develop improved plant-specific technical comment penod. Following the comment penod, the NRC staff specifications. The NRC staff is issuing this drafi new STS for a will analyze co mments received, finalize the new STS, and 30 working-day comment penod. Folloeng the comment penod, issue them f-

. iant-specific implementation This report con.

the NRC statt will analyze comments received, finalize the new tains three volumes. Volume 1 contains the Specifications for all STS, and issue them for plant specific implementation This sectons of the new STS Volume 2 contains the Bases for Sec.

report contains threa volumes. Volume 1 contains the Spec 6ca-tions for all soctiors of the new STS. Volume 2 contains the tions 2 0 - 3.3 of the new STS and Volume 3 contains the Bases for Sectons 2.0 3.3 of the new STS and Volume 3 con-Bases for Sections 3.4 3 9 of the new STS, tains the Bases for Sections 3 4 - 310 of the new STS.

NUREG-1431 V2 DRF FC: ST ANDARD TECHNICAL SPECIFICA-NUREG 1433 V2 DRF FC: STANDARD TECHNICAL SPECIFICA-TIONS WESTINGHOUSE PLANTS. Bases (Sections 20-TIONS GENERAL ELECTRIC UNITS, BWR/4. Bases (Sections 3.3) Draft Report For Comment.

Dmson of Operational 2.0 3.3). Draft Report For Comment.

• Dmston of Oputational Events Assessment (Post 870411) January 1991. 387pp.

Events Assessment (Post 870411), January 1991. 419pp.

9102140309. $6697;181 See NUREG-1431,V01.DRF,FC abstract.

S N REG 1433 0,DRF,FC abstra::t.

NUREG-1431 V3 DRF FC: STANDARD TECHNICAL SPECIFICA-NUREG 1433 V3 DRF FC: STANDARD TECHNICAL SPECIFICA.

TiONS WESTINGHOUSm PLANTS. Bases (Sections 3.4-TIONS GENERAL ELECTRIC UNITS. BWR/4. Bases (Sections 3 9).Drus Report For Comment.

Dmsson of Operational 3 4 - 3.10) Draft Report For Comment.

• Dmson of Operational Events Assessment (Post 870411). January 1991. 644pp' Events Assessment (Post 870411). January 1991. 475pp.

9102140312. 56694,101.

9102140295. 56702.116 See NUREG-1431,V01,DRF,FC abstract.

See NUREG 1433,V0kDRF,FC abstract.

NUREG-1432 V1 DRF FC: STANDARD TECHNICAL SPECIFICA.

NUREG-1434 VI DRF FC: STANDARD TECHNICAL SPECIFICA-TIONS COMRUSTION ENGWEERING TlO V GENERAL ELECTRIC

PLANTS, BWR/

PLANTS Specificatons Draft Report For Comment.

• Divison of 6 Specificatons. Draft Peport For Comment.

• Dmsion of Oper.

Operationa! Eveats Assessment (Post 870411) January 1991 ational Events Assessment (Post 870411). January 1991.

518pp. 91022C*257, 56753'020.

497pp. 9102200248. 56747.088.

This draft reprt documents the asults of the NRC staN This dratt report documents the results of the NRC staff review of new Standard Technical Specifications (STS) pro, review of new Standard Technical Specifications (STS) pro-posed by the Combustion Engineenng Ovners Group. The new posed by the BWR Owners Group for the BWR/6 design. The STS were developed based cn the cnterb in the intenm Com-new STS were developod based on the critena in the intenm mission Policy Statement on Technical Sacification improve'.

Commission Policy Statement on Technical Specificaton im-ments for Nuclear Power Reactors. datec February 6,1907 provements for Nuclear Power Reactors, dated February ti, The new STS will be used as bases for inom1ual nuclear power 1987. The new STS will be used as bases for individual nuclear plant owners to develop improved plant-spect'ic technical speci-power plant owners to develop Improved plant-specific technical fications, The NRC staff is issuing this draft new STS for a 30 specificatons. The NRC staff is issuing this craft now STS for a woriang-day comment penod. Following the comment period-30 working-day comment period. Following the commerit period, the NRC staff will analyze comments received, finahze the new the NRC staff will anaiyze comments received, finalize the new STS, and issue them for plant-specific implementation. This STS, and issue them for plant specific implementaten. This report contains three volumes. Volume 1 contains the Specifica-report contains three volumes. Volume 1 contains the Specifica-tions for all sections of the new STS Volume 2 contains the tons for all sections of the new STS Volume 2 contains the Bases for Sections 2.0 - 3.3 of the new STS and Volume 3 con-Bases for Sectons 2.0 3.3 of the new STS and Volume 3 con-tains the Bases for Sections 3 4 - 3 9 of the new STS tains the Bases for Sections 3.4 310 of the new STS NUREG-1432 V2 DRF FC: STANDARD TECHNICAL SPECIFICA-NUREG-1434 V2 DRF FC: STANDARD TECHNICAL SPECIFICA-TIONS COMBUSTION ENGINEERING PLANTS Bases (Sec-TIONS GENERAL ELECTRIC PLANTS, BWR/6 Bases (Sectons tions 2.0 - 3.3). Draft Report For Comment.

• Dmsson of Oper-2.0 - 3.3) Draft Report For Corwment.

• Dmsion of Operatonal atonal Events Assessment (Post 870411). January 1991 Events Assessrrent (Post 870411). January 1991, 447pp.

560pp. 9102200262. 56751:180.

910220025 t. 56746 001.

See N'JREG 1432.V01,DRF,FC abstract.

See NUREG 1434,V01,DRF,FC abstract.

I Main Citations and Abstracts 5

NUREG 1434 V3 DRF FC: STANDARD TECHNICAL SPECIFICA~

This document conteins the papers and the associated dis-TlONS GENERAL E i EC1RIC Pt ANTS, BWR/6 Bases (Sections cussions of the 21st DOE /NRC Nuclear Air Cleaning Confer.

3 4 - 310) Draft Report For Comment

• Division of Operational ence Major topics arti (1) chemica! processing systems, (2) re-Events Assessment (Post 870411) January 1991 496pp actor operations (3) incineration and vitnfication. (d) particulate filter developments. including fitter testeng and response to 9102200:54. 56748 225 phywcal and temperaturo stress, (5) adsorption and testing of See NUREG-1434,V01.DRFJ C abstract NUREG 1435 V01: STATUS OF SAFETY ISSUES AT LICENSED mitigahnn including modehng of emergency response systems.

POWER PLANTS TM1 Acton Plan Requiremsnts.

• Program (7) nuclear waste management systems. (8) carbon 14 removal, Management, Pohey Development & Analysis Statt (Post (9) monitonng and measurement systems, (10) the developmerit 870411) Marct.1991 872pp 9104080296 57295 063 of standards and reguletions and r,ncerns with einsting stand.

As part of ongoing U S Nuclear Rogulat]ry Comnusson ards and regulations, and (11) imclear av cleaning activites (NRC) efforts to ensure the quality and accountability of safety around the world issue information, a program has been estabhshnd whereby an annual NUREG renes repo-t will be pubbshed on the ttatus of NUREG/CP-0116 V02: PROCLES.dGS OF THE 21ST DOE /NPC licensee implementation and NRC verihcation of saiety issues in NUCLLAR AIR CLEANING CONFERENCE SESSIONS 9 16 Held in San Diego, Cahfornia. August 13 f 6, 1990 major NRC requiremont areas The data conened in this report FIRSLM W. Harvard School of Pubhc Health, Roston, MA f eb-are a product of the NRC's Salety issues Management System database, which is maintained by the Proiect Management Staff ruary 1091. 484pp 9103200094 CONF.900813 57061.001.

in the Othce of Nuclear Reactor Regulation and by personnel in See NUREG/CP4116.V01 abstract the NRC regions This report has been prepared in order to pro.

NUREQ/CR 2000 V09N12: LtCENSEE EVENT REPORT (LFR) vide a comprehensive descnpton of the implemoritaton and COMPILATION For Month Of December 1990 ' Oak Ridge Na-venhcation status of all the TMI Action Plan requirements at h.

tonal Laboratory January 1991 B2pp. 9102140277 DANil consed ruactors, and to make this information available to other NSIC-200 56M3 231 interested parties, including the public. A corollary purpose of This monthly report contains Licensee Event Report (L ER) this report is for it to serve as a follow on to NUREG-0933, "A operational information that was processed into the LER data Pnoritaation of Genenc Safety tasues," which tracks safet)

Ide of the Nuclear Safety information Center (NSIC) dunng the issues up untd requirements are approved for impostion at h.

w month penod identified on the cover of the document The censed f acihties.

LERs, from which this information is denved, are nubrnitted to NUREG/CP-0037: PROCEEDINGS OF THE SE MINAR ON AS-tt 9 Nuclear Regulatory Commission (NRC) by nuclear power SESSMENT OF FRACTURE PREDIC1 TON TECHNOLOGY plant licensees in accordance with federal regulations. Proco-PIPING AND PRESSURE VESSELS-R!SER.A L; dures for LER reporting for revisions to those events occurnng MAYFIELD.M E Office of Nuclear Regulatory Research (Post poor to 1964 are descobed in NRC Regulatory Guide 1.16 and 860720L February 1991 334pp 9103050499. 56880187, NUREG-0161, " Instructions for Preparation of Data Entry The 1990 Pressure Vessel and Piping Conference, sponsored Shoots for Licensoe Event Reports." for those events occumng by the Amencan Society of Mechanical Engineers (ASME). was on and after January 1,1984 LERs are being submitted in ac-held in Nashville, Tennessee from June 18 to June 21,1990 As cordance with the revised ruto contained in Title 10 Part 50 73 part of that conterence, representatives from the USNRC and of the Code of Federal Rogulations (10 CFR bo 73 Licensee AEA Technology in the United Kingdom jointly organized two Event Report System) whicf was published in the Federal Rog-panel sessions to dmcuss the current state of fracture prediction ister (Vol 40, No.144) on July 26,1983 NUREG 1022, "Li-technologies for piping and pressure vessels. A total of nine consee Event Report System Desenption of Systems and presentations were given, contrasting analytical predictions with Guidehnes for Reporting," provides supporting guidance and in-expenmontal re?ults. This document provides summanos of formation on the revised LER rule. The LER summaries in this each presentation and copies of the pertinent figures and other report are arranged alphabetically by facehty riamo and then visual aids This information has been compiled and pubbshed chronok)gically by event date for each facihty. Component, to permit reasonably prompt disseminations of the information system, keyword, and component vendor indexes fo!!ow the summanes. Vendors are those sdentified by the utihty when the pretiented. Based on the information presented dunng these two panel sessions, it appears that, while the current state of LER form is initiated. the keywords for the Component, systern, fracture prediction technology is reasonabiy wall advanced, and general licyword indexes are assigned by the computer more work is needed to provide analysis methods capable of using correlation tables from the Sequence Coding and Search accurately predeting ductile crack extension-Systern.

NUREG/CP-0115: PROCEEDINGS OF THE CSN1 WORKSHOP NUREG/CR 2000 V10 N1: LICENSEE EVENT REPORT (LER)

ON PSA APPLICATIONS AND LIMIT ATIONS. MOLIN A T.

COMPILATION For Month Of January 199f.

• Oak Ridge Na-Sandia National Laboratones February 1991 485pp.

tional Laboratory February 199L Gspp 9103200049 ORNL/

9103040390. SAND 90 2797. 50 M096 NSIC-200 57065-214.

This report contains the full papers submitted to the Commit-See NUREG/CR-2000,V09,N12 abstract tee on the Safety of Nuclear instaHations Workshop on Probabi-NUREG/CR 3145 V09: GEOPHYSICAL INVESTIGATIONS OF stic Safety Assessment (F SA) Apphcations and Umitations

.T HE-WESTERN OHIO-INDI AN A REGION Annual held in Santa Fe, New Mexico, USA, on September 4 through 6 Report. October 1980 September 1990 MEERT.JJ RUFF.L; 1990 The purpose of the Workshop was to provide an avenue LAFORGE,R ; et c Michigan, Univ. of, Ann Arbor, MI January for discussions in the following areas- (1) current PSA results, 199 L 42pp 9103260132. 57152 34'l (2) current uses of PSA, (3) views on current hmitations, (4)

Earthquake activity in the Western Ohio Indiana region has expert opinion; and (5) low probabihty numbers The papers been morutored with a precision seismograph network consist-contained herein address these issues, along with several other ing of nine stations located in west central Ohio and four sta-related topics tions located in Indiana Two local earthquakes have been re-NUREG/CP 0116 V01: PROCEEDINGS OF THE 2IST DOE /NRC corded dunng this rooort penod with magnitudes of 1.Om(L) and NUCLEAR AIR CLEANtNG CONFERENCE Sessions 1 - 0 Held 2 2 m(l) Two near-regonai events woro recorded by the not-in San Diego. Cahfornia, August 13-16. M90 FIRST,M W Har-work (Fostona, Ohio and Chnton, Ilknois eventM wrtt rnagne vard School of Pubhc HeaNh, Ooston. MA February 1991 tudes of 2 3 m(L) and 3 4 m(b)llg) Three other regional events occurred with magnitudes ranging from 2 9 m(b) to 4 6 m(b). All 564pp 9103200077 CONF 900813 57059153

.,i

l 6

Main Citations and Abstracts the regional events occurred in, or near, regions with well-estab-analyzed The fnchonal interface strength of an axially loaded lished histones of seismicity, borehole plug, the effect of axial stress and lateral external stress, and thermal effects are also analyzed. Implications for NUREG/CR 3916: PRESSURIZED MELT EJECTION INTO WATER POOLS. TARBELL,W W.; PILCH M. Sand,a National plug design are discussed. The main conclusion is a strong rec-Laboratones. ROSS.J W.: et al. Ktech Corp. March 1991.

ommendation to design inction plugs in shafts, drifts, tunnels, or 110pp. 9103260215. SAND 841531. 57161:230.

boreholes with a minimum length to diameter ratio of four. Such This feport describos five experiments that were performed to a geometncal design will reduce tensile stresses in the plug and study the influence of water pools on the behavior of pressure in the host rock to a level which should minimize the nsk of driven tretts. Four of the tests used knear scaled models of re.

long term deterioration caused t>y excessive tensile stresses actor cavtt:es. The core simulant was a molten mixtura of alumi-Push-out tests have been used to oetermine tne bond strength na and iron created by a metatiothermitic reaction. In all expen-by applying an axial load to cement plugs emplaced in bore-ments. the pressure-driven jet interacted er,ergetically with the holes in welded tuff cyhnders A total of 130 push.out tests water pool. The apparatus containing the water pool was de.

have been performed as a function of borehole size, plug stroyed in all cases, showing clear evidence of a violent fueh length, temperature, and degree of saturation of the host tuff.

coolant interaction. Pressure records and high speed framing The use of four different borehale radii enables evaluation of camera data were attempted in each test. The recorded pres.

size effects A well-oefened exponential strength decrease with sure waveforms appear to conelate with previous steam explo.

increasing plug diameter results. While these extrapolated sion expenments.

Strengths can be used for the de9gn of large diameter plugs, e g, in shafts or drifts, it would be desirab!e to confirm the ex-NUFNCR 42J5: SELECTION OF SILIOEOUS AGGREGATE trapolations by tests on larger plugs.

FOh ' 9NCRETE. CLIFTON,J.R.; KNAB,L National Institute of Standards & Tochnology (formerty Natiorial Bureau of Ods. Jan.

NUREG/CR-4444: RADIATION SAFETY ISSUES RELATED TO vary 1931. 22pp. 9102060171. NISTIR 4327,56651:156.

RADIOLABELED ANTIBODIES. BARBER,DE.; BAUM.J.W.;

Alkali-aggregate expansive reactions are one of the potential-MEINHOLD.C.B. Brookhaven Nationa! Laboratory. March 1991.

ly senous degradaton problems that could affect the structural 208pp.9104040200. BNL-NUREG-52275. 57261:140.

stability of underground concrete structures for disposing of low-Techniques related to the use of radioiabeled antibodies in level radioacttve wasto (LLW). It appears that all aggregates humans are reviewed and evaluated in this report. It is intended react to some degree with alkalles in cement. In the majonty of as an informational resource for the U S. Nuclear Regulatory cases the reactions are beneficial (e g., increasing the tiond be-Commission (NRC) and NRC licensees. Descnptions of tech-tween aggregate and hydrated cement paste) or innocuous. In niques and health and safety issues are provided. Pnncipal some cases, however, the reactions result in the formation of methods for labeling antibodies are summanzed to help identify expansive products which can cause sonous cracking of the related radiation safety problems in the prwaration of dosages concrete. This report deals with the selection of siliceous aggre-for administration to patients. The desenpbons are darived from Dates to avoid deletonous alkali-aggregate expansions. Current ari extensive literature review and consultations with experts 6n pracfices used to prevent expansive alkali silica reactions and the field. A glossary of terms and acronyms is also included An the standard test methods used to identify reactive aggregates assessment was made of the extent of the involvement of orga-are first discussed. Then the results of a study on using a new nizations (other than the NRC) with safety issues related to re-alkalbsalica reactivity test to select sihceous aggregates for use diolabeled antibodios in order to idenbfy regulatory issues which in the conemte of LLW disposal structures are presented. It is require attention. Federal regulations and guides were also re-recommended that siliceous aggregates, selected for construct-viewed for their relevance. A few (but significant) differences in0 underground vaults for disposal of LLW, have an expansion between the use of common radiopharmaceuticals and radiola-of less than 0.10 percent using the new test.

beled antibodies were observed. The clearance rate of whole, NUREG/CR4269: MODELS OF TRANSPORT PROCESSES IN radiolabeled immunoglobulin is somewhat slower than common CONCRETE. POMMERSHEIM J.; CLIFTON.J.R. National bsti.

radiopharmaceuticals, and new methods of administration are tute of Standards & Technology (formerty National Bureau of being used. New nuclides are being used or considered (e g.,

Stds. January 1991. 104pp. 9101300151. NISTIR 4405.

Re-186 and At-211) for labeling antibodies. Some of these nu-56535:024, clides present new dosimetry, instrument calibration, and patient management problems. Sub ects related to radiation safety that l

An approach being considered by the U.S. Nuclear Regula.

tory Commission for disposat of low-level radioactive waste is to require additional research are identified.

place the waste forms in concrete vaults buned underground.

NUREG/CR< 4670: RADIONUCLIDE DISTRIBUTIONS AND Ml-The vaults would need a service hfe of 500 years. Approaches GRATION MECHANISMS AT SHALLOW LAND BURIAL for predicting the service life of concrete of such vaults include SITES Final Report Of PNL Research investigations On The the use of mathematical models. Mathematical models are pre-Distnbution, Migration, And Containment Of Radionuclides At sented in this report for the major degradation processes antici-Maxey

Flats, Kentucky.

KIRBY,L.J.;

TOSTE,A.P.;

pated for the concrete vautts, which are corrosion of steel rein-THOMAS,C.W.; et al. Ba'telle Memonal institute, Pacific North-forcement, sulfate attack acid attack, and teaching. The models west Laboratory. February 1991. 95pp. 9103120103. PNL 7582.

mathematica!!y represent rate controlling processes including 56948.269 diffusion, convection, and reaction and socotton of chemical Dunng the past several years. Pacific Northwest Laboratory species. Those models can form the basis for predicting the life (PNL) has conducted research at the Maxey Flats Disposal Site of concrete under in-servtce conditions.

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

NUREG/CR-4295: BOND STRENGTH OF CEMENTITIOUS This work has identified the spectrum of radionuclides present BOREHOLE PLUGS IN WELDED TUFF.

AKGUN.H.;

in the waste trenches, determined the processes that were oc-DAEMEN.J.J. Arizona, Univ. of, Tucson, AZ. February 1991, cumng relative to degradation of radioactive material within the 315pp. 9103200031. 57063.039.

bunal trenches, determined the chemical and physical charac-This study includes a systematic investigabon of the bond tenstics of the trench leachates and the chemical forms of the strength of cementatious borehole plugs in welded tuff. Analyti-leached radionuclides, determined the mobility of these radionu-cat and numerical analysis of borehole plug-rock stress transfer clides, investigated the subsudace and surface transport proc-mechanics is performed. The interface strength and deformation esses determined the biological uptako by the native vegeta-are studied as a funcbon of Young's modulus ratio of plug and tion, developed strategies for environmental monitonng. and in-rock, plug length, and rock cylinder outside-to-inside radius vestigated other factors that influence the long.torm fate of the ratio The tens #le stresses in and near an axially loaded plug are radionuchde inventory at the disposal site. This report is a final l

L

i Main Citations and Abstracts 7

i summary of the research conducted by PNL and presents ttm doses weto investigated, using information provided by the in-results and discussions relative to the above investigatNo areas dustry The tasks that give hsgh dosos to these wo<k groups we examined and techniques described that were found to be NUREG/CR 4757: LINE LOSS DETERMINATION FOR AIR SAM.

panicular'y successful in reducing dose Quantitative informaton PLER SYSlEMS GLISSMEYER.J A.; SCHMEL,G A. Batteke x me cent of radawn doses b vanous wo* groups stows Memonal Institute, Pacific Northwest Laboratory. February 1991, that significant numbors of workers in several cntical groups re-105pp 9102200238 PNL 7597. 56836 278.

ce!ve doses greater than 1 and even 2 rom por year, particularly lodine depos: tion can potentially bias the results of radioso-contract personnel and workers at DWR. type plants. The dine air samphng systems To develop guidance and accept, number of radiation workors whose bietsme dose is greater than ance entena for detortrunations of line-loss correction factors, their ago is much less Although the techniques presented the data on lahoratory sampler simulations, field tests on sam-would go some way in reducing doso, it is 1%ely that a sizeabic piers and expenmentally measured iodine deposition rates were reduction to the high dose work groups may require develop-reviewed Sampkng system design features and operating con, ment of now doso-reduction techniques as well as major ditions at several power reactors are discussed Moasurements changes in procedures of iodine deposition rates on vanous air samplot construction matenals were reviewed, and predictel air sampler performance NUREG/CR 5262: ESTIMATION OF CONTAINMENT PRESSURE based on the data was presented Three examplos of field tests tOADING DUE TO DIRECT CONTAINMENT HEATING FOR of air sampler performance for radiciodine were examined A THE 'JION PLANT. TUTU,N K. Brookhaven Nabonal Laboratory.

model of todino depositon and resuspension was entonsively PARK C K Korea Atomic Energy Bescarch Institute reviewed, and suggestions were made for incorporating vanable GRIMSHAW,C.A ; et al Mar 0 rove Consulting, Ltd March 1991.

resuspension ratos Three pnncipal methods for determining re-57 9103260234. BNL NUREG-52101. 57159 239 diciodine hrnloss factors were defined and compared, in plac This report presents the results of a series of calculatons at field tests, laboratory mock up with modelled extrapolations to Brookhaven National Laboratory (BNL) to provide estimates of vanous reinase rate modes, and modelkng based on laboratory the DCH containment pressure loading in the Zion plant sub oct t

data on similar matenals Guidelinos for applying these methods to a wide range of initial conditions and phenomenological as-were givon Research was recommended to determine whether W@N MamW ban cadaWs m W the three methods were comparable so the less expensivo formed using a version of the CONTAIN code with update modi-method could be substituted for the proforted field tests.

fications, which parametncally charactenze DCH phonomena NUREG/CR-4867: RELAY TEST PROGRAM Series l Vibration (CONTAIN-DCH, Version 1.10) The range of calculation param-Tests BANDYOPADHYAY; HOFMAYER,C H, SHTEYNGART,S eters was selected to represent many of the current uncertain-Brookhaven National Laboratory. January 1991. 164pp-ties in DCH initial conditions and uncertainties in modohng DCH 9102250185 BNL-NUREG 52277. 56789 051.

phenomena The parameters vaned in the hensitivity study in.

Brookhaven Nationel laboratory has conducted a test pro-ciuded pnmary system pressure at vessel failure, core moft in-gram on rolays to determine the influence of parameters related ventory, mc1 and steam flow rates through the reactor cavity, to desi0n, electncal conditions and vibratory motion on thmr re-melt droplet size, mett trapping rato, extent of hydrogen com-spective seismic capacity lovels. Singie frequency excitation bustion, quenching of trapped debns, and co-disporsal of water was used for most of the test runs; multifrequency random from reactor cavity. The choice of CONTAIN calculation input motion was also used for some number of test runs The test parameters is discussed and results are presented for both a data have been evaluated and the results are presented in this seven-cell and a single cell nodalization of the Zion containment

'OPO'l-building NUREG/CR-4911: INCENTIVE REGULATION OF NUCLEAR NUREGICR 5285: CLOSCOUT OF IE BULLETIN 7913: CRACK-POWER PLANTS BY STATE REGULATORS MARTIN.R L; ING IN FEEDWATER SYSTEM PIPING. FOLEY,W.J.;

BAKER,K; OLSON.J. Battelle Human Affairs Research Centers DEAN.R S, HENNICK,A, PARAMETER. Inc March 1991.51pp.

February 1991. 95pp,9103040385 PNL-7596. 56869 001.

9103260100 PARAMETER IE176. 57150148 The Nuclear Regulatory Commission (NRC) monitors incen-This report documents closecut of IE Bulietin 79-13 regarding tive programs establishod by state regulators in order to obtain craclis in the feodwater system piping of certsin PWRs. Close-cunent information and to consider the potential safety effects out is based on implementation and venbcation of six required of the incentive programs as applied to nuclear units. The cur.

actions by hconsees and three required actions by designated rent report is an update of NUREG/CR 5509, " Incentive Regu, appbcants for operating bconses (DAOLs) Evaluations of licens-lation of Nuclear Power Plants ty State Pubhc Utility Commis, ee respunses. NRC/ Regional inspection reports, and NRC Blons," pubhshed in December 1989. The information in this memoranda in accordance with specific cntena indicates that report was obtained from interviews conducted with each state the bulletin is closed for all of the 54 PWRs required to re-regulator and each utility with a minimum entitlement of 10%

spond, including 13 DAOLs, it is concluded that (1) sctions re-The agreements, orders, and settlements from which each in quired by the bu,ilotin have been taken by the affected facihties contive program was implemented were reviewed as required.

and (2) the concerns expressed in the bulletin were validated in The interview and supporting documentation form the basis for that cracks were found and corrected at 18 of the 54 lacihties.

the individual state reports desenbing the structure and financial Background information is provided in the introduction ano Ap-impact of each incentive program The programs currently in pendix A, effect represent the adoption of an existing nuclear periorm.

ance incentrvo program proposal and one new program. In add'~

NUREG/CR 5288: CLOSEOUT OF IE BULLETIN 80-06 ENGi-tion, since 1989 a number of nuclear units have been included NEERED SAFETY FEATURE (ESF) RESET CONTROLS.

in one existing progrr.m; while one program was discontinued FOLEY,W.J.; DEAN R S ; KLOEHN.B A.; et al. PARAMETER, and another one concluded inc. February 1991. 33pp. 9102280242. PARAf.1ETER IE164.

NUREG/CR 5139: DOSE REDUCTION TECHNIOUES FOR HIGH-56830 246.

DOSE WORKER GROUPS IN NUCLEAR POWER PLANTS Documentation is provided in this report for the closcout of IE KHAN,T.A.; BAUM.J.W.; DtONNE B.J, Brookhaven National Lab.

Bulletin 80-06 regarding the change of safety-related equipment oratory. March 1991 82pp. 9103260083. BNL.NUREG 52278.

from the emergency or safety mode upon reset of the ESF signal Closecut is based on the implementation and venfication 57152.011.

This report summanzes the main findings of a study of the of four required actions Evaluation of utihty responses and extent of radiation dose received by special work groups in the NRC/ Region inspection reports, in accordance with two entena, nucinar power industry Work groups which chronically get large indicates that the bulletin is closed for 6f (95%) of the 64 opor-M

8 Main Citations and Abstracts atmg nuclear power facihtees to which it was issued fof action tiaHy absent Waste classhcation assessments have shown that Follow-up items are proposed for Se three faehties with open ait decommuoning matenais (except reactor pressure vessel status, Browns Ferry 1,3, and MMstone 1. F acmt es which were interna's) could be disposed of as Class A waste Measure.

Shut down indefinitely or permanently at the time of issuance of ments and asbessments of spent fuel assembty hardware have this report aro not included in this review Background inbrma-shewn that (63 Ni, (59)Nh and (94)Nb sometimes greatly tion 4 presented in the Introduction and Appenda A The con-eced the IDF R61 Class C hmit for some components, and clusion is made that the bulletin concoms have been resolved thus would require disposal in a high level waste repository pend:ng closecut of Browns f erry 1,3, and Mdatone 1 These measurements a<e providing the basis for an assessment NUREG/CR-5309; CLOSEOUT OF IE BUL LETIN 83 APPAR-of the d:sposal opt.ons for these types of highly radioactrve ma-ENTLY FRAUDULENT PRODUC'TS SOLD BY RAY ter,als Compansons of predicted (caiculated) activation product MILLER INC FOLEY,W.J ; DEAN.R S, HENNiCK.A. PAR AME-concentrations w'th the em.>ncai data are pronding an assess-TER Inc March 1991 43pp 9103260089 PAR AMETER IE200 ment of the accuracy of calculatona! methods 57152 093 Documentation is provided in this report for the closecut of IE NUREG/CR 5377: REVIEW OF THE CHRONIC EXPOSURE Bohet2n 83-07 regarding apparently fraudulent products sold by PAT HW AY MODELS IN MACCS AND SEVERAL OTHER Ray Mdier. Inc, to nuclear power and fuel facihties The bullet n WELLANOWN PROBABILISTIC RISK.

ASSESSMENT and two suppiements were issued to all holders of nuclear MODELS TVETEN U Institutt for Energiteknikk. June 1990 power reactor or fuel facihty operatog hcenses or construction 113pp 9101300222 565')4 008 permits Four actions were required of ali affected facilities to The purpose of this repon :s to document the results of the provide assurance that fraudulent items are not used in safety-work pwformed by the author in connect:on with ihe following related apphcat:ons. unless quahbed by tests Review of utWty task. periormed fe O S. Nuclear Regulatory Commission, Office responses and NRC/ Region inspection reports shows that the of Nuclear Regulatory Research. Division of Systems Research bullettn is closed for all of the 118 power fac* ties and for the two fuel facihties to which it was issued for action F acihties MACCS Chronic Exposure Pathway Models - Review the chron-which were shut down or had construction halted indefinitely or ic exposure pathway models implemented in tne MELCOR Acci-permanent'y at the time of issuance of this report are not in.

dent Consequence Code System (MACCS) and compare those ciudod it is concluded that all buSet;n concerns have been rtw models to the chronic exposure pathway models implemented solved Background informat.on is supphed in tne introduct:on in similar codes developed in countnes that are rnembers of and Appendix A OECD MACCS has been compared to the fol lowing internation-aW we n wn he codes AR ANO (Finland). CRAC/CRAC2 NUREG/CR 5312; A THERMODYNAMIC MODEL OF FUEL DIS-(USA). NECT AR (United Kingdom), NUCRAC (USA), UFOMOD RUPTION IN ST-1. GRiMLEY,A.J. Sandia Nationa: Laboiatones February 1991. 22pp 9103120079 SAND 88-3324 56942 244 (Federa! Repubhc of Germany) A direct companson has in A thermodynamic modet that qualitatively accounts for the ob.

many respects proved to be difficult to perform, because of the served fuel disiuption in the ST-1 test is presented The model many basic d.fterences between tne approaches chosen But is based on Winslow's equation for the oxygen p, essure over the report conta:ns cornprehensive destnpt.ons of the vanous hypostoichiometr,c fuel and the reducing nature of the test at.

approaches and defuulf vaiues of most of tne important param-mosphere. The stoichiometry of the fuel is ca;culated as a func.

eters it also conta:ns numerous remarks / comments at points tion of temperature. This calculation predicts part'al hauef action where the approach chosen (by MACCS of any of the other of the irradiated fuel in the test.

codes) may have weaknesses or faults, or where the desenp-t ons4nanuas am incomplete, difficult to understand, or not NUREG/CR 5331; MELCOR AN ALYSES FOR ACCIDENT PRO-GRESSION ISSUES.

DINGMAN.S E.;

SHAFFER.C J.

consismnt we informauon given in other documentation-PAYNE,A C ; et al Sandia National Laboratones January i991' NUREG/CR 5432 V01: RECOMMENDATIONS TO THE NRC 185pp. 9102060162. SAND 89-0072 56592 053 FOR SOIL COVER SYSTEMS OVER URANIUM MILL TAIL-Results of calculations performed with MELCOR and HECTR INGS AND LOW LEVEL RADIOACTIVE W ASTES Identification in support of the NUREG 1150 study are presented in this report 7he analyses examined a wtdo range of issues The And Ranking Of Sods For Disposa! Facility Covers analyses included integral calculations covenng an entire acci.

BENNETT,R D. Army. Dept. of. Army Engineer Waterways E4 dent sequence. as well as calculations that addressed specific penment Station.

February 1991.

57pp 9103200019.

iMues that could aHect several accident sequences The results 57066 174 of the analyses for Grana Gulf. Peach Dottom. LaSalle, and Se-The U S. Army Engineer Waterways Expenment Station quoyah are descnbed and "ie major conclusions are summa.

(WES) provides recommendations to the U.S Nuclear Regula-nzed tory Commission (NRC) for the seiection, placement, compac-tion. test;ng and acceptance of sods proposed to be placed in NUREG/CR-5343; RADIONUCLIDE CHARACTER 12ATION OF REACTOR DECOMM:SSIONING WASTE AND SPENT FUEL cover systems over uranium mill imhngs and low-level radioac-tive wastes The recommendations from WES are contained in ASSEMBLY HARDWARE Progress Report ROBERTSON.D Ea THOMAS.C W.; WYNHOFF,N C.; et al Battelie Memonal instg three volumes of NUREG/CR-5432 Volume 1 identifies the var-tute. Pacific Nortnwest Laboratcry. January 1991. 105pp tous sod *ypes and engineenng properties that are needed to 9102050011. PNL 6806 56575 314.

fulfdl important sod cover funct#ons The identified sods are then This study is providing the NRC and hcensees wth a more ranked according to their capabihty to perform the low.perme.

comprehensive and defensible data base and regulatory as.

abmty and filtnr and drainage functions Volume 2 provides rec-sessment of the rad 60iogical factors associated with reactor de-ommendattons for conducting pertinent laboratory and field commissioning and disposa! of wastes generated cunng these tests to ensure acceptable soi! cover periormance Vok>me 3 activities T is objectives of this study are being accomphshed covers recommendations from WES on proper field construction dunng a two-phase samphng. measurement, and assessment methods including guidance on quahty contro! testing and in-program invoNing the actual decomrmssioning of Shippmgport spections Recommendabons are gfven for seahng penetrations Steon and the detaded t.nalysis of neutron-activated matenals (e g. observation welts) that are required to penetrate covers from commercial reactors Radtological characten2ation studies for environmental monitonng of disposal facihty performance at Shipp<ngport have snown that neutron activat4cn products, dominated by (60)Co, make up the restoual raionuchde inven-NUREG/CR-5432 V02: RECOMMENDATIONS TO THE NRC tory Fis90n products and transuranic radioruchdes are essen.

1

i Main Citations and Abstracts 9

FOR SOIL COVER SYSTEMS OVER URANIUM MILL TAIL.

NUREGICR-5518, OUALITY ASSURANCE PROCEDURES F OR INGS AND LOW-LEVEL RADIOACTIVE WASTES. Laboratory THE CONTAIN SEVERE REACTOR ACCIDENT COMPUTER And Field Tests For Sod Covers DENNETT,R D ; HORZ,R C.

CODE. RUSSEL L.N A ; WASHINGTON,K E, BERGERON K D.;

Army. Dept of, Army Eng4neer Waterway 3 Expenment Station et at Sandia National Laboratoe,es January 1991. 147pp February 1991,76pp 9103200023 57065 346 9102050015. SAND 90-0011, 56576-059 See NUREG/CH 5432,V01 abstract The CONT AIN quality assurance program follows a stnct set of procedures designed to ensure the intognty of the code, to NUREG/CR 5432 V03: RECOMMENDATIONS 10 THE NRC ovoid errors in the code, and to prolong the life of the code FOR SOll COVER SYSTEMS OVER URANtUM MILL TAIL

• The codo itself is maintained under a code-configurat on control INGS AND LOW-LEVEL RADIOACTfvE WASTES Construction system that provdes an histoncal record of changes. All Methods And Gudance For Seeling Ponotrations in Soil Covers changes are incorporated using an updato processor that allows BENNETT.R D; KIMDRELL A F, Army, Dept. of, Army Engineer separate dentihcation of oprovements made to each succes-Waterways Expenment Station. February

1991, B1pp sive codo version Code modihcations and improvements are 9103200021 570t36 067.

formally reviewed and checked An exhaustive, multilevel test See NUREG/Cf. 5432,V' *bstract program va! dates the theory and implementation of all code changes through assessment calculations that compare the NUREG/CR 5481: DATA

SUMMARY

REP.RT FOR FISSION codo ptedicted results to standard hanabooks or vfeaktod test PRODUCT HELEASE TEST VI 4.

OSBORNE M F.;

cases. A document trail and archive establish the problems LORENZ,R A.; COLLINS.J L; et al OA Ridge National Laucra soNed by the software, the venfication and vahdation of the tory. January 1991. 72pp 9101300072 ORNL /T M-11400-software, software changes and autmquent revonhcation and 56535.305-revalidation. and the tracking of software problems and actions Test VI-4, the fourth in a senes of fygh-temperature fission taken to resolve those problems This document describes in product release tests in the vertical test apparatus, was con-detail the CONT AIN quality assu'ance procedures ducted in a flowing hydrogen helium atmosphere The test spec-imen was a 15.2 cm4ong section of a fuel rod from the BR3 ro-NUREG/CR 5525: HYDROGEN-AIR-DILUENT DETONATION actor in Belgium, which had been irradiated to a bumup of 47 STUDY FOR NUCLEAR REACTOR CS i}( ANALYSES, mwd /kg Using an induction furnace, et was heated under simu-ST AMPS O W., DENEDiCK,W B ; TIESZill %

t National lated LWR accdont conditions to a test temperature of 2400 K Laboratones. January 1991.07pp 9101r W ;A: '89 2398 for 20 minutos RadioactMiy measurements showed that the 56534282.

fuel collapsed after the Zircaloy cladding melted dunng heatup The detonability of hydrogen-air diluent mixtures es investe The total release of fission products from the fuel was 85% for gated expenmentally in the 0 43 m diamutor, 13 1 m long Kr 85, less than 1% for Ru-103,3 9% for St>125,96% for both Heated Detonation Tubo (HDT) for the effects of vanations in Cs-134 and Cs 137, and 13% for Eu-154 Most of the Eu was hydrogon and datuent concentration, initial pressure, and initial retained in the furnace, but most of the nther elements were re-temperature The data were correlated using a ZND chemical leased to the collection system. Small fractions of other fission kinetics model The detonation limits in the HDT were obtained products (Sr, Te, and Ba), as well as fuel (U and Pu) were re-expenmentalty for loan and nch hydrogen-aer mixtures and stoi-leased also The total mass release from the 100 g fuel specb chiometnc hydrogen-air steam mixtures. The addition of a dilu-men was 0.40 g. with 40% of this as vapor and 60% as aero-cnt. doch as steam or carbon dioxide, increases the dotonation sol ceil width for all mixtures. In general, an increase in the initial pressure or temperature produces a decrease in the cell width NUREG/CR 3495: CONCEPTUALIZATION OF A HYPOTHETICAL in the HDT, tne detonable range of hydrogen in a hydrogen-air HIGH-LEVEL NUCLEAR WASTE REPOSITORY EITE IN mixture initially at 1 atm pressure is tietween 116% and 74.9%

UNSATURATED,F RACTURED TUFF PARSONS,A.M.;

for mixtures at 20 degrees C, and 9 4% and /0 0% for mixtures OLAGUE.N Ea GALLEGOS,D P, Sandia National Laboratones at 100 degrees C, The detonation limit is between 38 8% and January 1991.177pp. 9102110177, SAND 89-2965 56651:350 40 5% steam for a stoichiometnc hydtogen-air-steam mixturn Under the sponsorship of the U.S Nuclear Regulatory Com-inmally at 100 degrees C and I atm The detonation limit ts be-mission (NRC), Sandia National Laboratones (SNL) is develop-tween 29 6% and 319% steam for a stoichiometric hydrogen-ing a performance assessment methodology for the analysia of air steam mixture with a final predetonation rruxture temperature long-term disposal and isolation of high-level nuclear waste and pressure of approximately 100 degrees C and 2 t, atm.

(HLW) in afternative geologic media As part of this exercise, SNL created a conceptualization of ground-water flow and rade NUREG/CR-5529: AN ASSESSMENT OF BWR MARK lli CON-onuchde transport in the far field (ie, outsido the disturbed TAINMENT CHAL LENGES, FAILURE MODES, AND POTEN-zone) of a hypothetical HLW repository site located in unsatu-TIAL IMPROVEMENTS IN PERFORMANCE SCHROEDER,J A.;

rated, fractured tuff formations This study provides a foundation PAFFORD,0 J, KELLY.D L.; et at EG&G Idaho, Inc. (subs of for the development of conceptual, matnematical, and numen.

EG&G, Inc ) January 1991. 307pp. 9102060148 LGG-2594.

cal models to be used in this performance assessment method-56592 262, ology. This conceptuahzation is site specific in terms of geome, rhis report describes nsk+gn'ficant challenges posed to try. the regional ground-water flow system, stratigraphy, and Mark Ill containment systems by sovere accidents as identified structure in that thew are based on information from Yucca for Grand Guit. Design similanties and differences between the Mountaan located on the Nevada Test Sde However, in terms Marit til plants that am important to containment performance of processes in unsaturated and saturated fractured, porous are summan2ed The accident sequences responsible for the media, the model is genenc This report also provides a revmw challenges and the postulated comainment failure modes asso-and evaluation of previously proposed conceptai modois of un-c ated with each challenge are identihed and descnbed im-Gaturated and saturated flow and solute transport This report provements are discussed that have the potential either to pre-provides a quahtative descnption of a hypothetca! HlW repose vent or delay containment f ailure, or to mitigate the offsite con-tory site in fractured tuff However, evaluation of thu current sequences of a fiwon product release. For each of these p; knowledge of flow and transport at Yucca Mountain does not tentialimproyuments a quahtative anatysis is provided A liroited yield a single Conceptual model Instead, multiple conceptual quantitative nsk analysis is provided for selected potent:al im-medels are possible given the existing information provements i

i bg

10 Main Citations and Abstracts NUREQ/CR 5631: MELCOR 18 0' A COMPUTER CODE FOR A study of the effects of aging on the Wet.tinghouse Control i

NUCLEAR REACTOR SEVERE ACCIDENT SOURCE TERM Rod Drrve (CRD) System was performed as part of tre Nuclear AND RISK ASSESSMENT A4.YSES, SUMMERS.R M ;

Plant Aging Research (NPAR) Program. The objectives of the COLE.R Ka DOUCHERON.E A; et al Sandia National Laborato-NPAR Program are to provide a techncal basis for 6denthying res January 1991. 177pp 9101300000 SAND 90 0364 and evaluating the degradaten caused by age in nuclear power

%535.128 plant systems, structures. and components. The information MELCOR is a fully integrated, engineenng level computer from this and other NPAR studies will be used to assess the cede that models the progression of severe accidents in liDht impact of aging on plant safety and to develop ettocuve mitigal-water reactor nuclear power plants. MELCOR is being devel-ing actions. The operating exponence data were evaluated to oped at Sandia National Laboratones for the U S Nuclear Ac9-identity predominant failure modes. causes, and effects For this ulatory Commisson as a second-generation plant risk assess' study, the CRD pystem boundary includes the power and logic ment tuoi and the successor to the Source Term Code Pack-s cabinets associated with the manuel control of rod movement.

age The entire spectrum of severe accident phenomena, in-and the control rod mechanism itself. The aging-related degra-ciuding reactor coolant system and containment thermal-hydrau-dation of the interconnecting cables and connectors and the 16c response, core heatup, degradation and relocation, and fis' rod potation indicating system also were considered. The eval-sort product release and transport, is treated M MELCOR in a vation of the data when coupled with an assessment of the unified framework for both boiling water reactors and pressut-tied water reactors MELCOR has btin especially designed to matenals of construction and the operating environment, leads facilitate sensitivity and urtertainty analyses. Its current uses in-to the conclusion that the Westinghouse CRD system is sublect clude estimator, of severe acodent source terms and their non-to degradation from aging, which could affect its 6nter.ded safety function as a plant ages. The numter of CRD system failures astivities and uncertainties lo a vanety of applications. This report is a summary of MELCOR 18 0, the code version re-which have resulted in a reactor trip (challenge to the safety leased in March 19t49, Condensed information is presented on System) warrants a higher level of regulatory and Industry atten-I*"

its developmental history, structure. modeling features and ca-pabihties. venfication and validation, and quality assurance De' NUREQ/CR 5558: GENERIC ISSUE 87. FLExlBLE WEDGE tailed documentation on these aspects M YELCOR, including GATE VALVE TEST TROGRAM, Phase 11 Results And Analysis.

users' guides, reference manuals, programmers guides, and as-STEELE.R; DEWALLK Ga WATKLNSJC. EG&G ldaho, Inc.

messment and application reports, is available in dratt form and ts distributed to MELCOR users.

(subs. of EG&G. Inc ). January 1991. 83po. P02110169 EGO-26u0. 566b3 222.

NURE0/CR 5536: DCM3D. A DUAL CONTINUUM, THREE DI.

Qualificaton and flow isolation tests were conducted to ana-

AENSIONAL, CROUND-WATER FLOW CODE FOR UNSATU.

fno the ability of selected bothng water reactor process valves RATED FRACTURED, PORCUS MEDIA. UPOEGRAFF.C D, to perform their containment isolaton functons at high energy Gram, Inc. LEE.C E. Applied Physics, Inc. GALLEGOS.D P.

pipe break conditions and other more normal flow conditions.

Sandia National Laboratones. February

1991, 151pp.

Numorous parameters were measured to assess valve and 9103120075 SAND 90-7n15. 56948.001.

inotor operator performance at va ious valve loaJngs and to This report constitutes the user's manual for DCM3D. DCM3D assess industry practices for predicting valve and motor opera-is a computer code for solving three. dimensional, ground water tor requirements. The valves tested were representative of j

flow problems in variably saturated, fractured porous media The those used in rehetor water cleanup system 2 in telling v.atof re-code is based on a dual <ontinuum mortel with porous media actors and inose used in boiling water reactor high-pressure l

cramposing urie continuum and fractures composing the other, coolant injocton (HPCI) steam lines. These tests will provide The cont:nua are connected by a transfer term that depends on further information for the U S. Nuclear Regulatory Commist, ion the unsaturated permeability of the porous medium. An integrat-Genene issue-87, " Failure of the HPCI Steam Line Without lao-ed finite-difference scheme is used to discretite the governing lation," and Genenc Letter 89-10 " Safety Related Moto' Oper-equatons in space. The time deperdent term is allowed to ated Valve Testing and SurveillaM" numain continuous. The resulting set of ordinary differential equatons (ODE's) is solved with a goneral ODE solver.

NUREG/CR 5577: EXTENSION AND EXTRAPOLATION OF J R LSODES. The code is capable of handling transient, spatially CURVES AND THEIR APPLICATION TO THE LOW UPPER dependent source terms and boundary conditions. The bounda-SHELF TOUGHNESS ISSUE. JOYCE.J.A. U S. Naval Academy, ry conditinns can be either presenbod head of presenbed flux.

Annapolis, MD. HACKETTEM David W. Taylor Naval Re-search & Development Center. March 1991. 10?pp.

NUREQ/CR 5539: A SELF. TEACHING CURRICULUM FOR THE gjg4pg.)0u. 57222.193 NRC/SNL LOW LEVEL WASTE PERFORMANCE ASSESS

• This document d9velops methods of measunng expenments' MENT METHODOLOGY.

CHU.M.S Y; KOZAK,M W.;

Iv the limits of vaW fracture mecharucs data that can be ob-CAMPBELLJE; et al Sandia National Laboratones January tained from small acture mechanics specimens The proposed 1991,195pp, 9102190208. SAND 90 0585 56754:178' technique generally shows that present ASTM limits are overly j

A performance assessment methodology has been deveicoed conservative and the new technique would allow almost a for Use by the U S. Nuclear Regulatory Commission in evaluat-three-fold increase in the amount of crack estension allowed in ing license apphcations for lowdsvel waste dispoal facilities' This report provides detailed guidance on input and output pro-the testing of a surveillance spe irr.an. Analytic relationships are then developed to allow use of the new expenmentally meno cedures for the computer codes fecommended for use 6n the methodology. Seven sample problems are provided for varcus aspects cf a performance assessment analysis of a simple hy-ysis applications to correlate best with the omega cnteren which defines limits on both the maximum J level and the mass-pothetical conceptual model When combined, these sample problems demonstrate how the met'odology is used to produce mum crack extenson aHowaW for a particular specimen site a dose history for the site under normal cor4tions, and to dem.

and matenal toughness combination. The final section looks at onstrate an analysis of an intruder scenarc the problem of extrapolaton of J R curve data when needed for a structure fracture analysis Several forms of extrapolaton rela-NUREG/CR-5555: AGING ASSESSMENT OF THE WESTING-tonships are compared from the point of view of accurate and HOUSE PWR CONTROL ROD DRIVE SYSTEM GUNTHER W.;

conservative extrapolation. particularly from !ne standpoint of St.A.UVAN K. Brookhaven National Laboratory. March 1991, teanng ins'stbility ana!ysis of a growing, ductile crack on the ma-194pp 9104080294. BNL-NUREG 52232. 57294 248 tenat upper theit.

..- - -. - -. _ -.-.,. - -. _.,,_ -. _.. - -.-.._ w. - -

,, - -._ a, -

Main Citations and Abstracts 11 NUREG/CR4581: Urv5ATURATED FLOW AND 1RANSPORT NUREQ/CR 5639: UNCE RT AINTY EVALUATION METHODS THROUGH iHACTURED ROCK RELATED TO HIGH LEVEL FOR WASTE PACKAGE PERrORMANCE ASSESSMENT.

WASTE REPOSITORIES Final Rt.por1. Phase ill. EVANS.D D ;

WU.Y T. Center for Nuclear Waste Regulatory Analyses RASMUSSEN,T.C. Anrona, Univ. of, Tucson, AZ. January 1991.

JOURNEL.A G Stanford Univ., Stanford, CA ABRAMSON.LR.;

79pp 9102050020. %576 200 et al Probabilistic Risk Analysis Branch. January 1991.100pp Research results are summarited for a U.S Nuctoar Reguia-9102260257. 60837:132.

tory Commission contract witt' the Unversity of Artiona focusing This report 6dentifies and investigates metnodologies to deal on field and laboratory trethods for charactertring un'Leturated with uncertainties in assespng high. level nuclear waste package l

fluid flow and solute transp9rt related to high-level radioactive perio'mance Four uncertainty evaluation methods (probability-waste repositones Charactertration activities are presented for delnbution approach, bounding approach, expert judgment, and the Apache Leap Tuff tield arte. The field site is located in un.

sonsttsvity analysis) are suggested as the elements of a method.

saturated, fractured turf in s,eritral Antona Hydraulic, pneumatsc, ology that, without either diminishing or enhancing the input un-and thermal charactonstics of tho tuff are summanted, along Certainties, can evaluate performance uncertainty. Such a meth-with methodologies employed to monw and sample hydrologic odology can also help 6dentdy critical Inputs as a guido to reduc.

and geochem9al processes at the field site. Thermohydrologe Ing uncertainty so as to provide reasonable assurance that the expenments are reperted which provide laboratory and field nsk objectives are met. This report examines the current quali.

data related to the effects of non isothermal conditions and flow tatrve waste containment regulation and shows how, in conjunc-and transport in unsaturated, fractured rock.

tion with the identified uncertainty evaluation methodology, a tramework for a quantitative probability. based rule can be devel, NUREG/CR-5618: USER'S MANUAL FOR THE NEFTRAN ll op(d, wher:h takes account of the uncertainties. Current NRC COMPUTER CODE.

OLAGUE,N E ;

LONGSINE,0.E 4 regulation requires that the weste packages provide substan.

CAMPBELL,AE.; et al. Sandia National Laboratones Februa'Y tially complete containment" (SCC) dunng the containment 1991. 259pp. 9103050503. SAND 90 2000. 56076.095.

penod. The term SCC" is amtnguous and subject to interpreta.

This document describes the NEFTRAN 11 (Network flow and tion. This report, together with an accompanying report which 1RANeport in Time Deperdent Velocity Fields) computer code descrit es the technical considerations that must be addressed and is entended to provide the reader with sufficient information to satinfy high leval waste coritainment requirements, provides a to use the code. NEFTRAN li was developed as part of a per-basis for a third report to develop recommendahons for regula.

formance assessment methodology for storage of high.tevel nu-tory uncertainty reduction in the " containment" *;,queroment of clear waste in unsaturated, welded tuff, NEFTRAN 11 is a suc-

1. CFR Part 60.

cossor to the NEFTRAN and NWFT/DVM compi. tar codes and contains several new capabilities. T hese capabitaties include: (1)

NUREG/CR 6664: CONTAINMENT VENTING ANnLYSIS iOR the ability to input pore velocities directly to the transport model THL SHOREHAM NUCLEAR POWER STATION.

and oypass the network fluid flow model,(2) the ability to trans-GALYEAN,W.J; VELLY D L. EG&G Idaho, Inc. (suba, of EG&G.

port radionuclides in time dependent velocity fields, (3) the abils-inc.). March 1991. 208pp R104000287. EGG-2632. 67321.!72.

tV to account for the et'ect of time dependent saturation An evaluation of the Shoreham Mark li containment was per.

changes on the retardation factor, and (4) the ability to account formed to identd the effects of containment venting on co's for time dependent flow rates through the source regime, in ad-rnett t'equency, > oniainment failure mode, and offsite conse-dition to these changos, the input to NEFTRAN 11 has been quences. The anatysis was based en the Long Ibtend Lighting modified to be more convenient for the user This document is Company's updated 1906 probabilities nsk assesenent of the divided into four main sections consisting of (1) a desenption of Shnteham plant with the preponnd Supplemental Containment all the models contained in the code (2) a description of the System (SCS). The SCS is a filtered Containment vent system program and subprograms in the code, (3) a data input guide, based on the Swedish Filtra system installed at the Barseback and (4) venfication and sample problems. Although NEFTRAN ll Nuclear Power Station in southern Sweden. The following three is the fourth generation code, this document is a complete de-r int containment venting strategies were examined for their acnption of the code and reference to past user's manuals

.is on plant risk: (1) venting using the proposed Filtra should not be necessary, system, (2) venting using the existing equipment at Shorche'n, and (3) no venting in add $on, the consequences of contain-NUREG/CR 5619: THE IMPACT OF THERMAL AGING ON THE ment venting were examinert in conjunction with two sets of as-FLAMMADILITY OF ELECTRIC CABLES NOWLEN S P. Sandia sumptions about the effects of a harsh reactor building environ-Natonal Laboratones. March 1991. 35pp. 9103200039.

ment produced by containment f ailure or venting through the SAND 90 2121. 57065.309-existing containment and reactor building heating, ventilating, An investigation of the impact of thermal aging on the flarn' and eir conditioning systems, on the equipment located there, mability of two common types of nuclear grade electncal catus Spncifically, the ana!yses stud;ed the consequences when a has been performed. Four large-scale flammability tests we.e harsh reactor building environment is assumed to have either performed with each of the two cable tyoes tested in hath an no adverse effect on equipment or to f ail all equipment.

unaged (ie., new off the reel) and a thermally aged (artificially aged) condition tn all cases, the fire was observed to consume NUREG/C45656: EXTRAN. A COMPUTER CODE FOR ESTt-virtualty all of the combustible cable Acket and insulation mate-MATING CONCENTRATIONS OF TOXIC SUBSTANCES AT nal piesent. However, for both cable types tested, the thermal CONTROL ROOM AIR INTAKES RAMSDELL,1V Battelle Me-a0ing process caused a decrease in the cable flammability as monal Institute, Pacific Northwest Laboratory. March 1991.

demonstrated by decreases in the rate of fire growth, peak fire 164pp 9103260116. PNL 7510. 57154-059 intensity, total heat released, and near fire temperatur$t ihis This repo#1 Vesents the NRC staff with a tool for assessing result is consistent with past cable aging studies because if has the potential effects of accidental releases of radioactive maten-been observed that the thermal aging process will dnve off cer-als and toxic substances on hebitabikty of nuclear facility control tain of the more volatile constituents of a polymeric matenal.

rooms. The tool is a computer code that estimates concentra.

Presumably, when these aged materials are sutyected to a fire, tions at nuclear facihty control room air intakes given informa-the evolution of volatile combustible gases is reduced as com-tion about the release and the environmental conditions. The pared to the unaged materials, and hence, flammability is re-name of the computer code is EXTRAN EXTRAN combines duced. The results of these tests indicate that, at least for the procedures for estimating the amount of airbome matonal, a two cable types tested, the evaluation of cable flammability Gaussian puff dispersion model, and the most recent sigonthms using unaged cable samples will remain a conservative indicator for estimating diffusion coefficients in building wekes It is a of cable flammabikty in a thermally aged Cond! tion modular cornputer code, wntten in FORTRAN-77, that runs on

l 12 Maln Citations and Abstiacts personal computers 11 uses a ma'h ( oprot.euar. if p'esent, but tional Laboratanes deveioped the (ode for the J S Nu: te ar dxs not repte one Code output roay t+ duet ted to a ponter Repatary Commitsmo on a VAxivMS mins omputes T his or du fues report documents the Idaho Natonai t r9neenng Laboratory wnaw n of M ACC51 r> f or compdaten and vierution on on NURE G/CR4658; I PF P.2 A CODE F OR I DL L OMNG Ain-OORNE F ISSION PRODUCT b W GE NE RIC NUCL E AR PL ANT

, taased IliM o' lbM compal@e pert otia! computer (PC)

FLOW PATHS OWC 2ARSkiPC.

DURu W,

" "mng wru n or the code is avaaatae through the R AMSDL LLJ V ; et ni Battehe Memonal Inst >tste. Pott North.

Nawnal E ng SMware Centet Argonne National Laboratoy west Laboutory. Mwh 1991 ft2pp 910/020004 PNL 7513

• h #'C8" ^ # ""' A'J""""'E N O 07221 N NUREQ/CR4672 V01: CHAR ACTER$ TICS OF LOW-LEVEL R A.

ThS report descrities the techngal t;ases and use of the DIOACTIVE W ASTE Decontamination Waste Annual Report computer code f PF P-2 (ritwo Produ t ilow Pathol f M P-2 i of I $; al

't ear 1990 MCISAAC.C V, AkERSD W EG&G was developed to estimve the contentrations and fmw rates of dh N bubs of EG&G. Inc l F obtuary 1991 33pp airbome fission prottuctti atong a genenc fivw path tohawmg a 93933493 g m apge, ggg pgg tranwent or pu't source of f$sion products at the beginning o' The M,mctwo of Proint iIN A0309. "Charactenstics of to*.

the flow path This report serves as a ust r s gmde for f PF P-2 Level Radioattive Watte Decontamination Waste f orms/

A complete code description, code operating instructions code funded by the U S Nuclear Regulatory Commission. 4 to pro.

l$teng1 and an Hample of the uw of f PF P-2 $Jpport the uw vde We4ne dMa on t% MMety and leachatulity of solidaed O'Ih" cod" tiecoritamination waste $ that are generated at operating com NURE Q/CR4%5: A SYSTEMATIC APPF10ACH TO REP (:TillvE mmrial nucinar power stations following the chemKal decon-F AILURE S ODLAND.D J Sonalysts, Inc February 1991, 33pp tamination of pomary coolant systems Th4 work m being per.

9103110198 SI 14940000 1 % 942 209 formed to asuu tM adequacy of tests identified in " Technical This report presents a model of a systematrc approach to ad Posmon on Waste l'o msJ prepared by the NRC low level d'ess and correct repetSvc failuret in tr s contest, repettve Waste Management Branch. to meet the reqwrements of v

twl-Jtes are the recurreg inability of a systmTt BAsystem, struc-10CFR61 As part of this prorct, sariples of decontamination ture or component to pedurm its intended function Tho report waste stream resins and coment waste forms were otilained presents a systematic method for identifpng repetMve tailures.

from commercal nuclear power stations Dunng Fmtal Year selecting the f ailures to be investigated _ determinirig root caum 1990, samples from the Fit Patnch Drunswick and Peach se!etting corrective actions for implementation, and monitoring bottom nuclear statiorm *me eaamined bampleb were tiubp+ct.

subwavent system / component performance Appendr A pro-ed to the leach tests desenbed in "Technicai Poution sn Waste vides an enample of the use of this methodology a. an operal-Iorms" to aswbs the eft (cts of the decontaminat6cn wastes on ing nuclear gnnerating station the stataty and teacnabihty of the waste forms Dominerakted NUREG/CR 5666: PROGRAMMATIC ROOT CAUSE AN AL YSIS water and four di ferent synthctn; leachates with pH rar7ng OF M AINT E N ANCE PERSONNEL PERf ORMANCE PROC-hom 4 2 to 10 4 wee uwd for W WMs W resWs of u ew LEMS INADAA XY2YX Information Cup January 1991 tetts an tabulated and preliminary analyws u e presentet' s

10Lpp 9102110195. 5Rt21b9 NUREG/CR4695: A PROCESS FOR RISK,f 0CUSED MAINTE-This riiport presents a method for diagnoung the proa'am.

NANCE. LOFGRENE V; COOPER.S E. KURTH,h E. et al Ecr matic root causes of pstonnel performance problems "r

once Applications International Corp (formerly Science Apphca maintenance of nuclear power plants t he process u*'

tions. Inc ) March 1991.141pp 91040802/3 57321031.

maDy available maintenance won order dsta to identify repeat TM repor1 presents a process for focuWng maintenante re-maintenance caused by inadequate personnel performance sources on components that enable nuclear plant syvems to The pnmar/ omphams of the analyes is on corrective mainte' portorm their eswntial functions and on components.wse fail nance but the process will detect corrective maintenance ac ure may inmate challenges to safety systems, so as to have the tions caused by errors made during scheduled maintenanco four logic trees are provided to help isolato the caubes of such greMed impact in decreaung nsk The process provides ente-na. bawd on nsk, for dec@ng which components are cntical to problems to program elements The program elements conust nsk and determining what maintonance activities are required to of the technicians and their managers. as well as support ele-ensure rehable operation of thor,e "nsk,cr$ cal" components monts and their managers, such as the people responsble for Two ap roathM are provided for selection of nsk-cntical com-developing procedures end othur dc.cumentation developing onents One approach uses the results of a Probatnhstic Risk and delivenng training programs. etc Decause of the impor-tance of management commitment to improve rnaintenance.

Assessment (PRA), the other is based on the methodology de-emphaos is placed on identifying responstilo managers, as a veloped for this report, which has a basis in PRA although il does not use the results of a PRA study following identacation pnmary or co-cause of problems A sampio appbcation of the of risk cntical components, both approaches use a onglo moth, process to a plant is also presented I r determining what maintenance activ$es are to-NUREG/CR4667: INEL PERSONAL COMPUTER VERSION Or auned to ensure rehable operation of the identAed components.

MACCS 1 s JONES.K R ; DOBBC.C A ; kNUDSON D L EG&G The report also proades demonstrations of apphcation of the Idaho, Inc (subs of EG&G. Inc ) Maren 1911. 37pp two approaches to selection of nsk-cntical components nd 9103260227. EGG 2634 57152 307.

demonstrations of apphcation of the methodology for determen.

The MELC9R Accident Consequence Code System. Veruon ing what maintenance actraties are required to an active Stand-15 (MACCS 15), calculates potential conseoances resulting by safety system. a normany operabng system, and passive from atmosphonc releases of rtdioactrve matmals Sandia Na-components

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

ElCONDARY fit POHf NUMbtR fit POHf NUMBtR f,f CONDARY *ttPOHf NUMBE R Rt PORT NUMHF R HNl / T M 114?O NUhl G/Wi 54151 DHANC 7(0/ WD/01)

Nunt G/(.H.4911

{')AhaW II N li 104 N1.if 4( (W( H tJfift flNL.NUhlG 5?181 NUtil G '( h LPR2 flN1, NUlliG t2M12 NUHf G/(J4 8.5%

nNoNUntG m s Nuni G,Ciu d44 r,,,,,,.

NUhi c. Cn m3 hNL NUNI G fE???

NUhl G/( R.466 7 py( 7 s.1 Q NUH( G M H %'A (int NUhl G SP278 NUhEGiCH $139 5 Nt.76.13 NUhl G/CJi SfAft

(#E01 NUhl G 1775 VO6 PNL.75ft2 NUh[ G/Ch 4670 PNL 759b Nllitt G/CH 4911 (O NI W AD13 NVHf G1C P-Of 10 v01 PM IhW NUhIG i H4I67 CONF.iK0fl13 NUht G!( P Of 10 yO/

f

',h {'f.

i GD P%4 NUtil G/CH L'i?9 nun, G,Cn su, i GG a.m Nunt u,Cn sm

,,,,,,3,,,

i GG T632 NUf t! O/CH $654 hAMID9 Ou tt 94Uht G /( 14 f.:13 1 i GG Pfi34 NUH[ G/Cf4 Of47 3AN[$9 219H NUh( G/(.4 6525 I GG 2035 NUht G/( h t472 VQ1 hANi> hts P4f 6 NUbi G/(.h 8.495 U.NirJ0-0011 NUfil G/C H f61B 11 !! 71# 1 3 NUhl G/GR 8Jf45 4

All II il 60 00 NUh!(i!CH L/he b^M NO D'H't NL Ihl Ci/Ch "p 6AN M M" Nuht G/(h h,n,0, d,,'

M 18tifG 07 NUh(b/CH f,309 f,9 NGilR 4327 NUHI G'OR 4235 NUh,G,ef.e is N sun dum NuniG1H4a4 sA OHNL /N%IC 200 NUhl G/0R JtXO VWN12 hANh(D 701f.

NUht G/(H MM OHNt /N5tG ?00 NUht GeCH 2000 V10 N1 bl-1494:000 1 NU6 tl G /CH 'u4 13

Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agroornent reports in alphabetical order. Each namo 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.

ABRAMSON.LA C AMPDE LL.J E.

Nuhi G/CH %39 UNCE RT AIN TY E V AL U A DON METHODS f00 NUnt G/CR M3W A !It.F.TE ACHN1 CURRICULUM FOR THE NHCl W ASTE PACF AGE P!HFORMANCE ASSESSM[NT SNL LOW Lt VEL WASTL P[HIORMANCE A%t $%MLNi ME THOD OLOGY AM E RS.D.W.

NUnEG/CR f4tB USEH S M ANUAL IOR THE N!F1HAN 11 COMPU1+

NUHf G/CR %/2 V01 CHAHACT[RIS11CS OF LO#tWIL hADIDAC-tH CODE TIVE WAS1E De.mtarn#naton Waee Annunt heport FN fisc al Year 19M C AMPBELL,R M NUh!G/CR 4E70 HADIONUCLIDE DisthiUUllONS AND MiGnATION AKOUN,H.

MECHANISMS Al SHALLOW LAND HUHlAL SITL S F6nal Report Of NUHEG/CH 4295 BOND STRE NG1H OF CEMENTITIOUS don [HOLL put n,,,,,th inveshgabons On The D+1ntiouon Mystion. And con PLUGS IN WELDED TUF F.

tament Of Radior xintes At Mavey Flats. Kentudy ALLENSPACHL NUHi G 1214 R07 HISTOhlCAL DAT A SUMMAHY OF THE SYSTEMA 1 NUHEG/CH 533i. MELCOR ANALYSCS F OH ACCID (NT PROGH[S IC ASSESSMENT OF LICENSEE PEHFOHMANCE SiON ISSUf S NURE G/CR R31 ME LCOR 18 0 A COMPUtt n CODE FOn NUCL t AH B AKE R.K.

HE ACTOH SEVf HE ACCIDENT !.OURCE ilHM AND RISA A%L15-NUHEG/CR 4911 INCE NTivE F4E WJt AllON OF NUCLE An POWL R MENT ANA(YSE S PL ANTS BY ST ATE REGULA10RS CARROLLD E.

BANDYOPADHYAY NUHEG/CR %18 OUALITY ASSURANCE PROCEDUHES FOR THE NUnLG/CR 4157 HELAY 1E ST PROGRAM Smms l Vibration Tests CONT AIN SLVERE RE AC10H ACCIDE NT COMPUT[ R CODE BARBER.D E.

NURE G/CH 4444 RADIAllON SAF ETY ISSUE R hlLATED TO RADIO CHU.M 6.Y NUREG/CR %39 A SElf.1E ACHING CUHulCUL UM FOR THE NHC/

LADE LED ANilDODi[ S SNL LOW LEVEL W ASTE P[RFORMANCE ASSESSMENT ME1 HOD-BAUM.J W.

OLOGY.

NUREGICR 4444 RADIATION SAFETY ISSUES HELATE D TO RADIO-L AHf LE D ANilDODit S CLIFONJA NUhEG/CM13v DOSE REDUCTION TECHNIOUCS FOR HIGH DOSE NUREG/CR 4235 Sl S ECTION OF SillCEOUS AGGREGATE fOR W0GKER GROUPS IN NUCLE AR POWER PJNTS CO:CRE TE BE NE D'CK.W.B.

CF E NURI G/CR %25 HYDhDG[N AIR-DILLEN1 DE TON ATION STUDY FOH NUCLEAR REACTOR SAFETY ANALYDES-COLE,R K.

NUHEG/CH %31. MELCOR 18 0 A C4 MPUTIR CODE F OR NUCLi AR BENNETT R.D ACER SMM AMN WW U HM M W EN NUR[G/CH t 432 V01. RECOMMENDATIONS TO THE NRC FOR Soll MENT ANALYSFS COVER SYSTE MS OVLH URAN!UM MILL T AILINGS AND LOW-LEVEL RADIOACTIVE W %STES Identificahon And Ranking Of soils COLLINSA NMMENDAllONS TO THE NRC iOR SOIL NUREG/CR-5451. DAT A SUMMAnY REPORT FOR FISSION PRODtlCT N E I

HELEASE 1EST VI-4 COVER SYSTEMS OVEH URANIUM M)LL T AILINGS AND LOW.

LEVEL RADIOACTIVE WASTES Latpatory And Field Testa for Soil COOPER,5.E.

NCR 6432 V03 RECOMMENDATIONS 10 THE NRC FOR SO!L NUWCHM A NESS W RWMW MWAE N

COVER SYSTEMS OVER URANtVM MILL TAILINGS AND LOW' D AE ME N.J.J LEVEL RAD!OAC11VE WASTES Construction Methods And Ouxtance NUniG/CR-4295 DOND $1FIENGTH OF CEVENTITIOUS DOREHOLE For Seahng Penetrabons in Spel Covers PL UGS IN WELDED TUFF.

BERGERON.K.D.

DAllMAN'CR 5529 N J-NURE G/CR-55t B OVALITY ASSURANCE PROCEDURES FOR THE NUREG/

AN ASSESSMENT OF BWR MARK lli CONT AIN.

CONT AIN SEVERE RE ACTOR ACCIDENT COMPUTE H CODE MENT CHALLENGES, F ALLURE MODES. AND POTENTIAL IMPROVE.

ME N1s IN PE RFORM ANCE BOUCHERON.EA NURE G/CF+5531: MELCOR 10 0 A COMPUTER CODE f OR NUCLE AR DE AN.R 6.

RE ACTOR SEVf HE ACCIDENT SOURCE TERM AND RISK ASSESS.

NUHEG/CA $285 CLLSEO'JT OF IE BULLETIN 7913 CLCkiNG IN MENT ANALYSES F E EDWATER S(STEM PiplNG BROWN.C NLREG/CR $2M CLOSEOUT OF IE BULLETIN BO.Ce ENGINEERED NUREG 0430 V10 LICENSED FULL F ACILITY STATUS SAF ETY FE ATURE (ESF) RE SET CONTHOL S NUHEG/CR S309 CLOSLOUT OF IE BULLL TIN B3 07. APPARENTLY REPORT. inventory DiNetance Data July 1D69 June 1930 (Gray Book FRAUDULENT PHODUCTS SOLD BY RAY MILLER,1NC.

11)

BU A K.K.W.

DE W ALL,K.O-NUREG/CR 5658 FPFP P A CODE FOF, F OLLOW'NG AlhDOMNE FIS-NURE G/OR 5%8 GENERIC ISSUE 8/: F LE X10LE WEDGE GATE SlON PRODUCTS IN Gt NE HIC NUCl E AR PLANT FLOW PATHS V ALVE TE ST PROGRAM Phase ll Resatts And Analysis 15

e 16 Personal Author Inden DINGM AN.S I..

Hi NNIC K.A NUht G/CH LM1 Mt tCON AN ALY 5[ 5 F OH /CCIDt NT PROSHI b-NU41 G'CH Ve CLOS! 001 OF tt DUt Lt1:N N t 3 ( RAL

• ING IN

% 0N15 %f5 f(( DA Ati H SyST[ M hP:NG NUht G/C4 M31 Mit COR 10 0 A COMPUTI H COOL I04 NUE L l AH NUHt G CH f.2pi CL OSt OU T OF Il Dutt (liN (W DS ( NG At i H( D 4l ACIOR b[ Vi h[ ACCIDI NT %DUHCl 1E HM AND M A A5bt 55-LU l 1Y f ( AT UHt (t bil H[ ht f CON 1HOL S MI NT ANAL Ybl5 NUHE G'CH f.3N CL 051 QU f Of Il DUltETIN B3 N APPAhlNilY f HAUDULt NT f HDDUCTS 5010 DY HAY MtlLL R INC NUht G th M3ia LOSE ly DUCTm t( CHNout S f 04 HIGH DOSl HL Tit R.D C.

WOHkl H GROUPS IN NUCLI AR POvVI R PLANT S NUhl G'CH SM3 R ADiONUCLIDt CHAH AC11 Hil AllON Of kl AC-104 DLCOMViS50NtNG A A$fI AND $Pl N1 i UI L ASSI MIR Y DOD BE.C.A.

HAHD" AHE Pwns hvoort NUHl GrCH %07 IN(.L f lHT DNAL COMPUil u VL HSON Of MACCL 1b Hi&[$tA L NuHtG/CPOD37. PIOCi t D:NGS Of THE bl VIN AH ON ABBESS WITA Mt NT Of t hAC1UNE Pht 01CTON TECHNJLOGY PIPING AND NUREG 0933 $12 A PHOR:T12AllON Of Gt Nt HIC SAf LTY ISSU( S PHE SSURE VI SSE L$

LVANS.O D.

HOf M AYER.C H.

NUhE G/C3 !&Bl.

UNSA1 UH A T E D FLOW AND T hM.SPOH T NUME G ?R e01 RELAY T E 51 l'h0Gh AM $ones i Vitusion Tets 1HHOllGH FRACTURE D HOM hiLAtt D 10 HIGH t(Vf L W ASTI Hi POSlf OtllES final Hopwt Phase ill HCtZ,R C.

NuHE GrCH t,4n vp2 niCOMMt NDAilONS 10 THE NMC f Oh bOtt U G CP-011ti V01 PROCEIDINGS OF THE 71$1 [OE /NHC NU-A VE S1 a de A f dlet i SI CLE AR air CLE AN;N3 CONIE RINEE Spons 1 8 Held in San gg Dwp Cabtornm Aupal 1316.1WO NUHI G/CP.011t> V07 PROC [L DINGS Of THE 21S1 EOl /NHC NU-igppo g_y, CLLAH AiH CLE AN!NO CONFI HL NCE St SSIONS 9 + 1E Held in han NUhE G 1397 AN ASSE ShMI NT OF Di SIGN CONih0L PRACTICES Og. Cahlmnia. Aupst 13 16.19D0 AND DE SIGN HLCON5flf UTON f ROGH AML IN THE NUCIE AH POWE R INM RY FOLE Y W.J.

NUHLG/CH 5205 ClOSEOU1 OF 40 DULLLTIN 7913 CHAF 4 IN gyggg g, N E e6 CLO E 1 OF IE DUL Lt T IN BO 06 t NGINi t 4L O Mo Em1 n t

Imm malm LAf( TY I E ATURE (t hi') Rf 5F T CONinois NUHf G/CR 5399 CLO5E OUT OF IE DULLI ilN B107. APPAR[ NTLY JONISKf1 FRAUDULENT POODUC1B SOLD tlV HAT MitLE FUNC NUht G/CH M.'9 AN ASStSSMENT OF tWR MAhK lli CONI AIN-ME NT CH ALL L NGE S. F Alt.UHE MODE $ AND POTi NTLAL IMPROVE-g Atttoog,g p, I

NUHF G/CH 5495 CONCl PfuAU?AllON OF A H1POTHE IICAL HiGH.

COMPUTER Vl'RSON OF MACCS LtilL NI'CLE AR W AS T E Hi POSlf DH Y SIT E IN Ib UNSATURA' If RACTUH[D TUI F NUREG/CR 55sti DCM3D A DUAt CONilNUOM THRE L DIME NSION' JOURNf LA G I

NUREG/CH 56% LNCE RT AINTY EV ALU ATION MEltODS FOR R[ '

S ME DI WASTI PACKAGE PEHF OOMANCE ASSl SLMF NT GALVE AN W.J.

NUHE G/CR-5654 CONT AINM[ NT VE NTING AN AL Y$15 F OR THE NUHE G -0410 V10 L IC[ NSED f UEL F ACILl1Y STA1VS SHORE HAM NUCt.1 AR POWL R St ATION' MEPORT inwntory DererKe Data July 1900 June 1990 (G'ay Book Ih s

GILBERT,0 W.

NURE G/CH 3916 PHE SSURil[D MELT (JE CTION INTO W ATER JOYCE.J A POOLS NURE G/CR tS77 E XT E NSON AND E XT H APOL AllON OF JH CURVE S AND THUR APPUCATON TO THE LOW UPPER SHELF GINSilE RO,T, NURE G'CR 6262 ES11MATON OF CONTAINME NT PHESSURF LOAD.

10VGHNE $516 SUE ING DUE TO DIRECT CONT AINMLNT HE ATING F OR THE ZION KE LLY,D.L ptAqy NUREG/CR MN AN ASSE SSMENT OF DWR MARK lll CONT AIN-MENT CHAlt ENGES. F AILUHE MODES. AND POTE NilAL iMPHOVE-GLISSMEYER,J.A.

NURE GICR 4 767 UNC LOSS DEliRMlNA10N FOH AIR SAMPLLH ME NTS IN PEHF ORM ANCL' NUHEG'CH M54 CONT AINMENT VE NTING ANALYSIS FOR THE SYSTEMS SHOREHAM NUCLEAR POWLH ST ATON GRlWLEVAJ.

NUHf G/CR4312. A T !E RMODYNAMIC MODEL OF l'Ut'L DISRUP-

"ILLT'J E-NUHEG'CR 5531 Mf LCOR 18 0 A COMPUTE A GODE 8 00 NUCLE AR TON IN ST t Rf ACTOR LEVERE ACCIDLNT SOURCE TERM AND RISK ASSESS-GRIMSHAW.CA MENT ANALYSES NUREG/CR4282 ESTiMATON OF CONTAINMENT PRESSURE $0AD-ING DUE TO DmECT CONTAINVENT HE ATING FOR THE 2ON K H AN.T.A.

NUR[G'CR4130 DOSE.REDUCTON TE CHNIQUES FOR HIGH DOSE PLANT.

WORnt R OROUPS IN NUCLE AR POWER PLANTS OUNTHER,W.

NUREG/CH45M AGJ:0 ASSESSMENT OF THE WESTINGHOUSE KIMBHILLAE NUREGeCR S432 V03 RECOMMENMTONS TO THE NRC FOR SO L PWR CONTHOL ROD DRIVE SYSitM COVLH SYSTEh5 OVER URANIUM MILL T AIUNGS AND LOW H ACK E TT,E.M.

LEVEL RAOCACTIVE WASis S Consvuction Metmin And Gudante NUREG'CH M77 E XT E NSON AND E nT R APOL AT ON OF AR For Scalmg Penetratons in SM Covers CURVES AND THEIR APPLICAYlON TO THE LOW UPPER SHELF TOUGHNE SS ISSUE klRB Y,LJ.

NU4F G/CR 4670 RADONUCUDE DISTRIBUTCNS AND MORATON HARRIS.C.L ME CHAN!SMS AT SHALLOW LAND BURlAL SITES Final Report Of NUREG/CH 5$18 QUAUEY ASSURANCE PROCEDURES FOR THE PNL Resea@ Investgalsons On The DminNtion. Myston. And Con-CONT AIN SEVEHE REACTOR ACCOENT COMPUTER CODE ta:nment Of Rahnuchdes At Mauer Fiats. kentuc6y 1

Personal Author index 17 N AIO P K-KLOlhN D A NUhl Wut fJbit LtO%f OUT (ni ll DUlii flN to 061 NQNll hl D NUhlb Ch %W uni ( H1 AINI Y I V AL U AIK dd Ml l HOD'l IUh

$Af f l y f I Af Uhl ti 55 ) hl 511 LON1h0Lb W A%f t PAC AA: { ll hl OhMANCl A%l Wi 41 It N AB.L N AK AMUH A.T.

touhl O!( h-4Mt Li L t L169N 06 SilIrl OU5 AGGhlLAil iou ggng 9,th e.4n) DA T A SUMM Ann hl l'Oh1 i 04 I 4".10N PT " hcl LONLhl II hl(lAhl 11STVI4 KNUDSON D L NltHOLB.R T NUHL G;LH SfC INI L Pl!MNm LOUI'Ull h Vi f N N 08 M AM $

ua w hW D VtL1 i A QUN INTO W A 4 h Poot b 9t02 AK.M W NUhl M h !Nik A St ti 1( ACHith CUhhk 44 UM I Oh 1HL Nim /

Nit L60N.H L hNL LOW ll VI L W A%f t Pt hl OhMANCL. ASSL 5%ML N1 MI T HOD Nullt Orch 4p0 4ADIONU(4IDL f usthtt1UTKWS AW MiGhAf tDN MI C6 LAN%MS At bHAL LOW L AND hUltiAl W L 6 f inal Helcri Di OL OG V.

PNL hewet h lnytenkptaps On 1tw (Mtnte.sn Mynlost Ahti Con IL4 li !49% A PflOCf b$ I Oh hihk I COUSl D M AINil N AN( l NOWLt N.$ P.

UAND UIllU,Y U#

t I

Ft3145 VDie G( OPH y blLAL IN w'l LilG AllONS 08 1HI

• U b

WL bil hN OHIO INDIAN A hl GION Annoni hegorRx tolect 1W beptember 19w ODL AND,0.J.

NUhl G!CH 'M A bv$fl.M A10 APPh0ACH TO N fi W I Ak t g te g,

NUht G/Ch fN10 [K;M3D A DUAL-(<DNilNUUM IHhl i DiMt NblON Uhl 5 AL. Gh0VND W Alt 11 iLOW L ODL f OH UN5AIUHAllD. I HAC OLAGUE,NO 1UHf D. POh0VS Mi DI A NUhl mLH t495 004C1 PTUAlllAlt04 (A A H'POihl llCAL HIGH t ilOH,C D.

ti Vi t NULLIAh W As1 t ht PON110llY W

IN NUhl G/Ch %I(i U%f H S MANUAL IUU lhi NIi IHAN 11 C( 5MPUI-UusA1Uin All D.6 H AC1Ultt D TUI F L h 00DI NUht G/Ui %1h U$1 h b MANUAL I G41Hf NII IhAN ll COMPUI-

[h(O DI LOF0ptN.L NUHL G/ChMS A Ph(X1 S% f Oh hl5h I(X.:Uhl D M AINil NAN ( T pyygg g.

NUhlMH M.

M WHJi D WO IM NW WW Mh LONGt INT.D L NUhl G/LH 1416 UM h 5 MANUAL I Oh lHL NIi lilAN ll COMPUI-POOL 5 IhGODL OLbON.J LOht'N2.H A.

NUhl GiCh 4911 int'i N1tVt h[ GUL AllON Of NU'AI Ah POWI h NUht u/LH 64fl1 DAT A bOMM Ah1 HI P(thi ( Oh l t% ION Ph0 DUCT PL AN15 tiy ST All. HL GUL A10h5 fit LL Abt ilSi VI 4 ORNSTLIN.H L MARTIN,H L NUht G typs ym, opt HATING i yP( M ;4Cl ilI DBACK N POh!

Nuhl G/Ch 49l1. INC ( NiiVL hlGULAIK)N Of Nutil AU POWL h bull NOtU GP( RAll D VAL VL PHPbt i Ms (x;mmoniW Powet he,av PLANIS liY ST All hlGULA10h8 m

M AYSIt'LD M L OWORM,M L NUht n/CP4037 Ph0Cf L DINGS Of THt St MiNAO ON AL5l SS Nuht G/ch tein DAT A SUMML4Y fil POh! f 0h ilSSION i,h0 DUG.1 PE NT Of T HACiuhl Phl.DIC110N llGhNOLCMY llPING AND itt if ASE Tl bf VI-4 PHL5SUhE VI 55f L S OWC 2 AHSKI.P C.

WCoulH LS. A.

NUhlG'Ch 5 fan i PIP 2 A (f0I l Oh IOtlOW!NG AlhDOhNl IIS-NUhtG-1w1 CH[ MicAt 10i0011Y OF UHANiUM Ht x At t UOltIDL LOMPAhl D 10 ACUTl t Iii C1S Of H ADIATION IInal heport SiON Ph000 CTS LN Gt Ni h!C NUCL L AH PL ANI f LOW PAih5 MCISAAC.CV P Af tORD.D.J.

NUht G/Ch TOP VO1 CHAHACit htSilCS Of LOW LI Vli hADICAG' NUhl G /Ch M?h AN A%%[ SSME NT Of DWh MAhk HICONf%N llVt W A$1 L Doc ontaminatun W ante Annual heport I of f is: at Y ca' Mt NT CHAT ti Nat 5. F All Uht MODI S, AND POil NiiAl IM' HOVE -

iWO Mt N1S IN Pt hi ohm ANCI MCf1HANLM C.

PAR Nuh[ G /Ch 4tWD HADIONUCIIDE OtSihibullONS AND MIGhAllON MECHANt%MS Al SHALLOW LAND Buf 0Al. SH f 5 final hoport 01 ING DUE 10 Dth[CT CONT AINML N1 HE AilNG f Din THE llON PNL f 4emoarch Inycetentent On The (%tntmten. Myahon. And Crn h^

lainffmnt Ol No.lpmtWS Al M8mDy Ilat$, h phlAky P AHSONS,A M.

Mt ERT,J.

NUh[G/Ch 8,4d$ CONG( PIUAUZAllON Of A hyPQ1HL ICAL thGH NUnfG/CH-3145 V09 GE OPH) SILAL INVI $ TIG A TIONS OF THE W[ST[hN OHIO 4NDIANA h[GtON Annual honort(xtobur 19N LEVfL NUCLtAh W ASif hlPOSITOW SITL IN UNSATUHATL DI HAttuhlO TVf F SeP emt* 1990 t

M(lNHOLD.C B.

P AY NLA.C<

NUhtO'Ch 4444 HADtAf TON SAF E IN ISSUL S hl LAll D YO HADIO NUht G/Ch $TH. Mi tCOh ANAL y5t 5 yOH AC0lDLN1 Ph0GhtS LABL L L D ANilDODilS 5 04 ISSUL 3 MILSTE AD,W.

pHitups,Lg NUGE G 0933 Sit A PhiOhl11/AfiON Of' GE Nt htC LA6 i Ty ISSulS NUM G /Ch 8495 A Ph0CI 55 i Oh hibr i OCUhl D M AINil NANCL MOLINA.T.

PILC i M j

NUht G/CP 0116 PROCll DING 5 Of' 1HE CSNI WDHKSHCP DN P5A APT LICAllONS AND LIMIT AllONS POOLS MURAT A.K K.

NUhE G /Ch %18 OUAllf y ASSUHANGE Ph0CL DUlqE S F Oh THE PITT W AN.J.

CONT AIN 50VL f 4 hl ACTOh ACCIDI NT COMPUTlh CODE NUht G Ofm 512 A PhlOh!112 Af TON Of GC NE htG SAf l1Y 155U1'S

18 Personal Author index POleMi RSHE IM J T ARBE L L,W W.

NUht G/CH 4Pt 9 MOD [ LS OF 1RANSPORY M A i SSI S IN CON NURfG<CH306 PHE 55Ur0Zi D MlL1 i A C10N INT O W All H CHEll PCOL 5 R AMSDE LLJ V.

1HOM AS.C W.

NUht G/CH %% ta1RAN A COMPUT[ A CODE FOR ( ShM AllN3 Nun (G<cq 4( a 44D c Ngclip[ Dig 1pung10NS AND MigqA1;ON CDNCtN1RAflONS Of TOEIC LUD51 AN:t 5 AT CONihDL hDOM M[CH AN!5MS AT $HAl LOW L AND llVRLAL 5'IE S Iinal hwi Of AIR !NT A> l S Pg homqh Inynbytions On the Distotyton Mystion, And Con tdVHE G/CH %58 F PrP 2 A UODE F04 I DLLOMNG AlklOHNt f Ib' u nment Of heJKenvades At Maucy Flets. kentxb SiON PRODUCT 5 iN GENE 4tC NUCLf AR PL ANT FLOW PATH %

NUHE G rCH.0 34 3 RADIONUCllDE CHARACif H12ATON Of nt AC.

10h D(COMM'SSON(NG W A510 AND $PE NT FUE t AbbiMBLY R AWUW N T C HA AHL h e sshercq NURL G/CR MBl UN#ATURATED Ft OW AND 1RANSPOHI THhDUGH F RACTURE D HOCK HELAi! D TO HIGH t(Vit W AS1[

THOMPSON.BM.

DE POST 10Htf 6 finW Hege imate ill NUnf G/CH %% A bE LF-1[ ACHING CUhniCUtUM IOR THE NHC/

M LO* d d l u#bU N "#U W A U " W N I"#

RICKARD,W H.

U#

NU4E G 'CR-4670 hADIONUCLIDL DiSTRIDUTIONS AND MiGRAllON MI CHAN'5MS AT LHALL OW t AND BUHIAI "a t S F ina; heport Of Tlt SZE N.S ft PNL heren'th In ntgatons On The Desintrution, Myabon. And Cm NUHE G/CH M25 HYDhCG N. Al4 DIL UE NT ( >E 10N A TION STUDV w

Dnmeni Of RahnuclKies At Masey F lats > entudy F OR NUCLE AH ht ACTOR SAF [ TY ANALY$l5 RIGGS R.

NUHLG 0933 $12 A P404fT12 ATON OF GLNiRfC SAF ETY IE50ES IG H-4670 kADONUCUDI DiSThillUf ONS AND MIGRATION ROBE RTh0N.D E.

ME CHANISMS AT SHALLOW LAND DUhlAL SITI S' nal Retot Of NURE G /CR-4670 RoDONUCLIDf DISTRfDUTONS AND MiGRATON PNL Rewa@ investgabons On The D$tulevi+n. Mv,on. And Con-MECHANISMS AT SHAlt.OW L AND DURiAL Si'[$ f inal Rew1 Of hennni Of Raionuchdes Al Mase) ' tats. > entud y BN PNL Hewaah In eshptKins On the Dmintaubon. Myst*un And Gun-v fat ) L

((C A A lt 2AllON OF REAC-NU

/CH 54B1 DAT A SUMMAny Rt PC'.T I OR f IS5ON PHDDUCT f

4 TOR DE COMM;SSON!NG W ASTL AND SPENT FULL AS$lMPLy HE Lf AST 1( Si VI-4 HARDA AOL Prog na Rep 3rt TUTU.N K.

ROSS.J W, NUMEG/GR E202 (SilVAT'N OF CONT AINVE N1 PDF MURE LOAD-NUHlG/04 3916 PHE SSUHil( D ME LT L JL CTION IN T O W ATt H ING DUE TO DIREL T CON T AINME NT Ht'AllNG s OR THE TON POOLS PL AN1 ROSS,T.M.

1 VE T E N,tt.

NURE G 1232 V03 502 SAF ET) EV AL UATON RE KWT ON lt NNt s-NUREG/CR 5377. RE VIEW OF THE CHRONIC DPOSURE PATH A AY SE E \\ ALL E Y AUTHOHITY DHOWNS Ft ARY NUCLt AR PtHFOHM MODE LS IN MACi S AND SIT [RAL OTHER WEll *NOWN PROD ANCE PLAN Browns F erry Unit 2 hestart ABillSTIC H!SK ASSES 6 VENT MODEL$

Ruf F L UPDEGR Af F,C D.

NUhEG/CR 3145 VUb GE OPHY SICAL INVE stlG AllONS OF THE NUR( G/CR 5536 DCM3D A DUAL. CONTINUUM. THOt t DIMENSON<

WLSTERN OHO INDIAN A REGION Annuat HegKat.Oct#n 1M9 AL, GHOUND W AT E R F LOW CODE F OR UNSATUR All D. I RAC-Septembef 1990 TURE D. POROUS ME DtA RUSSE L L,N.A.

W ASHINGTON.K E.

NUHEG/CR %tB QUAUTV ASSURANCE PROCfDUhES f:OH THE NUHEG/CR L'a1B QU All1Y ASSURANCE PRCCf DUhlS IDH THE CONT AIN SEVEht RE ACTOR ACCIDE NT COMPUTER CODE CON 1 AIN SEVERE RE ACiOH ACCIDEN1 COMPU1ER CODE SCHROEDER,J A W ATKINS J C.

NUREG/CR %29 AN ASSESSMLNT OF (4WO M A4% lli CONT AIN-NUHEG!CR S%8 G[ Ni hic ISSUE 07 FLEX 10LL WEDGE GATE ME NT CHALLE NGF S F AILURE MODES AND POTENT.AL IMPROVE -

V ALVE TEST Ph0 GRAM Phaw 11 Results And Analyus MINTS IN PE RFORMANCE.

Wt DSTt R.C.S-J E CR-4 47 UNE40$$ DE1EPMINA h0N FOR Aia SAMI Lf A S

ST V SY ST[ MS

• • Nb#

SHAf f f R,C J NURE G 'CR 'i331 ME LCOR AN AL YSE S FOR ACCIDE NT PHOGRE S-b"^'

SiON 15SUF %

PNL Rowarch inveshpbons On the D$tnbulon. A4vatKw And Con-SHT E Y NG AR T,$.

tainment Of Rawnuchdes Al Maiev Flats. tentudy NUREG'CR-496? RE LAY TEST PF03R AM Senus i Viteaton Tests ggg ST AMPS.D.W.

NUREG'CR Lo39 UNCr HT A:NT Y [V ALU ATION METHODS FOR NUHEG'CH M25 HYDROGEN AIR DiLUF NT DE10N AT ON STUDY W ASTE PACK AGE PERFOHM ANCE ASSE SSMENT FOR NUCt f AR RE ACTOR SAF ETY ANAL'r sES WYNHOFF,N C.

STEELEA NUHEG/CR 5343 R ADONUCL OE CHARACTLn!?ATON OF RE AC-NUHEG/CR 5%8 GENEFuC !$SUL 67 FLE UBL E W E D'il GATL TOR DECOMM SSONlNG W ASTE AND SFENT FUE L ASSEMBLY V ALVE ltST PH0 GRAM P%se 11 Acusts And Ansyus HARDW AAE Pitvess Report SULU V AN.K.

Y ASUD A.D.D.

NUREG'CR %% AG!N3 ASMSSMENT Or THE WE$TINGHOUSE NURE G'CR %58 F PF P 2 A CODE FOR FOLLOMNG AlRBORNE FIS-PWR CONTROL HOD PR!VE SYSTEM SON PRODUCTS IN GENERIC NUCLE AR PL ANT F LOW PATHS.

SUMME RS.R M.

YOUNG C.

NUREG/C4 M31 MELCOR 10 0 A COMPUTER CODE FOR NUCLI AR NUREG/CR 3145 Vo9 GECPH v 5tC AL INVL SilG AtlONS OF 1 HE RE ACTOR bEVERE ACODE NT SOU4E E TERM AND RISK ASSESS AE Sf L AN ONO-INDI AN A R[GON Ann al Repor1JAtote 1989 s

ME NT ANALYSES beNember 1930

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

NUREG 1434 V2 DHF FC ST ANDARD TECHNICAL SPLCIFICAllONS Abnormef 0(currence NUHlG 0090 V13 ND4 RE POHT TO CONGhtSS ON ADNORMAL G[ NI H AL [ L E C1RIC PL ANT S, BWR/6Daws (Soctons 20 OCCURHf NCES October Decemter 1W3 3 31 Draft He< ort For Cornnent NUhlO 1434 V3 DHF FC ST ANDAND TECHNICAL SPf CIFICATIONS 4

(K V13 t03 HLPOR1 10 CONGHLSS ON ABNORMAL

^f' p

CKTURRE NCE S July September 1990 NUPEG/CR %2v AN ASSL SbMENT OF DWH MAHA 111 COfif AIN.

MLNT CHALL[NGES F ALLURE MODt S ANC POltNTIAL IMPHOVC.

Abstract MLNTS IN PF'1FORMANCE-NUHtG 0304 V15 N04 Nf GULATORY AND itCHNICAL REPOHIS tABSTRACT INDEX JOUNNAL) Annual ConWahon f or 1WO bond 6trength NUHEG/CR 4705 DOND S1HLNGTH OF CEM(NN110VS DOHt HOL E Aggregate NUNLG/CR 4235 bl LIC1lON OF SILICE OUS AGGRE G AT E FOR PLUGS lN WE LDE D 1UF F CONCHETE porehole Plu0 NUREC/CR-4295 DOND STHINGIH OF CtMEN11TIOUS DOR [ HOLE Aging NUHEG/CH %% AGING ASSLSSMLN1 OF THE WESTINGHOU$E PLUGS IN WE LDED TUF F.

PWH CONTROL ROD DRIVE SYSTEM.

Budget Estimate W61W V07 Wat NAM S F mcal Yen's W W G F45 LINT LOSS DLTCHMINATION FOR AlH SAMPI L A 0*

CONT AIN NUNE G/CH M18 OUALITY ASSUR ANCE PROCE DURLS F OR THL BWR CONTAIN SEVEDL HE ACTOR ACCIDENT COMPUTf 4 CODE-N9HLG 1433 Vi DRF FC ST ANDARD TECHNICAL SPECIFICATIONS GLNLH AL ELE CTRIC UN118 UWR/4 5peahcatont Draft Report F or CSNI Workshop NUREG 1433 V2 DRF 8;C STANDARD TLCHNICAL SPECIFICAllONS NUHEG/CP-0115 PROCLtDINGS OF THE CSNI WOhitSHOP DN PSA Comment Gt NEH AL Ett C1 HIC UN115, DWR/4 Bases (Soctions 2 0 3 3, Dva t APPLICATIONS AND LIMlf ATIONS r

Report F or Crnment Nuht G 143') V3 DRF F C MT ANDARD T[UHNICAL SPECIFICATIONS Chemical Toucity GLNE HAL CLECTRIC UNITS, BWR/4 Danes (Sectinha 3 4 310)(katt NURLG 1391 CH[MICAL TOxlCITY OF URANIUM hey AF LVORIDE F9 port For Comment COMPAHED f O ACUTC l'F F[C1S OF AADIATlON Final Roport NUHEG-1434 V1 D4F FC ST ANDARD 1LCHNICAL SPECiflCAllONS GENLRAL ELE CTRIC PLANTS, DWR/6 Speahcahons Draft Report f or Closeout ffR S NL (

4 4 V2 DRF F C. ST ANDARD TECHNICAL DPCCIFICATIONS TW N

GENERAL E L ECTRIC PLANTS, BWRI0 bases (Socions 20 Nunf G/CR 5708 CLOSIOUT OF lE BULLETIN PO46(NGi4f thED SAFETY FC ATURE (ESF ) RESET CONTROLS.

3DFh NDARD TECHNICAL SPECiflCAflONS NUREG/CR $309 CLOSLOUT Or IE BULLETIN 83-OL APPARE NTLY NF 434 GENERAL ELE CTRIC PLANTS, BWR/6 Dates (Sochons 34 iRAUDuttNT PHODUCTS SOLD DY RAY MILLER,lNC 3101Dra t Report For Communt r

NUHEu/CR 5529 AN ASSES $ME.NT OF DWR MARK 111 CONT AIN-Combustion Engineering MENT CHALLENGES. F ALLURE MODE S. AND POTENTIAL IMPROVE-NUREG.144 VI DAF FC ST ANDARD 1[CHNICAL SPECIFICAllONS ME NT S IN PLHF ORM ANCE COMBUSTION E NGINEE RING PLANTS Speahcationt DeMt Report 8 or Comment Babcock And Wilcon hvRLG 1432 V2 DHF FC ST ANDARD TLCHNICAL SPLCIFICAf TONS NURE G-1430 V) 00F FC-ST ANDARD TECHNICAL SPECIFICAT60NS BABCOCK AND WILCOx PLANTS Specthcabons Draft Report For COMBUST:ON E NGINCI NING PLANT S Bases (Sections 20 3 31 Drsh Report F or Comment Comment NUHEG 1430 V2 DHF FC ST ANDARD TECHNICAL SPECIFICATIONS NUREG-1432 V3 DRF FC STANDARD TECHNICAL SPECIFICAllONS BABCOCA AND WILCOX PLANTS Dates (Secbons 2 0 3 3) Ewatt COMBUSTION ENGINE ERING PLAN 1 S hases (Sectioris 34 N

14X FC. ST ANDARD TECHNICAL SPECIFICATIONS BADCOCK AND WILCOX PLANTS Danes (Sechons 3 4 3 9) Draft Component Performance Report For Comment NUREG/CR 56% A SYSit malic APPHOACH TO Rf PETITIVE F AIL-URES.

Doll 6ng Water Reactor NUHEG 1433 V1 DRF FC ST ANDARD TECHNICAL SPECIFICATIONS GE AL ELL 'RIC UN'TS. DWR/4 Specahcahons Ekatt Heport f or N FyEG/

$518 QUAllTY ASSURANCE PROCEDURES FOR THE CONT AIN SEVERE RE ACTOR ACCIDE NT COMPUTER CODE NUREG 1433 V2 DRF FC STANDARD TECHNICAL SPECIFICATIONS NUHLG/CR M31 MELCOR 18 0 A COMPUTER CODE FOn NUCLE AR GENERAL ELECTRIC UNITS, BWR/4 Dasos (Socbons 2 0 - 3 3) Draft RE ACTOR SEVEHE ACCIDENT SOURCE TEAM AND RISK ASSLSS-Ramrt For Comment MENT ANALYSES NUH[G-1433 v3 DHF FC ST ANDARD TECHNtCAL SPECIFICATIONS NUREGICR-M36 DCM3D A DUAL CONTINUUM, THREE-D;Mi NSION-GE NE RAL ELECTRIC UNITS, BWR/4 Bases (Sechons 3 4 310) Dra t AL. GHOUND-WATER FLOW CODE FOR UNSATUHATED FRAC-r Repor1 For Comment TURED. POHOUS MEDIA NUHLG 1434 V1 DRF FC ST ANDmHO TECHNICAL SPECIFICAllONS NUREG'OR %18 USER S MANUAL FOR THE NEFTRAN ll COMPUT-Cf NE RAL ElrCTRIC PLANTS, BWR!6 Specihcahons Draft Report F or Comment i R CODE.

I 19

20 Subject index c

NURE G/CR %56 E XT R AN A COMPUTER CODt FOR E SilMATING Doolmetry CONCENTRATONS OF 10xlO SUBST ANCE S AT CONTROL ROOM NUHEG'CR $139 DOSE RE DUCTION TE CHNIOUES FOR HIGH DOSE A!R INT A> LS WORLER GROUPS IN NUCLE AR POWE R PL ANib NURL G/CR %67. INEL Pt RSONAL COMPL'TE R VERSON OF MACCS 16 Durstillity NURE G/CR-4235 SE L E CTION OF sillCEOUS AC.GRE G AT E FOR Conceptual Model CONCRE1E NUREG/CR4495 CONCEPTUAll2ATION OF A HVPOTHETICAL HIGH LEVEL NUCLE AR W AST E RE POS! TOR Y SIT E IN EXTR AN Computer Code UNSATURATE D F RACTURE D TUF F NUPEG/CF4 %% Ex1RAN A COMPUTt R CODE FDR E STIM ATING CONCE NTRATIONS OF TOxlO SUBST ANCES Al CONTROL ROOM Concrete A!R INT ALES NUREG/CR 4235 SE LE CT ON OF SillCEOUS AGGREGATE FOR CONCRE1E E arthq ; Ae NUREG/CA-4269 MODE LS OF TRANSPORT PROCESSES IN CON-NUREG/CR 3145 W9 GE OPHYtlCAL INVE S tiG ATIONS OF THE CRETE

@ STERN OH 0 INDIANA REGION Annual Report Octotier 1989 9 stemt,er 1993 NURE G/CR %54 CONT A;NME NT VENTING ANALYSIS FOR THE Electric Cable SHOREHAM NUCLEAR POWER ST ATON NUREG/CR 5619 THE IMPACT OF THERMAL AGING ON THE FLAM MABILITY OF ELECTRIC CABLE S Containment Hastirig NUREG/CR 5)e2 E STIMAtlON OF CONT AINME NT PRESSURE LOAD-Enforcement Action ING DUE TO DtRECT CONT AINVENT HEATING FOR THE 2ON NUREG 0940 V09 NO4 ENFORCEMENT ACTIONS SIGNIFICANT AC.

PLAN T.

T ONS RE SOLVE D Osanorty Progens Repor10ctote Decemt.et Containment Pressure NUREG/CR 6282 ESilMATION OF CONT A!NMENT PRESSURE LOAD-Engineered Safety 7 esture ING DUE TO DIFIECT CONT AINMENT HE ATING FOR THE ZION NUREG/CR 62M CLOSLOUT Or IE BULLETIN BO-06 LNGINEERED PLANT SA8 ETY FE ATURE (ESF) RESET CONTROLS Control Ftod Drive Esposure Pathwsy NUREG/CR55% AGING ASSE5SMENT OF THE WESTINGHOUSE NUREG/CR 6377. REVIEW OF THE CHRONIC LkPOSURE PATHWAY PWR CONTROL ROD DRIVE SYSTEM MODELS IN MACCS AND SEVERAL OTHER WELL-KNOWN PROB-ABILi$rC FuSK ASSESSMENT MODELS NUREG/CR %56 EXTRAN A COMPUTER CODE FOR ESTIMATING FPp P 2 CONCENTRATIONS OF TOxlC SUBST ANCl$ AT CONFROL ROOM NUREG/CR %% FoFP 2. A CODE FOR FOLLOWING AIRBORNE FIS-AIR INT AKE S SiON PRODUCTS IN GENE RIC NUCt C AR PLAN T FLOW PA1HS Core Melt Feedwater System Piping NUREG/C9 5654 CONT AINME NT VENTING ANALYSIS FOR THE NUREG/CR 52t 5 CLOSEOUT OF 10 BULLETIN 7913 CRACK.NG IN SHOREHAM NUCL1 AR POWER ST ATION FELOW ATER SYS1EM PIPING Corrosion Finsson NUREG!CR 4269 MODELS OF TRANSPORT PROCESSES IN CON-NUREG/GR 5461. DATA

SUMMARY

REPORT FOR FISSON PRODUCT CRETE RELEASE TEST VI-4 Cracking Fleston Product NUREG/CR 5285 CLO3EOUT OF lE BULLETIN 79+13 CRACMNG IN NUREG/CR %58 FPFP 2 A CODE FOR FOLLOWING AIRBORNE FIS F E E DWATER SYSTEM PIPING SiON PRODUCTS IN GENERIC NUCLF AR PLANT FLOW PATHS Cross Byetem Failure Flamma54tity NUREG-1275 V06 OPERATING EXPERlENCE FELDBACK REPORT NUREG/CR 6610 THE IMPACT OF THERMAL AGING ON THE FLAM-SOLENOO OPERAILD VALVE PRODLEMS Commerpal Power Reac-MABILITY OF ELECTRIC CABLES tors Flow Path DCM3D NUREG/CR %$8 FPFP 2 A CODE FOR FOLLOWINu AIRBORNE FIS NUREG/CR 5516 DCM3D A DUAL CONTINUUM, THREE -DIME NGON-SiON PRODUCTS IN GENERIC NUCLE AR PLANT FLOW PATHS AL, GROUND W ATER FLOW CODE FOR UNSATURATE D. FRAC-TURED, POROUS MEDIA Fracture Mechanica NUR E G 'CP-0037: PROCEEDINGS OF THE SEMINAR ON ASSESS, Decommissionin0 MENT OF FRACTURE PREDICTION TECHNOLOGY, PiPIN3 AND NUREG/CR 5343 RADIONUCLIDE CHARACTER 12AllON OF REAC-PRESSURE VESSEL S TOR DECOMM'SSONING W ASTE AND SPENT FUEL ASSEMBLY NUREG/CR 5577: EXTE NSION AND EX TRAPOL ATION OF JR HARDW ARE Pro 7ess Report CURVES AND THEIR APPLICATON TO THE LOW UPPER bHELF TOUGHNESSISSUE.

Deal n Control PracGeo 0

NUREG-1397. AN ASSESSMENT Or DFSIGN CONTROL PRACTICES Fractured Rock AND DESIGN RECONSTITUTION PROGRAMS IN THE NUCLEAR NUREG/CR 5581.

UNSATURATED F LOW AND TRANSPORT POWER INDUSTRY.

THROUGH FRACTURED ROCK RELATED TO HIGH LEVEL vv ASTE

~

Design Reconstitutlon Program NUREG 1397. AN ASSESSMENT OF DESIGN CONTROL PRACTICES Fractured Tuff AND DESIGN RECONSTITUTION PROGRAMS IN THE NUCLEAR NUREG/CR44%. CONCEPTUAll2ATtON OF A HYPOTHETICAL HIGH-POWER INDUSTRY LEVEL NJCLEAR WASTE REPOSITORY SITE IN UNSATURATED. FRACTURE D TUF F.

Setonation NUREG/CR 5525 HYDROGE N-AIR-DILVENT DETONATION STUJY Fraudulent Product FOR NUCLEAR REACTOR SAFETY ANALYSES.

NUREG/CR-5309 CLOSEQUT OF IE BULLETIN R3 07. APPARENTLY Dose-Reduction Technique NUREG/CR-St39 DOSE REDUCTION TECHNOUES FOR HIGH-DOSE Frequency Response WORKER GROUPS IN NUCLE AR POWER PLANTS NUREG/CR 4867. RELAY TEST PROGRAM Senes i V4*Etion Tests 1

Subject Index 21 Isoiauon Valve F uel Damage NUHL GWR 54B1 BAT A SUMM Ahi HE PO41 F OR F 15504 l'RODUC1 NUREG/CR L%8 GENEHiC ISSUE 67 i LE AltkE WE DGE G AT E HELE ASE 1LST VI 4 V ALVE T ES1 P40 GRAM Phaw 11 Rewts Ami Ana%ss F uel Disrup6on J-R Cur,e NUhEG/CR 5312 A thE RMDDv h AMIC MODEL Or FUE L dis 4#

NUHtG/ER W 7

[.11[ N5lON AND E X1 R ADOLA T ON Cd JR TIDN IN Si 1.

CU4/E5 AND THEin APPUCATON TO 1HE LOW UPPER SHELF T OUGHNE SS ISSUL Oonerel E 6*ctric NUREG 1433 V1 DHF FC ST ANDARD TECHN' CAL SPECiriCAf TONS LER GENER AL E LE CTRIC Units DWFU4 Speuf<et.ons Drau Report F or NUPE G LH 2XC V09N12 LICEN5E E E VE NT REPORT (LER)

Comment COMDn ATION F or Msnth Of Decemter 1W3 NURE G 1433 V2 DRF FC ST ANDARD TE CHNiCA1. SN CJICATONS NURE G/CR 2300 V10 N1.

LICE NSE E EVENT REPORT S E R)

GE NERAL EL E CTRO UN!TS DAH'4 Banes (Snctons 2 0 3 0l DraN cpypit ATON F or Month Of JaNry tm Report For Comment NUREG 1433 V3 DHF F C ST ANDARD 1ECHNICAL SPEC 4 ICAT ONS Legal issuancet GENERAL ELE CthC UNITS. BWH/4 Braes (Sectons 3 4 310) DraN NURE G 07!4 V32 N05 NUCLE AR REGULATORY COMMISS DN IS Repor1 For Commnt SUANCE S FOH NOSE MDER IW9 Pages 333 393 NURL G 1434 V1 DHF FC ST AND%RD TECHNICAL SPECIF K \\110NS NunEG-0750 V32 N% NUCLE AR HEOULATOHY COMM!SSON IS-GENLRAL E LECThtC PLANTS. EtWn/6 Spedicatons Dra'1 RV t ' n' SUANCES FOR DECEMDEh IW3 Pa3es 3W4M Comment NURE G 0750 V33 NO1 NUCL E AR hi GUL A10H f COMMtSSON IS NUhEG 104 V2 DRr F C ST ANDARD TE CHNICAL SP[ CiflCA10NS SUANCES F OR JANUARY 1991 Page 140 GE NE R AL E L ECT RIC PLAN 15. EtWR/6 Bese s (Se@ons 20 3 3) Dea 4 Repor1 F or Emment L6 cense Appl 6 cation NUME G 1434 V3 DhF F C S1 ANDARD 1ECHNICAL SPE C:F ICA t lON5 NUHE G 1199 R02 ST ANDARD FORMAT AND CONTENT OF A U-GE NE RAL E L E Cl HIC PL ANT S.

BWR/6 Dason (Soctions 34 EENSE APPUCAllDN IOR A LOh LEVE L RADOAC11VE W ASTE 310) Eheft Remw1 F or Comment p;spO;At r Antity.

NURE G.1200 R02 ST ANDAHD hlWEW PLAN F OR THE RE vie W OF A Generic issue SF t.ICI NSE APPLICATION F OH A LOW LEVE L RADOACTIVE W ASTE NUREG/CR 5558 GENE RIC ISSUE 87. F LE MOLE WEDGE Gall DnPOSAL F ADU1Y V ALVE TE ST PROGRAM Phase 11 Hesta"s And Anahs4 Licensed Fuel Facility status Report Generic $stety issue WREG000 V10 UCENSED F UE L F ACluTV STATUS NUREG 0933 $12 A PROR!TIZATON OF GENERIC SAF ETY ISSUE S HE POR T 1%er tory DWeente Data Juh 19M Jono 1WO (G!ay DotA la Groundwster NURE G/CR 5516 DCM3D A DUAL. CONTINUUM. THRE E O'ME NSON Wensee bent Repon AL, GROUNSWAf EH F LOW GODE F On UNsA1URA tED, i n AC, NURE G/CRWJD V09N12 L ICE NSE E E VE NT REPORT (LER)

TURED. POROUS ML DIA COMPIL AT ON Fm Month Of Decomt+f 1WO NURE G/CR 2000 V10 N1 UCENSE E EVlNT REPORT (LEH)

High Dose COMPtLATION For Mantn Of January 1991 NURLG/CR $139 EOSl REDUCitON TECHNOUl S IOH HIGH DOSE WORKER GROUPS IN NUCLE AR F*DWER PLANTS Line P oss NUHEG/CH 4757 LINE LOSS DETERMINATION F OR AIR SAMDLER H6gh Levet Nuclear Waste NUNEG/CR 5495 CCNCEPTUAU2ATION OF A HvPOTHE TICAL HOH S YSTE MS LEVEL NUCL E AR W AS1E RE POSIT OR Y SIT E IN Loading UNLATUH ATCD FRACTURED 7 UF F NUREG/CR 5262 E STIM ATON OF CONTAINMENT PicESSURE LOAD.

ING DUE TO DIRECT CON 1 AINWNT HE ATING FOR THE ZION High-L evel Radloactive Weste Disposal NUf;EG/CH $618 USER'S MANUAL F OH THE NEFTRAN 11 COMPUT.

PLANT.

ER CODE LoeLevel Radioactive Weste High-Level Radionue Jo Weste Management NURE G/CR 5432 V01 RECOMMENDATONS TO THr NRC FOR SOtl NURE GICR 5639 UNCE HT AINTY Ev ALUA10N MET HODS FOH COVER SYSTEM ~

ER URANIUM MILL TAlt iNGS AND LOW-W ASTE PACK.GE PE RF ORMANCE ASSESSMENT LEVEL RADOACTIVL vn ASTES IdentAcaton And Ranking Of Soils f or Denal F accty Covers High-Level Weste Repository NUHf G/CR 502 V02 RE COMMENDATIONS TO THE NRC FOR SOtt NUREG/CR 5581 UNS ATUR ATED F LOW AND TRANSPORT COVER SYSTE MS OVER URANIUM MILL T AluNGS ANO LOW-THROUGH FRACTURED ROCA RE LATED TO HGH LEVEL W ASTE LEVEL RADIOACTIVE W ASTES Labcentary And Field Tests for Son REPOSITORIE S Final Report - Phase tu ces NUREG/CR 502 V03 RECOMVE NDATIONS TO 'HE NRC FOR SOlt.

Hydrogen Combustion COVER SYSTEMS OVER URANIUM MILL T AILINGS AND LOW-NUREG/CR 5525 HYDROGEN AIR-DiLUE NT DE TON A10N STUDY LE VEL RADICACTIVE WASTES Constructon Metnods And Gudance FOR NUCLE AR RE ACTOR SAFETY ANALYSES For Sewg Penetratens in Sod Covers NURE G/GR M72 V01. CHARACTE R1SilCS Of TOW Lent RAD!OAC.

TIVE WASTE Decontaminaton Waste Annuat Report f or Fmcal Year U E i CR-52tl5 CLOSEOU1 OF lE BULLETIN 79-13 CRACMNG IN F FEDW ATER SYSTE M PtPiNG NUREGICR 52148 CLOSEOUT OF IE BULLETIN B0,90 ENG;NEERED Low-Level Radioacttve Weste Disposal NUREG/CR 5539 A set F-1EACHING CURRICULUM FOR THE NRC/

NU R 0 L E U CF LETIN B3 07 APPARENTLY SNL LOW-LEVEL W ASTE PERFORMANCE ASSE SSMENT METHOD-FRAUDULEN'T PRODUCT S SOLD BY RAY M:LLEHJNC.

OLOGY.

incentive Flegulation Low Level Waste NURE G 'CR-4411 INCE NTIVE REGULATON OF NUCLEAR POWER NUHEGrCR4670 RADONUCUDE DtSTR+BUTIONS AND M GRAtlON PLANTS DY STATE REGULATORS MECHANISMS AT SHALLOW L AND BUR:AL SITES Final Report Of PNL Research investigatons Jn The Distrbutton, Mgabon, And Con-lodine NUREGtCR4757. UNE-LOSS DETERM!NATON FOR AIR SAMPLER tainrnent Of Radonuchdes At Maxey Flats, kentucky S4 STE MS Low-level Wasts Disposal triadiated Flencint Fuel NUREG 1199 R02 ST ANDARD FORMA 1 AND CONTENT OF A U-NUR E G-0725 R07 PUBUC INFORM ATON CIRCULAR FOH SHIP-CENSE APPUCATION FOR A LOW LEVEL RADtOACTIVE WASTE MENTS OF IRRADtATCD REACTOR FUEL DI5POSAL FAC1UTY

22 Subject index NUREG.1230 502 ST ANDARD RE Vl0 W PL AN FOR THE REV!E W OF A NUREG 1431 V3 DRr *C ST ANDARD TECHNICAL SPECIF6 CATIONS LICE NSE APPLICATION FOR A LOW L E VE L RADIOACTIVE W ASTE WE STINGHOUSL PLANTS Bases (Sectons 3 4 3 9) Dra't Repo1 For D!SPOSAL F ACILITY Comment NURE G/CH 5343 RADONUCLIDE CHARACTEkl ATION OF RE AC-NUREG 1432 V1 DRF FC ST ANDARD TECHNICAL SPECIFIC ATIONS TOR DI COMM:SSIONtNG W ASTE AND SPENT F UE L ASSE MBLY COM9USTION E NGINE E RING PLANTS Specificabont Draft Repari HARDWARE Proyt$$ Report For Comme t a

NUREG 1432 V2 DRF FC ST ANDARD TECHNICAL SPECIFICADONS MACCS E NGINE E RING PLANTS Bases (Sectons 20 COMBU,STION NUREG/CR 5377 REviE W OF THE CHnONtC E xPOSURE PATH A AY 3 33 p,,, nepn,1 F or Comment MDDtt$ IN MACCS AND SE wE RAL OTHE R WELL-KNOWN PROB-NUREG 1432 V3 DRF FC ST ANDARD TECHNICAL SPECIFICATIONS ADiLISTIC MK ASSESSMENT MODELS COMBUSTION E NGINE E RING PL ANT S Bases (Sec teas 34 3 91 Dratt Report Fof Comment

^

J CF 7

L PERSDNAL COMPUTER VERSION OF MACCS PWR CONTROL ROD ORiVE S1 STEM t5 P 0' *'"C ' A ""'**"I Lt.LCOR NURE GiCR 5331 MELCOR ANALYSES F OR ACCIDE NT PROGRES NUREG!CR %33 A SELF 1EACH!NG CURRICULUM FOR THE NRC/

999 ir,sut s SNL LOW LE' VEL WASTE PERFORMANCE ASSESSMENT METHOD-NUHEG/CR 5531 Mf LCOR 1 B 0 A COMPUTl R CODE FOR NUCLE AH OLOGY RE AC'100 SEVE RE ACCIDENT SOUREE TE RM AND R!SK ASSE SS.

NUREG/CR 5010 VSER S MANUAL FOR THE NEFTRAN I! COMPUT-MENT ANALYSE S E R CODE NURE GICRM39 UNCE RT AINTY EVALU A160N METHODS FOR Maintenance WASTE PACKAGE PE RFORMANCE ASSESSMENT NURE GeCR %66 PROGRAMMATC ROOT CAUSE ANALYSIS OF MalNTE NANCE PE RSONNE L PEHFORMANCE PROOLE MS Performance History NUREG/CH MM A PROCESS FOR R15k FOCUSED MAINTENANCE NUREG 1214 R07 HISTORICAL DAT A

SUMMARY

Or THE SYSTEMAT-Mark til Containment NUREG/CR 5529 AN ASSESSMENT OF EWR MARK 11! CONT A1N-Personnel Perf ormance MENT CHALLE NGES F AILURE MODES, AND PO1ENTIAL IMPROVE' NURE G/CR4%6 PROGRAMMATIC ROOT CAUSE ANALYSIS OF ML NTS IN PERFORVANCE MAINTENANCE PERSONNEL PERFORMANCE PROOLEMS Mechanical Vibration Petitions For Rulemaking NURE G/CR 4867 RE LAY TEST PROGRAM Sones I Wtwaton Tests NUREG 0936 V09 N34 NRC RE GULATORY AGEND A Ouartetty Migration Report October Decemter 1990 NURE G'CD 4670 R AD!ONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL S!1ES Final thport Of Jf E G /CP-0037. PROCEED:NGS Or THE SI MINAR ON ASSESS-PNL Recorc.h invest,gabons On The Eutobution. Migrabon. And Con.

MENT OF FRACTURE PREDICTION TECHNOLOGY. PIPING AND ta:nment Of Radionachdes At Mamey Flats. Kentuch pg NEFTP AN 11 Computer Code NORE G/CRER USER'S MANUAL FOR THE NEFTR AN 11 COMPUT.

Practice And Procedure D6 gest ERCODL NUREG-O%6 E'95 R09 UNITED 5TATES NUCLE AR REGULATORY COMMISSION STAFF PR ACTICE AND PROCEDURE Nuclear Air Ciceuing DIGEST Commisson Appeal Board And Ocensing Doard NUREG/CP Oi tt; VD1 PROCEEDINGS OF THE 21ST DOL 'NRC NU-Decisons. July 1972 Septemte 1930 CLE AR A'R CLE AN;NG CONFERENCE Sessons 1. B Held in San Diep Cetynia, August 13-16 19w Pressure Vessel NURL G'CP 0116 V02 PROCEEDINGS OF THE 21ST DOE!NRC NU.

NUR E G /CP-0037 PROCEEDINGS OF THE SEMINAR ON ASSESS-CLEAR AIR CLL AfitNG CONFERENCE SESSIONS 9 - 16 Heid in San ME NT OF FRACTURE PREDICTION TECHNOLOGY. PIPING AND Den CaMoma. Augast 1116,1990 PRESSURE VESSELS Nuclear Medicine Pressurized Melt L)ection NUREG/CR 4444 RADiATtON SAFETY ISSUE S RE LATED TO RADIO-NUREG/CR 3916 PRESSURt2ED MELT EJECTION INTO WATER L ABELED ANflBODlES POOLS Nuclear Power Plant Pressurtzed Water Reactor NURE GICR 411 INCENTIVE REGUL ATION OF NUCLE AR POWER NUREG 1430 V1 DRF FC. ST ANDARD TECHNICAL SPECIFICATIONS PLANTS BY ST ATE REGULATORS BABCOCK AND WILCOX PLANTS Specificatons Draft Report f or Comment Occupational E xposure NURE G-1430 V2 DRF FC-ST ANDARD TECHNICAL SPECIFICATIONS NURE G/CR 5139 DOSE-REDUCTION TECHv00ES FOR HIGH DOSE BABCOCK AND WILCOX PLANTS. Bases (Sectons 2 0 - M) Dram WORF ER GROUPS IN NVCLEAR POAER PLANTS Report FC,r Comment.

NUREG 1430 V3 DAF FC STANDARD TECHNICAL SPECIF6 CATIONS Opers%ng Exper6ence Feedback Report BABCOCK AND WILCOx PLANTS. Bases (Sections 3 4 - 3 9) Draft NUREG-1275 vo6 OPERATING EXPERIENCE FEEDBACK REPORT SOLENOID OPE RATED VAlkE PROBLE9S Commercias Power Reac-(*

h*]",t WESTINGHOUSE PLANTS Spockabons Dra't Repon For Comment PWR NUREG-1431 V2 DRF FC ST ANDARD TECHNICAL SPECIFICATIONS NUREG-1430 V1 DAF FC ST ANDARD TECHNtCAL SPECIFICATIONS WE STINGHOUSE PLANTS Bases (Sections 2 0-3 3) Draft Roport For D C K AND WILCOx PLANTS Speaticon is Draft Peport For nt p

NUREG 1430 V2 DAF FC ST ANDARD TECHNICAL SPECiriCATIONS WESTINGHOUSE PLANTS Bases (Sectons 3 4 3 9) Dratt Report For BABCOCK AND WtCOx PLANTS Eases (Sectons 2 0 3 3)Deatt Comment.

Report Fcr Cemment NUREG 1432 V1 DRF FC ST ANDARD TECHNICAL SPECIFICATIONS NURtG-1430 "3 DRr rC; STANDARD TECHNICAL SPECIFICATIONS COMBUSTION E NGtNE E RING PLANTS Speaficabons Dratt Report BABCOCK AND M COE PLANTS Bms (Sectons 3 4 3 9) Draft for Comment ReNrt For Comment NUREG-1432 V2 DRF FC ST ANDARD TECHNICAL SPECIFICATIONS NUREG 1431 V1 DNF FC STANDARD TECHNICAL SFECIF CATIONS COMBUSTION E NG:NE ERtNG PL ANTS Baws (Sectons 2.0 4

WESTINGHOUSE PL ANTS SpxAcat oq Drah Aeport For Comment 3 3) Dra*1 Report For Comment NURE G-i a31 v2 DRF rC S T ANDARD TECHNICAL SPECiF 6 CATIONS NUREG-1432 '/3 DRF FC ST ANDARD TECHNtCAL SPECIFICATIONS WESTINGHOUSE PLANTS Rases (Sectons 2 0-3 3) Dra't Report For COMBUST PON ENGINEER 6NG PLANTS Baws (Sectons 34 Comment 3 9; Dran RePu t For Comment l

Subject index 23 NU4EG,CH 5555 AGING A55ESSME NT OF THE WE 5 f tNGHOUSE Repository Site PWR CONTROL ROD DFUVE SYSTEM NURF G/CH 54% CONCEPfvAlll ATON Of A HvPOTHEICAL HM LE y t.4 NUCLE AH WASTE h[ PDst100 y sit i IN Primary Coolant System UNSA f uh All D F R AC1URE D TUF r NUREG/CR %72 VQt. CHARACT[.HISTICS Or LOW LE VE L HADIDAC ifVE W ASTE. Decontamartstion Waste Annual Report F or f oal Yea' Restari 1M NuhEG 1232 V03 602 SAF E h EV AtUAllON HiiChi 04 ilNNI 5 b

N#

Probabilistic Hisk Analysts

^

• I ## # E NUREG-1150 V03 SEVEHE ACCIDE NT htSAS AN ASSE SSME NT FCH I IVE U S NUCLE AR POWE R PLANTS APPendues D And E hna' ng NUREG OW33 $12 A PHOHITil AllON Or GIN!4tC SAFily ISSUE S Probabilistic Risk Assessment NDOI C80" NUHEG/CR-5377 HEvtEW OF THE CHRONIC ElrPOSURE PATHW Af NURE G/Ch %4 PROGhAMMATIC 6001 CAUM ANALYSIS OF MODELS IN MACCS AND SEVERAL OTHER WELLA NOWN PHOB.

MAINTENANCE PE HSONNtt Pt rd OhMANCE FHOULIMS ABILISTIC RISK ASSESSMENT MODE tS NUME G/CR 5531. MELCOR 1 h 0 A COMPUTE R CODE FOR NUCLE AR D

RE AC10R SEVERE ACCIDENT SOURCE 1ERM AND RISA ASSI SS NUhlb 09'56 V09 4 34 NHC hl GUL ATDRY Aut NDA Ot.riony MENT ANALYSES Report Octate De:emter 19M Probabinstic Safety Assessment NUHf G/CP4115. PROCEEDINGS OF THE C5N1 WORKSHOP 04 PSA Hules Of Practice APPLICATIONS AND LIMIT AllONS NUREG 03a6 Dot R09 TINGE D Sf All h NUCLI AR Rf UUL AID 4V COMM(SSION

$1 AFF PR ACYlCI AND Ph()C[ Duht Proceedings DG ST Commwyn.

Appea!

lurd And L n ensing the:1 NURE G/CP 0037 PROCE E D:NGS OF IHL SEMINAR ON ASSE SS-peog,on,jui,3977. sppg,ncor39ag MENT OF FRACTURE PHEDICTION TECHNOLOGY hhNG AND PRE SSURE VESTELS st.1 Test NUREGICP 0115 PHOCEEDINGS OF THE CSNI WO4ASHOP DN PSA NURE G/CH 5312 A THl hMODYNAMC MODE L OF F Ull DtbHUP-APPLICATIONS AND LIMITATIONS llON IN ST-1 NUHE G/CP4116 V01 Ph0CEEDiNGS OF THE 21ST DOL /NHC NO.

CLEAR AIR CLE ANING CONFERE NCE SMasons 1 G Hold in S" Safety Evaluation Report 2

b^' f

^

" "( " "

NU E /

16 VO F E E'D S OF THE PIST DOL /NHC NU-SEE V ALLEY AUTHO nY DROWN 5FEHHy UCLi AH PI HF ohm CLE AR AIR CLEANING CONF EhiNCE SESSONS 9 16 Hofd in San ANCE PL AN Browns Ferry Unit 2 Hestri Diogo. California. August t's 16,1990 NUhl G 1382 SAF El y ( V Al U ATION hlPOH1 hf Lt.1E D TO 1HL F ULLMHH OPl RATING LICE NFE FOR OYSTER CHEE A NUCLE AR Quality Assurance GENE HATING ST ATON Domt Na 50 219 tGenuf at Pvtmc Ut*to NUi TG/CR 5518 OU ALIT Y ASSURANCE PROCEDURES FOR THE CONTAIN SEVERE RE AClOR ACCIDENT COMPUTER CODE Nudoa' Cap et al)

Sately issue Radnauon NUREGA331' CHEMlCAL TOxlCITY OF UR ANIUM HE X AF t.UORiDE NUAC G 1435 VD1 ST ATUS OF-SAiETY IS5U( S AT llCENSLD COMPARED TO ACUTE EF FECTS OF P ADIATION Finat Report POWEH PLANTS TMi Action han Requoements NUREG/CR-4444 RADIAllON SAF ETY ISSUE S ret All D TO HADIO-LAEiLLED ANTIBODIES S sismicity NURE G/CR 3145 V09 GE OPHY SIC AL IN VE ST tG ATIONS OF T H(

Radnotabeled Antibody WESTERN OHiOaND;ANA hi GON Annuai hepntt,0ciate 1 i+ 9 NUREG /CR-4444 RADIATION SAF ETY IS5UES RELATED TO RADIO-g g,m We1990 LABELED ANTIEsODIES Service Life N REG /C R DIONUCLIDE D;S1R$UllONS AND MiGHATION MECHANISMS AT SHALLOW LAND DUR;AL SITES hnal Report Of PNL Research Investigations On The Dir.tnbubon, Myabon. And Con-Severe Accident tamment Of Ha$onuchdes At Mamey flats Aentey NUREG/CR 5331 MELCOH ANALY51 S F OR ACCIDENT PHOGnf 5 SiON is5UE S Reactor Cavity NUREG/CH 5529 AN AME 55ME NT OF DWH MAhk lil CONT AiN NUHEG/CR 3916 PRESSUR; LED MELT EJE CT ON INTO W A1E R ME NT CHALLENGES F Alt uRE MODE h AND POTENilAL iMPHOvl-POcts Mf.NT S IN PL RF OHM ANCE NUAEG/CR 5531 MELCOR 18 0 A COMPUTER CODE F 00 NUCLi AR Reactor Safety RE ACTOR SEVt RE ACCIDENT SOURCE TE OM AND R15h A5SLSS-NURE GICR-5525 HYDROGE N-AIR-D!LUE NT DE TON ATION STUDY FOR NUCLEAR REACTOR SAF ETY %NALYSES MENT AN ALYSES Regulatory Agenda Severe Accident Risk NU4E G 0036 V09 N04 NRC REGULATOR Y AGENDA Ouarter y NUREG.1150 V03 SEVERE ACCIDE NT RiRS AN ASSE SSME NT F OH e

Reput. October Docember 190 F IVE U 3 N JCLE AR POWE H PLANIS APWnaices D Ant! E hrd Regulatory And Technical Report NUHEG-0304 V15 t,04 REGULATORY AND TECHNICAL RE PORTS severe Beactor Accident (ABSTRACT INDEx JOURNAL) Annual Compilat.on For 1%0 NUREGJCR 551B OU AllT V ASSUHANCE PROCE DURES FOR THE CONT AIN SEVLHE hl ACTOR ACC DENT COMPUTER CODE Relay Test Program NURE G/CR 4867-9ELAY TEST PROGR AV Senes i Vuation Terds Shallow Land Burial NUREG/CR 4670 RADONUCL1DE DtSf atDUTIONS AND MiGR A1 TON Repetttive f ailure M[ CHANISMS Al SHALLOW LAND OUHtAL Sl!E 5 hnal Report Oi NUREG'CR SM5 A SYSTEMAllC APPROACH TO REPETiliVE F AIL.

PNL Rewrch inveshgadora On The Dstot ubon Mganon, And Con.

UHf S Report To Congress NUREG 000 V13 NO3 REPORT TO CONGR2SS ON ARNORMAL Shelf Toughness OCCURRENCES Jay September 1930 NURE G {R-557 7 E X T E NSON AND E X T H APOL A f lON OF 5A NUREG-0090 V13 NS4 hEPORT TO CONGRESS ON ADNO4 MAL CURVES AND THUR APPLICATON TO THE LOW UPPE4 SHELF OCCURRENCE S OctateDocemt e< 1930 TOUGHNE55 IS5UE

f i

2 24 Subject Index doH Cover System NUREG 1434 V3 DRF FC-STANDARD TECHNCAL SPt C!IICATONS NURt G/CH 5432 V01 84lGOMMENDATONS TO THE NRC FOR SOIL GENE R AL (LECTRO PLANTS, B AR/6 Bases (Sectenn 34 COVER SYSTEMS OVlR URANIUM MILT T AILINGS AND LOW-310) Draft R+.irt f or Comment thE L RADCACTIVE WASTE S 1:tentkabon And Rartng Of sons F or Dn.paat F a9ty Caers Byatematic Assessment Of Lkensee Performent's NUREGNH b432 V02 RICOMI/ENDATONS TO THE NRC FOR SO!L NUREG 1214 RDT HISTOHtCAL DAT A

SUMMARY

OF THE SYSTEMAT+

COVER SY3TEMS OVER URANIUM MILL T Altl4GS AND LOW IC AbSESSMENT OF UCENSEE FIRFORMANCE LEvil RADOA0tlVE WASTES (dwatory Arq1 F end Tests for Soit Covers TMI Act6oci Plan NUREGICR 6432 V03 RECOMMENDATONS TO THL NRC FOR SOIL NURIG 143b V01 ST ATUS OF sal f TV ISSUEB AT LICE N5LD COVE R SYd1LMS OVt p URANIUM MILL 1 AILINGS AND LOW-POWt H PLAN 181Mi Acton Pian Requecments LEVf L HADCACTIVE WASTES Contructson Mott 4s And Guitlance f or Seawg Penetsations in basi Cows TectoIC NUREG /CR 3145 V09 GEOPHYSICAL INVt SilGATONS OF THf Solenold-Operated Veno WESTERN OHIO INDIANA REGION Annual Report,0ctoter tLM NUREG-1275 V06 OPLHATING EXPERIENCE FEEDBACK REPORT -

Septemtes IWO E.0LE NO'D OPE 9ATED VALVT PRDOLE MS Commerpal Power Reac-tus Thermal Agine NUREG/CR4619 THE IMPACT CF TtqERMAL AQtNG ON THE FLAM-Sohdification Process MABlUTY OF f LECTRC CABLES NUREG!C4b672 V01: CHARACTiRISTCS OF LOW LEVEL RADCAC.

flVE WASTE Decontam# nation Waste Annual Deport ior Finat Year Thermodynam6e 1990 NUREG/CR S317 A THERMODYNAMC MODEL Or FULL DiSRUP, TON IN S14 NUREG/CR $343' RADONUCLIE'E CHARACTERIZArqON 07 RE AC-Title List TDH DECOMM(S$lONING W ASTE APQ SPENT FUFL AF SEMBLY NUREGM40 V12 N11: itTLt UST OF EOCUMENTS M4RE PUBUCLY HARDWARE Prtyens Report AVAl ADiE. Novemter 130.1WO t

NUREG 0540 V12 N12: TITLE LIST OF LOCUMENTS MADE PUBUCLY Spent Fuel Shipment AVAtt ADL E Decernter 131 1pp NUREG J725 A07. PUDUC INFORMATON CIFICULAR FOR SHIP-NUREG.0540 V13 N01. TITLL'usT Or DOCUMENTS MADE PUDLICLY MENTS Of tRRADIA1ED REACTOR IUEL AVAILADLE, Jermyy 1 31,1991 Standard Format 1 oste Substance NUHEG 1999 F102: STANDARD TORMAT AND CONTENT OF A Ll' NUREG/CR56% LXTRAN A COMPUTER CODE FOR ES11 MATING CENSE APPUCATION FOR A LOW LEVEL RADQACTIVE WA$TE CONCENTRATONS OF 10XIC SUBSTANCES AT CONTROL ROOM DISPOSAL F ACILITY AIR INTAKES Standard Reir'ow Plan NUREG-120s, R02. ST ANDARD REVIEW PLAN f OR THE REVIEW OF A

"[g*R[ ' 's269 MODELS C/ 1RANSPOR1 PROCESSES IN CON E

LICENSE A'PLICAtlON FOR A LOW-LEVEL RADIDAC1tVE WASTE NffhC45681:

DISPOSAL f %CluTY.

UNSATURATED h0W AND TRANSPORT Standard Technica. 4pecificatana THROUGH IRACTURED ROCE f.tiLATED TO HIGSLEVEL WASTE NUREG-1430 V1 DFS FC: $ 'ANDARD TECHNIC *l Sf 4 (F.cA TtONS REPOSITORIES Final Report 4 Phase ill K AND WILw M ALANTS Specificatons Draft Repnrs For Urisaturated Flow NUREG 1430 V2 DRF FC, STANDARD TECHNICAL SPECIFICAllONS NUREG/CR $536 DCM3D A DUAL CONTINUUM, THREE DiMENGION-BABCOCK AND WILCOX PLANTE Dases (Sections 7 0 - 3 31 Draft Al GROUND-W ATER FLOW CODr FOR UNSATURATED, FRAC-Repnr1 For Comment 1URED. POROUS MEDIA-NURE G 1430 V3 DRF FC. STANDARD TECHNCAL SPECIFICATIONS N sa BADCL K AND W LCOX PLANTS Bases (Sections 3 4 3 rR Draft yg13gl C EMCAL TOCCITY OF URANIUM HFxAFLt,ORIDE NUFN143) VI DAF FC: ST AND6AD TECHNICAL ',,PECIF6CATONS COMPARED TO ACUTE EFFECIS OF R ADIATION Final Remt WESTINGHOUSE PLANTS SpeJfications Draft Report For Comment NUREG 1431 V2 DAF FC, ST ANDARD TECHNICAL SPECIFICATIONS Uranium Mill Talling WESTINGHOUSE PLANTS 0ases (Sections 2 0-3 3)Dratt Report Fo, NUREG/CR-5432 V01 RECOMMENDATONS TO THE NRC FOR Bolt Comment COVER SYSTEMS OVER URANIUM MILL TAluNGS AND LOW-NUREG-1431 V3 DRF FC STANDARD TECHt. CAL SPECIFICATIONS LEVEL RADCACTIVE WASTES Identificahon And Ranking Of Soils WES11NGHOUSE PLANTS Bases (Sections 3 4-3 9) Drai Report Ier For Disposal F ac*tv Covers Comment NUREGICR 5432 V02. RECOMMENDATIONS TO THE NRC FOR SOIL NUREG 1432 V1 DAF 8:C. S1 ANDARD TECHNICAL SFECIFICATONS COVER SYSTLMS OVER URANIUM MILL TAtuNGS AND LOW-COMDUSTON ENGINEERING PLANTS Speckanons Drafi Report

( EVEL RADIOACTIVE WASTES Lateratory Aruf Field Testo For Son For Comme.nt Covers NUHEG.1432 V2 DRF FC-STANDARD TECHNCAL SPECIFICATONS NUREGiCR 6432 V03 RECOMMENDATIONS TO THE f4RC FOR SOIL COMBUSTON ENGINEERING PLAN TS caws (Sections 20 COVER SYSTEMS OVER URANIUM MILL TAIUNGS AND LOW-3 3) Draft Roport for Comment LEVEL RADIOACTIVE WASTES Construction Mathods And Guk1ance NUREG-1432 V3 DAF FC: STANDARD TECHNICAL SPECIFCATONS For Seakng Penetrations in Soi1 Covers.

- COMBUSTION ENGINE E RING PLANTS Bases @ectona 34 3 9) Deafi Report For Comment.

Vendor inspection NUREG-1433 V1 DAF FC: STANDARD TECHN' CAL SPECIFICATONS NUREG-0040 V14 N04 UCENSEE CONTRACTOR AND VENDOR IN-GENERAL ELECTRC UNITS, DWR/4 Speckatons Drett Report For SPECliON ST ATUS REPORT. Quartery Report Octoter December Commant 1990 (White Boolt)

NUREG 1433 V2 DAF FC. STANDARD TECHN1 cat SPECIFICATIONS GENERAL ELECTRC UNITS, BWR/4 Bason (Sections 2 0 3 3bDraft Venting Repor1 F or Comment NUREG rCR4554 CONTAINMENT VENTING ANALYSIS FOR THE NUREG 1433 V3 DRF f C: STANDARD TECHNCAL SPECIFICATONS SHOREHAM NUCLEAR POWER STATION GENER AL ELECTRIC UNITS. BWR/4 Basca (Sectons 3 4 310) Draft Report For Comment Waste Pactiege NURLG 1434 VI DRF FC ST ANDARD TECHNCAL SPECWICA10NS NUREG/CR4639 UNCERTAINTY EVALUATON METHODS FOR GENERAL ELECTRC PLANTS, BWR/6 Speck.ations Draft Report For WASTE PACAAGE PERFORMANCE ASSESSMENT.

Comment NUREG-1434 V2 DAF FC; STANDARD TECHNCAL SPLCIFCATONS Water Pool GENERAL ELECTRIC PLANTS. BW/0 Bases (Sections 20 -

NUREG /CR-3916 PRESSUMED MELT EJECTION INTO WATER 3 3) Oraft Report For Comme; t POOLS r

___u_.___-__,___.._.___,_---,_

l Subject Index 25 w doe cat. veive w..taghov..

NUREG 1431 VI DRF f C ST ANDARD TECHNICAL SPICIF CAllONS NuhEG/CR 8Afs8 GlNtiliC 155Uf b7. I ll UlR L WlDGE GATE M S11NGHNSE PLAN 1s Stax* atoet (wan Herod F & Co'nnent V ALVE f f ST PR(Xs0AM Phase il Hesuttu A<ri Ar.ein's NUREG-1431 vt DAF F C $1 ANDAHD 1[ CHNICAL SPE Cif 0ATIONS WESTINGHOUSE PLANTS l'wes L5m ton 6 2 0 3 3) r>aN Apport f tw Wolded Tuff Comnent NUHlGICfl 4M ttDND $1HING1H Or Of MI NilTOJS (son [ Holt ygnt G.143t V3 DRf f C 51 ANDAMD 1FCHNICAL SPECilICATIONS PLUGS IN WE L DE D TUf F WESTINGHOU$l PLAN 1S Dant +s (Sections 3 4-3 9) Diaft Regert f or Comnent i

it j

NRC Originating Organization Index (Staff Reports)

This index lists thoso NRC organizations that have published staff reports. The index is ar-ranged alphabetically by ma;or NRC organizations (e.g., program officos) and then by sub-sections of these (e.g., divis ons, branchos) whero appropriato. Each entry is followed by a NUREG number and titto of the report (s). If further information is noodod, refer to the main citation by NtIREG number.

OFFICL OF EEtCUTlvt DIRECTOH FOR OPERATlONS (f DO)

LDO OFFICI OF NUCLt AR RtOULAfORY Rt St ARCH (POST 820406)

OF F ici of NUct t AH HI GU. AluHY HE SF AHUH IPOS 1 %0720)

OF C OF LNi OHCl Mt NT (POST 8104131 i4UH[ G/CP 003 7 PRLK:.t i DINGS 06 T HE 51 M)N AH ON AbSE SS NUht 0-0940 V09 N04 [NF OHCLME N1 ACTIOt4S SIGNtf IC AN1 AC-ME NT OF F HACTURL PHI DICTION f f CHNOLOGY. PihNG AND TONS htSOLVED Ouarwly Prtvets Detot Cxtuter-Decembo, IHf %URL VLSSE IS 1999 DIVIssON Of fil GUL ATOHY APPtlCAtl&NS (ICS1870413l NUhp33 W A PHORWA10N OF MNLR0 SAW EDO. OFFICE OF ADMlHISTRATION (PHE 470413 & POST 890205)

I UE DIVISON OF F RL E DOM OF INF OHMATlON & PUBLICAllONS SLHV-g g

^

^

NU [G 04 VI N4 htGULATORY AND 11CHNCAL hif0 HTS D

O 1

Ar i

( ADSTFIACI INDlx JOURNAL) Annual Compilabon Ior 1990 NURLG 11SO VU3 St Vi ht. A(; Cit)t N1 FilSK$ AN ASSI SSMt NT NOREG OS40 V12 N11 TITLC LIST OF DOCUMLNf 5 MADE PUBLIC i OR f IVL U S NUClLAH POWE 4 PLANIS AM ordces D And LY AV AllADL E. Novemtser 1,30.19W t iinal Report t4UCEO OS40 V12 Nt2 flit E LIS1 OF DOCUMENTS MADf PUDLIC-PRODAIMLISilC HISK ANALYSIS ORANCH LY AVULAbit Decemter 1 31, 1990 NUHE G/CH %39 UNCE H1 AINTY E V AL U A flON MLTHODS fOR NURE G.0S40 V13 N01 TITLE LIST OF DOCUMF tils MADE PUDLIC-W A$tt PACKAGC Pt hf 0HMANCE AbSt SSMLN1.

LY AVAILABLE Janusry t 31,1991 100. OFFICE OF NUCLE AR Rt ACTOR REOULATION (POST 4/20/90)

NURIGA7SO V32 NOS NUCLE AR HCGULATORY COMMISSION 15 PHW' HAM MAN A3E ML N1 POLICY ULVILOPMLN1 & ANAt YSIS SU. NCES f OR NOVlMBER ikie0 Pages 333 393 NUHtG-01SO V32 N00 NUCtt AR RE GULA10HY COMMISSION is-gg$k^h[Shero }tusOF SAF E T Y ISSUES Al llCE NSID g

GUANCE S FOR DLCC MBL R 1990 F aps 395 496 p ",

"]*"

p i 5 870411)

NURf G-0750 V33 N01 NUCLE AR REGULATOHY COUMISSION IS 9

SUANCES F OH JANUAHY 1991. Pages 140 NUHf G1232 V03 S')2. SAF L TV IVALUAflON NfICAT ON fin NURE G 0936 V09 f404 t4HC RE GULATORY AG[ NDA Quano"Y NESSE E VAltiY AUTHORITY, DHOWtes Ft HRY NUCLEAR Pt H-Huport.CktateDocemt,ar 1930 F OHMANCE PL AN Brownn F erry Uret 2 Rastart NUHI G 1362 SAFL TY [VALUAllON ht' PORT R[ LAlf D TO THE EDO OFFICE OF THE CONTROLLER (PRE B20414 & POST 990205)

F ULL.li RM opt RATING tICLNSE F OH OYSIE R CHEL K NUClF-DIVlslON OF HUDGtT & ANALYSIS #POSi 890205)

AR GE NE RATING ST AllON Docket No SO 210 (General PutAc Uhh NUHf G-1100 V07 DUDGET ESTIMATES Fiscal Years 1992-1991 tes Nuclear Corn et af)

DIVI 5 ION OF Ort HATIONAL tVLNTS A%rSsMi NT (POST 610411)

EDO.OHICE FOR ANALYSIS 4 EMLUATION OF OPERATIONAL yJnt G 1430 VI DnF F G ST ANDAHD 1LCHNCAL SPIClf ICAIK)NS BABCOCK AND WILCOK PLAN 15 Stelt ations Draft Hopori F or DATA OFFICS FOR ANALYSIS & CVALUAllON OF OPCMTIONAL DAT A, Di congneng NUHtG 1430 V2 DHF iC ST ANDARD TECHNCAL SPlCIFICAT60NS RECTOR NURt G 0000 V13 NO3 REPORT TO CONGHESS ON ABNOHMAL DADCOCK AND WILCOK PL ANTS. Danos 6ecticos 2 0 3 3)Dratt Hopori i or Comnent OCCUR 30NCE S July September 1990 NUHf G 1430 V3 DHF F C ST ANDARD TlCHNICAL SPE Cl))CAllONS NURLG-0090 V13 Nod REPOR1 TO CONGRESS ON ADNORMAL D ADCOCK AND WILCOX i t. ANIS Dam (S4xhons 3 4 3 9, D'att OCCURHENGLS Octot>er-Decemter 1990 Hepir1 F or Comment NUREG 1275 vue OPE HATING EWLRiLNCE FEEDDACK I f PORT.

NURt. G 1431 vt DRF I G ST ANDAHD TECHNICAL SP[CIFICAllONS

' Ot ENOID. OPERATED V ALVE PHOBLt MS Comecent Power no WESTINGHOUSL PLANTS Spuaft.shons Draft Peport f or Com.

r ment NUHF G 1431 V2 DAF FC St ANDARD TE CHNCAL SPECIFICAllONS 3-4 NUCLE AR MATERIAL SAFETY & SAFEOllARDS WE SilNGHOUSE PLANTS Baws (srchons 2 0-3 3) Dra't Acpy1 f or O

1. NUCLEAR MATT 31AL SAFETY & SAf f GUARDS NU y G-0430 V10 LCfW D FUE L F ACitlTY STATUS J1 V3 DHF F C. ST ANDARD TL CHNCAL SPLCif ICAllONS Rt RT inventory Ditterence Ld4 July 1989 June 1990 (Gray ESTINGHOUSE PLANTS Daset (Sect.ons 3 4-3 9) Dra't Hepor1 F or DIVIStON OF SAF EN'RDS & TRANSDORT ATION (POST 870413) g"C 3? VI DHF f C ST ANDARD TECHNICAL SPLC6FICATIONS y

NUREG 0725 H0c PUBLIC INFORMATION CIRCULAR FOR SH;P.

COMDUST60N ENGINhERING PLANTS Lpockahons Drati Reprat MENT S OF IRRADIATE D HEACTOR FULL I

DIVISION OF LOW LFVEL WASTE MANAGEMLNT & DLCOMM!SSION-g[q'

[V2 DAF FC. ST ANDARD TECHNICAL SPLCIFICAflONS

):

NLF

9) R 2 1 ANDARD FORMAT AND CONIENT OF A LI-t 3

p CE NSC APPtlCAf 50N FOR A LOW t,tVE L RAD'OACTIVE WsSTE NUHEG 1432 V3 DHF I C SI ANDAHD 1[CHNCAL SF-(Cli CA1CNS DISPOSAL F ACitif Y.

COMBUSTION E NGINEERING pt ANTS Daws (Sectr;ns 34 NUREG-1200 R02 ST ANDAHO HEVILW PLAN FOH THE HEvilW OF 3 H Drah Ret For Comment A llCCNSE APPLtCATON IOR A LOW LEVEL R ADIOACTIVE NUR001433 VI DAF F G ST ANDARD TLCHNCAL SPLC1llCATIONS W ASTE DISPOSAL F#CillfY GfNERAL E LICihC UNITS DWR/4 Specihcahona Draft Hogort v or Comment U.S. NUCLE AR REOULATOR f COMMISSaON NUHLG1433 V2 DRF f C-SI ANDARD llCHNCAL SPE0lf CATIONS OF F CL OF THE GENLf4AL COUNSEL (POST fG701)

GLNtHAL ELE C1 DC UNITS DWR/4 Bucs (sect *>ns 20 NURLO 03% 005 R09 UN!TED ST ATES NUCLEAR HEGULATORY 3 3) Drah hePon rnr Comment COMMISSION ST AU PRACitCC AND PROCEDURE NUHLG 913 V3 DRF F G ST ANDARD TLCHNCAL SPE CIFCATIONS OlGEST Commwwon Arpeal Daard And Licen&ng Board GE NE RAL EL EGIRIC LM15. DWR/4 Daw {%chans 34 thons July 1972 September 19fe0 310) Dra t HMot for Comment

-l r

l

)

27

28 NRC Originating Organization index (Staff Reports)

NUREG 1434 V1 DRF FC STANDARD TECHNICAL SPECarlCAT!ONS DM$ ION OF nEACTOR IN5PECTION & $AF L GUARDS i OST P

GENERAL ELECTRIO PLANTS, BWR/6 Specitt.atont Draft Rup rt 670411)

For Cornment NUREMK>40 vid 404 LICEN5f E CON 1RACTOR AND VENDOH IN NU'1EG 1434 V2 f46 FC STANDARD TECHNICAL SPEC 4 iCATIONS SPEC 140N ST A1U9 RE POHT. Quartony Swsurt Octcur Dec emtver NN G SE$5 MENT Of DE$1GN CON 1ROL PRACTICES

3) e Re Frs,

nt NUREG 1434 V3 DRf I'C ST ANDARD TECHNICAL SPEClflCATIONS AND DEdiGN RECONSTITUTION PROGRAMS IN THE NUCLEAR pjyi$$r INeb PERFORMANCE & QUALITY EVALUATION GENERAL ELECTRIC PLANTS, DWR/6 0aws (sectons 34 310) Desh Report For Comment (POST e70419 NUREG 1714 R07 HISTORICAL DAT A

SUMMARY

Or THE SYSTEM.

A1.C A$$ESEMENT Cr LICEN5E E PERF OHMANCE I

NRC Originating Organization Index (International Agreements)

This index lists those NRC organizations that have published international a0reement ro.

ports. The index is arranged arphabetically by major NRC organizations (e.g., program of-ficos) and then by subsections of those (e.g., divisions, branches) where appropriato. Each entry is followed by a NUREG number and title of the report (s).1f further information is needed, refer to the rnain citation by NUREG number, u m., or, nauncc n A,,v.m to, m, au.,im.

29

l t

I J

I l

1

NRC Contract Sponsor Index (Contractor Reports)

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

(DO. Of flCE f 04 ANALY$ll & IV ALV Af TON Of OPI R ATION AL NUHE G'CH %72 VOI CHAHACit HtSilCS Of (OW ti vil HADfD AC1 tVi W AS10 Dentammation Wasic Annual floPv1 I of I w el DATA Of f ICL F OH ANAL YLIS & f y ALL AllON Of Ol'l fiAflONAL DAT A Db har 190 hlCTOH Divi $lON Of hlGUL ATOHY API LICAtlONS (PONT B7041:H NUhl G/CH NXi VD9412 LICE NSf L (VENT hlPOhi (L[ fH NUHt G/CH 4444 HADIAtloN SAF L1Y ISSUCS HI LAf f D 10 HA LOfAPil A160N f or Manth Of (w emt>ce ime0 DIOL Abt Li D AN11HODIE B NUNI G/CH PPO V10 N1 ILL N51 i L VIN 1 hlPOHI (LI IH NUhl G/GH t,tD DOSl H[ DUCT 604 ll CHNIOUl % IDo HIGH-COMf'll A1 ION F or Month Of Juqury 199t DOM Wohns R GHOUPS IN NUct t AH POWt H PL ANTS WUht G/CH L343 HAinONUCllD( CHAHACil Hl/ alton Or HL AC-tDO Of FtCE OF NUCLE All Malt HIAL SAFtTY & $Af f 0VAND$

TOH Of GOMMISSIONING W ASIE AND SP! NT FUt L AS5( MittY DIVISION of HIGH tl VI L W A51L MANAnt Mf NT (Post e70413)

HAHDW Ahl Pturess flerwet NUHf G/CH Wl9 UNPI H T AIN T Y E V AL U A f ION METHODS IOH NUNI G/CH %M A SYbil MATIC APP 40ACH IO hl PI tillVt i All WA$f t PACK AGE "Iht OhMANCE A%E55MI NT UHL %

DIVl510N Of LOW ll Vf L WASIL MANAGI MI NT & DL COMMi% TON NUHL G/CR ',febit PROGHAMMAllC H001 CAU5l ANAliSIS Of MA NAN h ONNt i Pt Hf OhMANCE PHOOtt MS N

/05 54 12 1 HI COMMI NDA1 IONS TO THE NHC I Oh

^

SOlt COV[H SYBit MS OVE f4 UHANIUM MILL 1 AILINGS AND LOW LtVI L HADIOACTIVL WASit 5 locntifu ation Amt Hanbry Of D' VISION OF SAF i TY 1%UL hl LOL UTION (DOST 0h0717)

~

4f f(fIM)t NDAtlONS TO 1HE NHC IOH NL l CR I

ghg g fj g

SOIL COVt H $YSitMS OVin UHANtUM Milt 1 AtLINGS AND g g i"W [f VLL HADIOAC11VL WAS Tl S Latuabry And f wild Tests NURt G'CH M'e t x1HAN A COMPUll H CODL 'OH E SilMAflNG CONCI N1H AllON5 Of 1011C SUDST ANE L S Al CONTHOL NL L /

$ 2 V03 R(COMME NDAllONS TO THE NHC f 0H SOIL COVi h SY$1tMS OVf H UNANtUM MILL 1 AILINGS AND NU IG C ?

I P 2 A CODr i 04 I OLLOWING AthDDHNI-LOW LEVI L HADIOACitVE WASTLS Constructen (4tNds And I @ON PHODUCT$ IN (af N( HIC NUCLfAH PLAN 1 ILOW GManta f or Scaling Punciratons in had Covers NUH[a/CH MM A bliI.10 ACHING CUHRICULUV F OH THl NHC/

D'VI i l S% bil MS Hf Li ARCH (POS1 fth071h SNL LOW L EVEL W AS't PlHf 0HMANCE AS$[ 55MLNT ML 1H qgg'EG/CH 3916 Phl 550 Hill D MEll EJLCilON INTO W ATL n ODO, t OG Y.

pgg g NUh! G/CH S2fl2 L %11M ATION Of CON T AINMI N T Phl5%UHI E DO OFFICL OF NUCLE AR HLOULATORY HEST ARCH ' POST 820406) iMDING DUf 10 DlHIC1 CONT AfNMI N1 Hi ATING f OH THl DIViblON OF L NGINt LHING g4051 B7041W NUHIG/CH 3145 VD9 GEOPHYSICAL INVESilGAllONS OF THE DON PL ANT NUHf G'CR fi3 J A THE RMODiNAMIC HDDL L Of f Ut L DiSRUP.

WE STi HN OHIO INDIANA HiGION Annue1 Honort Cktater t 9ft9 IlON IN SI'1 Neptamtet 1999 NUHLG/CH4235 bilLC160N Of SILICEOUS AGGhEGAl[ fOR NUHl G/CR t331 MILCOH ANALYSE S IOR ACCIDf N1 PHOGRES-SiON ISSUE S CONcHLT L NUHf G/CR-4?b9 MODEtS Of 1HANSPOHT PHOCl SSE S IN CON.

NUHLG/CH 5377 HEVlf W Of THE CHHONIC DPOSUHE P ATH-W AY MOpt LS IN MACCS AND SE VI HAL OTH[H WELL kNJWN CAETE NUHLG/CR 4295 DOND StHE NG1H Of CEVENTITIOUS DOH[.

PHOHABILISTIC RISK AS5L 55ME Ni MODELS NURL G/CH $481 DAT A SUMM Ahv HL 50HT I OH I t$SION PROD-HOLE Pt.UGS IN Wt LDED TUf f NUHf G/CH do?O H AulONUCllDt DISTHthullONS AND MiGH A UCT RE LL Ast 1EST VI-4 NUhtG/CH %tB OVALITY ASSURANCL PROCEDUHis 5 001HL NON MLCHANISMS AT SHALLOW L AND BUH!AL SITES finat CONI AIN SEVEHE Hf ACTOR ACCfDLNT COMPuif H CODE Hoport Of PNL Hescarch Investgat< ms On The D+stntiuten. Mg'a tion. Ard Contamment Of Ha$onuclides Al Many riats. tente y NUHE G'CH4$2$ HYDHOGEN AIR DlLUt NT DETONATION STUDY NUHt G.CR~4867. HE L AY TE S1 PHOGR AM Scoes ! Vitaation 1esta FOR NUCLLAH HC ACTOR SAF(TY ANAtt Sf S NUHEG/CR $4% CONCE PTUAlt2 ATION Of A HYPUTHE f tCAL NUHf G/CH-%31 M( LCOH 1 H O A COMPult H CODE rOH NUCL L-HIGH Lt V1 L NUCLt AH W AST E MOCSIT OHY S11 E IN AH Rt ACTOH SLVLHE ACC DENT SOUHCL TE HM AND H!5K AS-UNSATUHATEDIHACTUHf D TUf F.

SE SSMEN1 ANALYSIS NURI G/CH 5536 DCM3D A DUAL CONTINUUM THHI E DtME N NUHLG/Ch 6M4 CONT AINML f.T VE NTING AN ALYSIS F OR 1Hf SiON AL GHOUND W ATE R FLOW CODF FOH UNSATUHAftD, 5HOHE HAM NUCLE AH POWLR STATION FR ACiUHE D. POHOUS ME DIA NUH[G/CH %M. INE L PE RSON AL COMPUT L R VE RSION OF NUHEG/CR S%5 AGING AS5[ SSME NT OF THE WE STINGHOUhl M ACCS 15 PWR CONTROL 400 DRIVE SYSTf M NURC G/CH b%6 GENLRiC ISSUE BT. FLt Xibt E WF DGL GATL EDO OFFICE OF NUCLLAf4 RE ACTOR REGULATION (POST 4/2a/60)

VALVE TEST PHOGHAM Phase it Heeutta And Analysis PHOGHAu MANAGE Mt.NT. IOLICY DE VL L OPHL N T & ANALY515 Nont.G/CH M77. E mit NSION AND

t. m THAPOL AT ION OF 4H STAF F (POST 87041 TJ CUHVLS AND THE IR APPLICATlON TO ML LOW UPPE R SHE Lf' NUREGICH 4911 INCENTIVE REGULATION Of NUCLE AR POWE R TOUGHNL SS ISSUL PL ANi$ BY ST ATL Rt gut A TORS NUhEG / CH-M81 UNSATUR AT ED FLOW AND TRANSPOH1 DivtSION Of OPE RAtlONAL t VENi$ ASSE SSMt NT (POST 0704 t N THnOUGH IHACTURED HOCK PtLAf t D TO HIGH4E VEL W ASTE NUHLG/CH 5285 CLOSIOUT OF 10 DULLt11N 7913 CRACKING IN HE POSl10 HIE S f anal Hetwn - Pbese lit i Li DW Alf R SySTIM PIPING NUHtG/CR %16 U5f ftS M ANU AL F OR THE NE f1H AN tt COM NURIG/CH5?M CLOSF1UT Of if BULLt'1tN 00 06 CNGtNit RE D Pulf H CODE S AT ETY f f ATUhl (E S+ a itE SE T CON f RN NUHLG/CH 5619 THE IMPACT OF THE RM AL AGING ON THE Nunt G/CH4300 CLOSE OUT Of IE HUL L E ti.' B3 o? APPARENTLY FLAMMADILITY CV LLEC1HtC CADLES f RAUDULINI PHODUC15 SOLD BY HAY M3LLLHING 31

32 NRC Contract Sponsor index oivisou or nxo.AtoN enoTtcToN a iutnattcy ent rAnco-NLES(DOST 870411)

NUhl G/GR 4757. L.INE.405$ Dell hMIN ATON f 00 Al4 EAVPt.l.h Sv $i C MS

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

APPLit D PH YSICS, lHC.

t O&O 10AHO, INC. (SUBS. OF iC&Q, INCJ NUlilG/CH %:e6 (OM:ID A DUAL CONTINUUM.1HHL I OMI NMON-NUH(G/CH M29 AN ASSES %MLNT OF l1WH MAHK Di CONT AIN AL GHOUND W All H I t.OW CODI I OH UNSATURAll D. I H AC-Mt NT CHAttt NGi S, F AttUHL MODES, AND POf t Nil AL IMPHOVL-T UHL D. POHOUS Mt D1 A Ml NIS IN Pt HrOHMAU;f NUht G'GH %56 G[ Ni nlC ISSUt fl? F t L *1tu t WlbGL GAf[

ARl2ON A UNIV. OF.1UCSON, AZ VALVE il 51 PHOGHAM f%ste H flotul4 And Aaniytet NUHE G/CH 4?95 (104D PHLt4GTH OF ClMLN1110VS lOHE HOLE NUHi G/CH M S4 CONI AINME NI VI N11NG ANALYSIS f OR TH[

PL UGS IN WE LD[ D TUF l SHOHE HAM NUCtl AH POWlH STATON NUHlG/ Cit %M1 UNSATUHA1('D F LOW AND T R ANbi'OH f NUHEG/CH %67 tNil PE HSONAL COMPUTEH ViliSON OF MACCS THHOUGH F HACIUniD HDCK Ht t (TLD 10 HIGH LLVf L WASit 16 fit POS110 Hit S f ina! Heport Pt.ase til NUHL G/CH htJ2 V01 CHAHACitHISilCS Or LOW LE VLL HADIDAC.

Trvt W AS1f (Wontanunaton Wante Annua! Heport F w f at e! Year ARMf, DE PT, OF, ARMY INGINit R WATERW AYS EXPE RIMt NT 1999 ST AllON NUHf G/CH S432 V01 HECOMMLNDAtlONS TO THE NHC f OH SOlt OR AM.1NC, COVE A SYS1t MS OVE H HHANIUM MllL 1 AllINGS AND LOW.

NURL G/CH M36 IX M3D A DUAL-CONilNOUM THHII DIME NSION LEVIL HADIOACllVE WASTE S IdentAtation Ard Hanmg Of Swig AL GHOUND W Alf H f LOW COUL f OH UNSATUHATE D, F RAC-I a (kwoonalI aciliff Cove's TUHf D POHOUS MtDiA NUH( G/Cil $41? V07 HE COMME NDAtlONS 10 THE NHC F OH SOtt COVt H SYSit MS OVt H UHANIUM Mit L 1 AllINGS AND log H ARY ARD $CHOOL OF PUBLIC Hi ALTH, DOSTON, MA Lt VI L HADIDAClivE WA4T[5 tatoatory And Fw.id Tests F or Sal NUHf G/CP 0110 VOI PHOCl[ DINGS Of 1HI 21ST COL /NHC NU-CLt AR Al4 CLI ANING CONF [HlNCE !*tsons 1 - (4 Held in San Cowws NUNIG/CH f.437 V03 HiCOMMlNOA10NS TO THE NHC f On SOlt twp, Caha Aupt 1316. IDW COvt R SYSTCMS OvlH UMANIUM MILL 1 AILINGS AND LCV-NUhl G/CP 0116 V02 PHOCi tDINGS OF THE 21ST DOf /NHC NU-LLVil HADIOACTIVL W ASitS Construt ton MotNvju Ard Gudarg, et_L AH AlH CL t AHING CONF E HENCE bl SSIONS 9 15 Held in San F or Scalino Punettanons in Sul Coworn Dego, CaI6'wa, August 111tt 1990 hATit LLE HUMAN AFF Alf48 RLfitAf4CH CE NTERS INSTITUTT FOR ENtRQlit KNIKK F O LG/CH4911. INCINHVL HIGULAllON Of NUCll AFI POWt h NURIG/CH S3/F FttvitW OF THE CHHONIC IxfUSUHE PATHW AY PL* N1

• frv ST ATE Rt GUL A10HS MODLLS IN MACCS AND Srvt HAL OTHL H Wttl ANOWN PHOB-ARILISTIC HISK ASSL SSME NT MODELS B ATTE LLE.MORIAL INSTITUTE, P ACIFIC NORTHWE ST 6 ABOR AT ORY INTERA TECHNOLO0tts, t.

NUHIG/CH 4670 HAD40NUCLlDL DISTHiBUTIONS AND mig 4ATION NUHLG/CH %39 A SitF 1E ACHING CUHHICULUM f 04 THE NHC/

ME CHAN!$MS AT SHALLOW L AND DU4IAL SITES hnal Hepoet Of SNL LOW (IVEL WAS1t Pt HF OHM ANCE ASSI SSML Ni METHOD PNL Hotearch inventegatone On 1ho Cnatbuton, M,g'aton, And Con OLOW iminrnent Of fia&onuci.@t At Masey F late. Acntucky NuhlG/CH 4767. LINE-LOSS DL if hMINAtlON F OR Alh SAMPLt H KORt A ATOMIC ENE RGY RESE AHCH INSTITU1 NUME G/CH $?B2 E.SilMAllON OF CONT AINMt Ni PHf SSURE LOAD-Si Si t M3 NUHE G/CH S343 UADIONUCllDL CHAHAC1t hl7ATION Of ht AC.

ING DUE TO DlHE CT CONT AINMLNT IE Ai'NG $ O4 THL 7 ION 10h DE COMMISSIONidG W AST[ AND SPINT F UEL ASSEMBLY PL AN T.

HARDWARE Pfoyeen Hoport NUHE d / CHM % iXTHAN A COMPUTf H CODE FOR t SilMATING KTECH CORP.

CONCE N1HA10NS OF TOxlC Suus1 ANCtS AT CONTHOL ftOOM NuntG/CH 3916 PHESSUHl7FD MI L1 lat CIR N INTO WATLH AIR 'NT AK[ S POOLS NUHL G/CH %% f PF P ? A CODL l'OH F OLLOWING AlRHOHNt' FIS.

SiON PHODUC15 IN GI NLHIC NUCLL AH PL ANT I LOW PAT HS MAROROVE CONEULTING, LTD.

NUHtG/CH $262 L SilMA10N Or CONT AINME NT ppt SSURE LOAD-BROOKHAVEN NAin 1NAL LADOR ATORY ING DUE 10 DiHECT CONT AINME NT HLAllNG FOH 1HL 7 TON NUHt G/CH 4444 HAD!ATION SAF ETY ISSUES HELATED TO HADtO-PLANY L A!tf LED ANTIDODif S NUHF G/CH Aft 67 Hf LAY TE ST PHOGRAM Nwes l Vitwaton tests MICHIG AN, UNIV, OF, ANN ARDOR, MI NUHt G/CH 5139 DOSL HLDUCTION TE CHNIQUES F OH HIGH ICSE NUHEGICH 3146 VO9 G(OPHYSICAL INVESilGATONS Or jgt WORKIH GHOUPS IN NUCLf AH POWE A PLAN 1$

WLSTLhN OHOINDIANA H0GION Annow Hoport,0(tote 1989 NunrGeCH 5282 i StiMAtlON OF CONT AINMEN1 PHESSURL l.OAD Septerntstw 11670 ING DUE TO DtHtCT CONT AINMENT HL AtlNG F OH THF llON PLANT NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FOHMERLY NURLG/CR SMS AGING ASSESSMLN1 OF THE WESTINGHOUSE N ATION AL DUHE AU OF PWH CONTHOL HOD DHlv0 SYSTEM NUREG/CH 4236 SELCCTION OF SILICEOUS AGGHLGATL FOH CONCHE1i CENitR FOR NUCLEAR W AST[ REGULATORY ANALYSES NUHF G /CH 4269 MODL~LS Or 1H ANSPORT PHOCESSLS IN CON NUME G!CH %39 UNCt HI AINTY EV ALU AT ON METHODS FOR ChtTE WASTE PACKAGE PCHf 0HMANCE ASSE S$ MENT.

OAK HIDOC NATIONAL t.ABORATORY DAVID W. TAYLOR NAVAL RECE ARCH & DEVELOPMENT CENTIR NUMEG/CH 2000 VD4N17 LICI NSI E EVENT FiEPORT (t t up NUHf G/CH %77 L X1E NSON AND E XT H APOLA TION Or JH COMPit ATION Fot Manth Ot Docemte 1990 CUHVES A'lO THLIN APPLICATON TO 1HE LOW UPPEft SHtLF Nunt G/CH P300 V10 ll1 LICL NM E EVLN1 HEPOHT (LfH) f OUG, INE Sd ISSUE COMPIL ATiON f or Month Of January 1991 33

34 Contractor Index NUREG/CR 5491 DAT A SUMM ARY REPORT FOR FISSION PRODUCT NUREG/CR $536 DCM3D A DUAL CONTINUUM, THREE DIMENblON-RELEAGE TEST Vl-4 AL. GROUNDW ATER FLOW CODE IOR UNSATURATED. f RAC-TURE D POROUS MEDIA P AR A ME TE R. INC.

NUREGeCR $$39 A SELF TE ACHING CURRICULUM FOR THE NRC/

NUREG/CR-6?M CLOSLOUT Of if. DULL ETIN 7913 CHACkiNG IN SNL LOW LEVEL W ASTE PLRrORMANEE ASSESSMENT METHOD-FEE DW ATE R SY0tE M P41NG OL OGY NUREG'CR t?fe CLOSEOUT OF IE OULLETIN B0 00 ENGINEERLD NUREG/CR-5618 USER S MANUAL F OA THE NEFTRAN 61 COMPUT-SAFETY f E ATURE (ESri RE SET CONTROt S E R CODE NUREG/CR 6309 CLOSEOUT O' !L BULLETIN 03 07 APPARENTLY NUREG/CR E619 THE IMPACT OF THERMAL. AGING ON THE FLAM.

FRAUDULENT PRODUCTS SOLD SY RAY MILLER.INC.

MABfLITY OF ELECTRIC CABLE S SANDtA NATIONAL LABORATORIES SCIENCE APPLICATIONS INTERNATIONAL CORP. (FDRMERLY NUREG/CP-0116 PROCLEDINGS OF THE CSNI WORKSHOP ON PSA SCIENCE APPLICATIONS, APPUCATIONS AND UMITATIONS NUREG/CR %96 A PROCESS FOR RISK.rOCUSED MAINTENANCE NUREG/CR 3916 PRESSURilLD MELT EJECTION INTO W ATER SON ALYSTS, tNC.

NUREG/CRM05 A SYSTEMATIC AFPROACH TO REPETITIVE F AIL-NU G/CR $317 A THERMODYNAMtC MODEL OF FUEL DISRUP-ES TION IN ST 1.

NURLG/CR 6331: MELCOR ANALYSES FOR ACCIDENT PROGRES-ST ANFORD UNIV., $1 ANFORD. CA SiON ISSUF S NURE G /CRM39 UNCERT AINTY EVALUATION METHODS FOR NUREG/CR.W5 CONCEPTUAll2ATION OF A HYPOTHEilCAL HIGH.

W ASTE PACKAGE PERFORMANCE ASSESSMENT.

LEVEL NUCLE _AR WASTE RE POSITORY SIT E.

IN UNSATURATEDJR ACTURED TUFF-U.S. N AVAL ACADE MY, ANN APOLIS. MD NUREG/CH 6518 QUALITY ASSURANCE PROCEDURES FOR THE NURE G /CR-b577. E XTE NSION AND E xT RAPOLATION OF JR CONTAIN SEVERE RE ACTOR ACCIDLNT COMPUTER CODE.

CURVES AND THLIR APPLICATION TO THE LOW UPPER SHELF NVI'EG/CR $$25 HYDROGE N-AIR-DILUENT DETONATlON STUDY TOUGHNESS ISSUE-FOR NUCl E AR RE AC10h SAF Et Y AN AL YSE S NURLG/CR $$31. MELCOR 18 0 A COMPUTE R CODE FOR NUCLEAR XYZYX INFORM ATION CORP.

RE ACTOR SEVERE ACCIDENT SOURCE TERM AND RISK ASSESS-NUREG/CH 5660 PROGRAMMATIC ROOT CAU3E AN8LYSt$ OF MENT ANALYSLS MmNTENANUE PERSONNEL PERFORMANCE PROBLEMS l

l

International Organization Index i

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

There were no NUREG!lA reports for this Quartet.

35

B

Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number, if further information is needed, refer to the main citation by the NUREG number, wrw em ir, no, et.. s,wn u e r.

wiroiza m 22 w 29s a 9xa., n-. s'exn vm t una>cn sie2

% 219 m een A a hant Jrtev NRG OB2

$0 X4 7

P m W 2, NJillG'CA L2B2 J/f,=2b t

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1. 44C F ORM 335 VS NUCet AR ALGULATORY COMMISSION

1. ht POHI NUMDt H

( Assigend.v,94HC. Add Vo!..

try j

(249)

Bupp, H and Aoaundam tJam-t#4CM i102,

• * * - "*"*i mW BIBLIOGRAPHIC OATA SHEET NUlllIG41304 (s instructions e it....t s.i Vol.16, No.1 e mot ANu suoniot J DAIL Hi POHI PVthibHt D llegulatory and Technical 1(eports (Abstract Index Journal)

Compilation for June 1991 First Quarter 1991

a. ree oR oRANT Nuuot R January-March

. tus O streHi

6. Avisausi lleference

7. FtHiOD COYLRLD enetusive Dat.s)

January-March 1991

e. ets OnMiNo OnaArnauvN - Naut ANu Avustos of Nac, pro io. omsion. cmic. v nvon. u u tu.ar neuatory corrmssion. and mening ae.ss; o contracior, provio.,,ae. and ma% ae.ss i Division of Freedom of Information and Publications Services Office of Administration U.S. Nuclear llegulatory Commission Washington, DC 20$35 9 bPONSOHING OHQAtM A flON - NAML AND ADOHL L b Of NHC. typ. " Sane as aboy.' i 11 cont' actor, provio. NHC Dmsson. Otti:. or Region, U. S. Nuci.ar Hegulatory Commissio% and rnatiing acess. )

Same as 8, above.

10. 6UI'PLLMtNi AH Y NOT L u 11 ADSTRACT (?OO woros or less)

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

13. AV AiLABiuTY ST ATEMENT

12. KEY WORDS/DESCRiPTORS (Ust words or phrases trist w!II ass st r.s.arctwo in iocating the report 1 Unlimited Sa. SECURITY CLASS!FIC ATION compilation (t his rass) abstract index Unclassified Ohns iteport)

Unclassified 16 NUMOLH Of P AGE S 16 PRICE NROFORM 335 (2-89)

a THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER l

s[OINtIN!>o NUCLEAR f,1 U TDMY OMMt:$ TON i

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l W ASHINGTON, (LC, 20WA PtRMir No 0 07 C:

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Main Citations y'

and Abstracts C

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PUBLICATIONS SVCS P

TPS-POR-NUREG P-223 W SHINGTON DC 20555 Secondary Report Number Index

,D Personal Author index 5

8 Subject index b

C' M

t:!

NRC Origincting Organization hm Index (Staff Reports) p s-

>g 5-t EPm NRC Originating Organization

~3 Index (International Anreements) no A

NRC Contractor

'e Spensor Index

{z Contractor index s

International Organization Index El r

Licensed Facility

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index j