ML20086R263

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Second Quarter 1991,April-June

ML20086R263
Person / Time
Issue date:	11/30/1991
From:	NRC OFFICE OF ADMINISTRATION (ADM)
To:
References
NUREG-0304, NUREG-0304-V16-N02, NUREG-304, NUREG-304-V16-N2, NUDOCS 9112310208
Download: ML20086R263 (46)

Text

..

NU REG-0304 I

Vol.16, No. 2 Regu:atory anc Tec:anical Re;por:s

< Abs:ract Inc ex Journa:3)

\\

Compilation for Second Quarter 1991 April - June U.S. Nuclear Regulatory Commission Office of Adntinistration

~

tr atavy

/

s i

lM A8s2 9"2 0304 R PDR

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.

Sin 0 e copies of this publication l

are available from National Technical information Service, Springfield, VA 22161

'i l

l m

NUREG-0304 Vol.16, No. 2 i

l Regulatory and Technica Reports (Abstract Index Journa )

Compilation for Second Quarter 1991 April - June lhte l'ublished: November 1991 t

llegulatory l'ublications liranch Division of Freedom of Information and Publications Services OITice of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 p = %,,

h i

l

.m.

L CONTENTS Preface...

.... v t

index Tah Main Citations and Abstracts

.1

< S'aff Reports

• Crnference Proceedings Contractor Reports International Agreement Reports Secondary Report Number index.

2 Personal Authorindex

.3 Subject lnde x...........................

4 NRC Originating Organization index (Staff Reports).

5 NRC Originating Organization Index (International Agreements).

6 NRC Contract Sponsor index (Contractor F.gorts).

.7 Contractor index,

8 International Organization index.

,.9 Licensed Facility index.

.10 f

ii

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

Technical Publications Section Regulatory Publications Branch Division of Freedom of information and Publications Services L~

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

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

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor index (Contractor Reports)

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

The bibliographic elements of the main 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 published, (6) number of pages in the report, (7) the NRC Document Control

~

System accession number, (8) the microfiche address (for internal NRC use).

- Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND 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) rep uthor, (4) organization that compiled the proceedings, (5) date report was published, (6) number o gges 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 I

REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R.

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

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

V

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

j s

NUREG 0040 V15 N01: LICENSEE CONTRACTOR AND and Licensing Board Panel, the AJministrutive Law Judges, the f

VENDOR INSPECTION STATUS REPORT. Quarterly Directors' Decisons, and the Denials of Petztens for Rutemak-Report. January-March 1991.(Whito Book)

• Dvson of Reactor ing are presented.

Inspecton & Safeguards (Post 870411) May 1991. 10$pp 9105300232. 57867:156 NUREG-0750 V33 N02: NUCLEAR REGULATORY COMMISSION This penodical covers the results of inspections performed by ISSUANCES FOR FEBRUARY 1991. Pages 613 73.

• Division the NRC's Vendor Inspection Branch that have been d6stnt fed of Freedom of Information & Pubhcations Services (Post to the inspected organizaton dunng the penod from January 890205) Apnl 1991.121pp 9105160092. 57727.282.

1991 through March 1991.

Legal issuances of the Commission, the Atomic Safety and Li-censing Appeal Panel, the Atome Safety and Licensing Board NUREG-0540 V13 NO2: TITLE LIST OF DOCUMtNTS MADE Panel. the Administrative Law Judges, and NRC Program Of-PUBLICLY AVAILABLE. February 1 28,1991.* Dwon of Free-fices are presented corn of information & Pubhcations Services (Post 890205) Apnl 1991. 336pp. 9104250053 57489113 NUREG-0750 V33 NO3: NUCLEAR REGULATORY COMMISSION This document is a muathly pubhcation containing desenp-l'SUANCES FOR MARCH 1991 Pages 175-232.

• Division of tons of information received and generated by the U.S. Nuclear Freedom of Information & Publicatons Services (Post 890205)

Regulatory Commisson (NRC). This information includes (1)

May 1991. 64pp. 9105300258. 57869-308 docketed matenal associated with Crvilian nuclear power plants See NUREG-0750,V33.N02 abstract and other uses of radioactive matenais, and (2) nondocketect matenal received and generated by NRC pertinent to its role as NUREG-0750 V33 N04: NUCLEAR REGULATORY COMMISSION a regulatory agency The tollowing indoxes are included Pet.

ISSUANCES FOR APRIL 1991.Pages 233-293

• Dmson of sonal Author, Corporate Source. Report Number, and Cross Freedom of Information & Publicatons Services (Post 890205)

Reference to Pnncipal Documents, June 1991. 69pp. 9107010138. 58250114 NUREG-0540 V13 NO3: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. March 1-31, 1991.

• Dmsion of Free-NUREG-0837 V10 N04: NRC TLD DIRECT RADIATION MONI-dom of informaton & Publications Services (Post 890205) May TORING NETWORKProgress Report October December 1990 1991. 380pp. 9105210080. 57808-012.

STRUCKMEYER,Ra MCN AMARA,N. Reg,on 1 (Post 820201)

See NUREG-0540 V13.N02 abstract.

Apot 1991 325pp. 9104290263. 57529 208.

NUREG 0540 V13 N04: TITLE LIST OF DOCUMENTS MADE This report provides the status and results of the NRC Ther.

m luminesant Dosimeter (TLD) Direct Radiaton hong PUBLICLY AVAILABLE, Apol 1-30. 1991.

• Deson of Freedom Network. It presents the radiaton levels measured in the vicinity of informaton & Publicatons Services (Post 890205) June 1991. 386pp. 9107010133. 58252:076.

of NRC licensed facihties throughout the country for the fourth See NUREG 0540,V13,N02 abstract.

quarter of 1994 NUREG-0675 S34: SAFETY EVALUATION REPORT RELATED NUREG-0847 S06: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF DIABLO CANYON NUCLEAR TO THE OPERATION OF WATTS BAR NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50 275 And 50, PLANT, UNITS 1 AND 2. Docket Nos 50-390 And 50-391 (Ten-323.(Pac

• e Gas And Electnc Company)

ROOD.H.;

nessee Valley Authonty) TAM,P.S Dmson of Reactor Projects -

CHOKSHI,N.; MCMULLEN.Ra et al Dmson of Reactor Protects 1/11. (Post 870411). Apol 1991.159pp. 9105150345. 57717.273.

- til,lV,V (Post 901216). June 1991. 354pp 9107100057.

Supolement No. 6 to the Safoty Evaluation Report for the ap-58383 001.

phcation fded by the Tennessee Valley Authonty for heense to Supplement 34 to the Safety Evaluaton Report for the apph-operate Watts Bar Nuclear Plant. Units 1 and 2 Docket Nos.

caten by Pacific Gas and Electnc Company (PG&E) for hcenses 50-390 and 50-391, located in Rhea County, Tennessee, has to operate Diablo Canyon Nuclear Power Plant, Unit Nos 1 and been prepared by the Office of Nuclear Reactor Regulation of 2 (Docket Nos. 50-275 and 50-323, respectively) has been pre.

the Nuclear Regulatory Commission. The purpose of this sup-pared by the Office of Nuclear Reactor Regulaton of the U S.

piement is to update the Safety Evaluation of (1) additional in-Nuclear Regulatory Commisson. This supplement documents forma:en submitted by the applicant since Supplement No. 5 the NRC staff review 31 the Long-Term Seismic Program con.

was issued, and (2) matters that the staff had under review I,

ducted by PG&E in response to License Condition 2.C (7) of Fa.

when Supplement No 5 was issued c y pera ng License DPR-80, the Diablo Canyon Unit 1 oper.

NUREG-0936 V10 N01: NRC REGULATORY AGENDA.Ouarterly Report. January-March 1991.

• Division of Freedom of Informa-NUREG-0750 V32102: INDEXES TO NUCLEAR REGULATORY tion & Pubhcations Services (Post 890205) Apnl1991 156pp CC,MMISSION ISSUANCES. July-December 1990.

• Dmson of 9105150343 57717 117.

Freedom of Information & Publicatons Services (Post 890205)

The NRC Regulatory Agenda is a compdation of all rules on March 1991. 75pp. 9104250060. 57488 326 which the NRC has recently completed acton or has proposed, Digests nd indexes for issuances of the Commisson, the or is considenng action and all petitons for rulemaking which Atomic Safety and Licensing Appeal Panel, the Atomic Safety have been received by the Commisson and are pending dispo-1 l

l 1

L

3 and Abstracts Main Citations w of the results of Jhe NRC statt rewefor a preh safety This report provides thecontained in ds referenceort desenbing Westinghouse Electnc Corporation The standard safety analysts rep 24,1983 proval of the SP/90 reactor d the industry it regulates in1990, with exceptions as submitted from Octoberff of the latory ana?ysis report f acts about the agency an the design of the facinty wthrough March 9,198

tors, mmercial nuclear power reac D75 through of Nuclear Reactor Regulai Based on its f ctor general, the data cover 1noted. For operating U S co apacity and average capaaty asubmitted to the mapt rt of the RESAR SP/90at there are be.

Commission. Othee d at this f

n is reviewed or this safety evaluntion repo monthty oporating reports snformahon on gerierating c gn, have not been resolve hout review, the staff concludes thcause of the TNs informatio ton s are discussed in detail throug d nt vat >dation and/or ven6ca i obtained from 16d WS ton NRC directly by the bconseoconsistency only. No indepen e For detaded and complete informa i stage of review These issuemmay is pwM in Sodon m

This to the source pubhcations.RC staff is periormed by the NRC the general use of the N mp 4 and a INSPECTOR su about tables and figures, referdigest is published annual!y for hs THE 1991,

• OF GENERIC OFFICEOctober 1990 March V03 NO2:

and is avadabb to the pubhcFINDINGS RELATEDReactor Vessel Thermat TO NUREG-1415 GENERAL Sem, annual Report NUREG-1374: TECHNICAL 79 An Evaluaton Of PVEtCooldown. P AGE f 1978, as requved, by the IG Act oal reports 149pp the May 1991

((03 2 Stress Dunng Natural Convectionissue Resoluton (Post 68071 Nuclear Regu-7)

ISSUE Inspectors General are and audit actmties of the o i amendod, to prepare semiannu March 31 and Septe ber 30.

ma les work periormed by theGenene issue 79, "Unana-Natural m

of Safety sign hcant investigatwemonth reporting penod e ear The Chairman preparesreport to R) Thermal Stress Dunn0The report evaluates the effec s mmission statt to resolve t

Chairman T s te report is submitted to the October 31, respectwely, of each yG Act, and tr

{

lar ty7ed Reactor Vessel (PW latory Co ctor vessMs (RVs). with particu n (NCC) region. A conservative inde'mments as required by the I THE RESOLU-Convection Cooldowof an NGC ovent on PWR reaclosure flange b

analysis of a B&W 177. fuel-as-RC contractor, b009*8S co OR WATER erformed by the Nevaluabon was pen REGULATORY ANALYSIS F0 ESS on the pendent confirmatory stress emphasis SITES.

n sembly RV (B&W 177) was p mechanics companson of geo-NUREG 1421: TION OF GENERIC ISSUE 13 ; MULTI-and an independent fracture

&W 17 7 and other PWR RVs, the these and a AT 9

FAILURES 34pp 9107060230. 58307:09 require all U S formed by the staff Based on BASDEKAS.D ; M AZETIS G Divisio SYSTEM that are apphcable to metnc simitanty between the BNRC staff developed hndings SYSTEM water system (ESWS) is ation (Post 880717) June 1991 ower plants donng normal oper compo-essenhal service ESWS typically supports DAT A heat en RESPONSE Office for Analy-provide coohng in nuclear pand acciden The hangora, containment spray EMERGENCY mergency JOLICOEUR.J.Rl Data. Director June 1991 80pp ton pump od coolers, ebuild NUREG 1394 Rot:

F ail-nont coohng water heat enc (ERDS) IMPt.EMENT ATIONsis & Evaluation of Operationa changers, high-pressure insec idiesel ssion has begun impie-severe Responso Data System (ERDS) to 9107010108 5tt250:183The U.S Nuclear Regulatory Commi

" The nsis in ure of the ESWS functonTNs report pres data from nuclear power plants Multi-Unit Sites =ther insighi ct mentaten of the Emergencylant. ERDS provides a dire Fadures at t/beneht anaiyses, and oof th licensee plant computers to thehas been designed to be upgrade its abihty to acquireevent of an emergency at the p tsal Service Water System hown that implementationnsk a reduction estimates, cos gained dunng this ettort have swarra real-time transfer of data from emergency which has beentevel. The NRC portion of anny reduce the badfit ru the NRC Operationc Center. The system f

recommendations wdl signiic actwated by the heensee dunng an sort and fde the data. The improvements are classified at an ALERT or higtur FROM ns Center, the NRC Region-d if requested, the States 10CFR50.109(a)(3t OF REPORTS m

EROS will receive the data strea,

COMPILATION MATERIALS ENG users will include the NRC Operatio 1

site. The currently in-SY THE 1965 suppto.

NUREG-1426 V01: SUPPORTED ENGINEEPING870413) el Othce of the affected plant, anwithin the 10- m e EPZ of thewill be used to u May IfL OF nng (Post

/

n SEARCH BRANCH. DIVISION staried Emergency Notahcation Sysreport provides the minimum gsitos. It is intende tem HISER,AL Dwision of Enginee g 3 ranch. Division oh which are SSpp.9105300222 571367.261Si ntary latory Commission's Office o ntation under the current voluthe minimum stan

- ment ERDS data. This EADS at hcensee d its podecessors dating ba for implementation of 9'neenng. of the Nuclear Reguclea t9 used for planning impleme d res

^ yam as well as for providingYSIS FOR GENER-nting the proposed EROS rute-ctors The components qn the Atomic Energy Coconcommg the integrity of SEAL 1 ORFT FC: REGULATORY ANAL PUMP COOLANT SHAUKAT,S K4 sure bounday of kght water rearesearch progr programs REACTOR Comment-i generators, and the piping.

o Reso_

P 23;'

MATCHER.D.F. Division of Safety ssu covered a broad range of tog For 489.033

, Report -

cern an thesepressure vessel (RP Apdl 1991. 77p:,p. 9104250020. 57 nmental t' i for Gener-the regulatory /backfit analys s research programs have d re." The tor Coolant Pump Seat Fa u pechon n of irradiation offects hty assurance provisions for re-and procedures for RPV and piping appbcations. ins ciuding tracture omplete a listing as pr and rtuahf4 cation, and eva tted to the NRC by the g

nd provisions for seal cochn~ dhing loss of a4 sea! coo mentation hstin formal technical reports submi reports, and is tors working on thosetopical. final and c

a report will cover several topi TO PORT RELATED ports of mulu faceled prre, in ANDARD NUCLEAR many cases AR SP/90 Docket in the case of progress reis hsted u area in c Therefo Inc.)

• Dms,on 001216), Apnl

Main Citations and Abstracts 3

major facts about the agency and the industry it regulates in This report provides the results of the NRC statt review of the general, the data cover 1975 through 1990, with exceptions Westinghouse Electnc Corporation for a preliminary design ap-noted For operahng U S. commercial nuclear power reactors.

proval of the SP/90 reactor contained in its reference safety information on generating capacity and average capacity factor analysis report The standard safety analysis report desenbing is obtained from monthly operating reports submitted to the the design of the facihty was submitted from October 24,1983 NRC directly by the hcensee. This informaton is reviewed for through March 9,1987. Stati of the U S Nuclear Regulatory consistency only. No independent vahdahon ar.d/or verification Commission Othee of Nuclear Reactor Regulation, prepared is periormed by the NRC For detailed and completo information thm safety evaluation report of the RESAR SP/90. Based on its about tables and figures, refer to the source pubhcations This review, the staff concludes that there are open issues that, be-digest is pubhshed at tually for the generat use of the NRC staff cause of the stage of the design, have not been resolved at this 6

and is available to the pubhc-stage of review These issues are d:Scussed in dotad throughout

~

this report, and a summary is prov,ded in Section 1.6 of this NUREG 1374: TECHNICAL FINDINGS RELATED TO GENERIC

• P "

ISSUE 79 An Evaluation Of PWR Reactor - Vesset Thermal Stress During Natural Convection Cooldown. PAGE,J D Division NUREG 1415 V03 NO2: OFFICE OF THE INSPECTOR of Safety lasue Resolution (Post 880717) May 1991.14Dpp GENERAL.Semiannutj Report. October 1990 March 1991.

• 9106180011,58130 241's work performed by the Nuclear Regu-Office of the inspector General (Post 890417) April 1991. 34pp.

This repbrt summanze 9107030211. 58285 00).

latory Commission staff to resolve Genenc issue 79, "Unana-Inspectors General are required, by the IG Act of 1978, as tyzed Reactor Vessel (PWR) Thermal Stress During Naturaf amended, to prepare semiannual reports which summange the Convection Cooldown (NCC), The report evaluates the ettects W

Wd dh h &

of an NCC event on PWR reactor vessels (RVs). with panicular month reporting period ends March 31 and September 30. The emphasis on the closure llenge regon. A conservative inde' te ort is submitted to the Chairman not later than Aptd 30 and pendent confirmatory stress ana!ysis of a B&W 177. fuel as-October 31, respectively, of each year. The Chairman prepares sembly RV (B&W 177) was performed by the NRC contractor, comments ac required by the IG Act, and trantimits the report to and an independent fracture mechanscs evaluation was per.

formed by the staff Based on these and a companson of geo-C0"9'*85 metnc simdanty between the B&W 177 and other PWR RVs, the NUREG 1421: REGULATORY ANALYSIS FOR THE RESOLU-N C stati rieveloped findings that are applicable to all U S TION OF GENERIC ISSUE 130. ESSENTIAL SERVICE WATER SYSTEM FAILURES AT MULTI UNIT SITES. LEUNG,V.;

NUREG 1394 ROI: EMERGENCY RESPONSE DATA SYSTEM BASDEKAS.D ; MAZETIS,G. Division of Safety issue Resolut on (ERDS) IMPLEMENTATION JOLICOEUR.J R. Othce for Anaty-(Post 880717) June 1991. 34pp 9107080230. 58307.099 sis & Evaluation of Operational Data Director. June 1991.80pp The essential service water system (ESWS) is required to 9107010108. 58250:183 provide cooling in nuclear power plants dunng normal operation The U S. Nuclear Regulatory Commission has begun imple-and accident conditions. The ESWS typically supports compo-mentation of the Emergency Response Data System (ERDS) to nent cochng water heat exchangers containment spray heat eo upgrade its abihty to acquire data from nuclear power plants in changers, high-pressure injection pump oil coolers, emergency the event of an emergency at the plant. ERDS provides a direct diesel generators, and auchary butiding ventiaten coolers. Fail-real-time transfer of data from heensee plant computers to the ure of the ESWS function could lead to severe consoquences.

NRC Operations Center. The system has been designed to be This report presents the regulatory anatysis for GI-130, "Essen-acuvated by the hcensee dunng an emergency which has been tai Service Wate System Failures at Mult-Unit Sites." The risk classified at an ALERT or higher level. The NRC portion of reduction est? mates, cost / benefit analyses. and other insights EROS will receive the data stream, sort and file the data The gained during this effort have shown that implementation of the users willinclude the NRC Operations Center, the NRC Region-recommendations will significantly red xe nsk and that these al Office of the affected plant, and it requested, the States improvements are warranted in accordance with the backfit rule, which are within the 10 mile EPZ of the site The currently in.

10CFR50109(a)(3).

stalled Emergency Notification System will be used to supple-ment EROS data This report provides the minimum guidance NUREG 1426 V01: COMPILAT50N OF REPORTS rROM RE-for implementat on of ERDS at licensee sites it is intended to SEARCH SUPPORTED BY THE MATERIALS ENGINEERING be used for planning implementation under the current voluntary BRANCH. DIVISION OF ENGINEERING 1965 1990 program as well as for providing the minimum standards for irn-HISER,AL Division of Enginnenng (Post 870413) May 1991.

piementng the proposed ERDS rule-55pp. 9105300222. 57867:261.

S'nce 1965. the Matenals Engineenng Brar ch, Division of En-f.

NUREG 1401 DRFT FC: REGULATORY ANALYM FOR GENER-gineonng, of the Nuclear Regulatory Commission's Office of Nu-IC ISSUE 23.

REACTOR COOLANT PUMP SEAL clear Regulatory Research, and its predecessors dating back to FAILURE Draft Report For Comment, SHAUKAT S.Ka the Atomic Energy Commission (AEC), has sponsored research JACKSON,J Ed THATCHER D.F. Division of Safety issue Reso-programs concerning the integnty of the pnmary system pres-lution (Post 880717) Apnl 1991. 77pp. 9104250020. 574S9 033 sure boundary of hght water reactors. The components of con-This report presents the regulatory /backht analysis for Gener-cern in these research programs have included the reactor ic issue 23 (Gi 23). " Reactor Coolant Pump Seal Failure" The pressure vessel (RPV), steam generators, and the piping These regulatory analysis includes quahty assurance provisons for re, research programs have covered a broad rango of topics, in-actor coolant pump seals, instrumentation and procedures for ciuding fracture mechanics analysis and expenmental work for monitonng seal performance, and provisens for seal cooling RPV and piping apphcahons. inspecten method development dunng off normal plant condibons involvng loss of all seal cool _

and quahficaten, and evaluaton of irradiation effects to RPV ing such as station blackout _

steeis This report provides as complete a hsting as practical of NUREG 1413: SAFETY EVALUATION REPORT RELATED TO formal technical reports submitted to the NRC by the invest ga.

THE PRELtMINARY DESIGN OF THE STANDARD NUCLEAR tors working on these research programs. This listing includes STEAM SUPPLY REFERENCE SYSTEM.RESAR SP/90 Docket topical final and progress reports, and is segmented by topic No. 50-601 (Westinghouse Electnc Corpornhon. Inc )

• Divison area in many cases a report will cover several topics (such as of Advanced Reactors & Special Projects (Post 901216) Apol in the case of progress reports of multi-faceted programs), but 1991. 398pp 9105220026. 57024160.

is listed under only one topic Therefore. in searching for reports I

l

4 Malf' Citations and Abstracts i

on a specific topc. Other related top:c areas should be checked See NUREG/CP 0114,V01 abstract also.

NUREG/CP-0114 V03: PROCEEDINGS OF THE EIGHTE ENTH NUREG-1435 V02: STATUS OF SAFETY ISSUES AT LICENSED WATER REACTOR SAFETY INFORMATION MEETING POWER PLANTS.Unrtsolved Safety fssues

• Program Man-WEISS,A J Brookhaven National Laboratory. Apol 1991.582pp agement, Pokey Development & Analysis Staff (Post 870411) 3# N

• May 1991. 234pp 9106120188. 58062.261.

As part of ongomg U.S Nuclear Regaiatory Commission See NUREG/CP-0114,V01 abstract.

(NRC) efforts to ensure the quahty and accountabehty of safety 6ssue information, a program has been established whereby an NUREG/CR 2000 V10 N2; llCENSEE EVENT REPORT ILERI annual NUREG report will be published ori the status of hcens-COMPILATION For Month Of February 1991.

• Oak Ridge Na-ee implementation and NRO venticaton of safety issues in tional Laboratory March 1991 112pp 9104220299 ORNL /

major NRC requirement areas TNs report, the second volume NSIC-200. 57450.119 of a three volume senes, addresses the status of unresolved This monthly report contains Licensee Event Report (LER) safety issues at Icensed plants The data containec' in tNS operational informaton that was processed into the LER data report are a product of the NRC's Saiety issues Management file of the Nuclear Safety information Center (NSIC) dunng the System database. wNch is maintained by the Project Manage.

one month penod identified on the cover of the document. The ment Statt in the Office of Nuclear Reactor Regulaton and by LERs, from wNch tNs information is denved, are submitted to personnel in the NRC regens This report has been prepared in the Nuclear Regulatory Commisson (NRC) by nuclear power order to provide a comprehensive description of ine implemen-plant licensees in accordance with federal regulations. Proce-tation and venfication status of all the TMI Action Plan require.

dures for LER reporting for revisions to those events occurnng ments at licensed reactors, and to make this information avail-poor to 1984 are descnbed ir NRC Regulatory Guide 1.10 and able to other interested parties, including the public A coroltary NUREG 0161, " Instructions for Preparation of Data Entry purpose of this report is for it to serve as a follow-on to Sheets for Licensee Event Reports." For those events occumng NUREG-0933, "A Pnontaaton of Genenc Safety issues," wNch on and after January 1,1964, LERs are being submitted in ac-tracks safety issues up until requirements are approved for im, cordance with the revised rule contained in Title 10 Part 50.73 positen at liconand facihties.

of the Code of Federal Regulations (10 CFR 50 73 Licensee MUREG 1435 V03: STATUS OF SAFETY ISSUES AT LICENSED Event Report System) wNch was pubhshed in the Federal Reg-POWER PLANTS Generc Safety issues.

• Program Manago-ister (Vol. 48, No.144) on July 20,1983 NUREG-1022, "LL nient Polcy Development 1 Anaiysis Staff (Post 870411) June censee Event Report System Descnption of Systems and 1991. 271pp. 9107080225. 58306.188 Guidelines for Reporting," provides supporting guidance and in-As part of ongoing U.S. Nuclear Regulatory Commisson formaton on the revised LER rule The LER summanes in this (NRC) efforts to ensure the quahty and accountability of safety report are arranged alphabetically by facility narne and then tssue Informaton, a program has been estabhshed whereby an Chronologically by event date for each facihty. Component, annual NUREG report will be pubbshed on the status of licens.

system, keyword, and component vendor indones follow the ce implemenlahon and NRC venfication of safety issues in summanes Vendors are those ident:fied by the utihty when the major NRC requirement areas This report, the third volume of a LER form is initiated, the keywords for the component, system, three-volume senos, addresses the status of genenc safety and general keyword indones are assigned by the computer issues at hcensed plants The data contained in this report are using correlation tables from the Sequence Coding and Search a product of the NRC's Safety issues Management System da.

System.

tabase, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by personnel in NUREG/CR-2000 V10 N3: LICENSEE EVENT REPORT (LER) the NRC regions. This report has been prepared in order to pro, COMPILATION For Month Of March 1991

• Oak Ridge Naton-vide a comprehensive des cnption of the implementation and al Laboratory Apnl 1991,97pp 9105170174. ORNL/NSIC-200.

venfication statas of all genenc safety assues at licensed reac.

67771:222.

tors, and to make tNs informaton available to other interested See NUREG/CR-2000N10,N02 abstract.

parties, including the pubhc. A coroPary purpose of this report is for 11 to serve as a follow on to NUREG-0933 "A Pnorittration NUREG/CR 2000 V10 N4: LICENSEE EVENT REPORT (LER) of Genonc Safety issues," which tracks safety issues up until COMPILATION.For Month Of Apnl 1991;

• Oak Ridge National requirements are approved for imposition at licensed facilities.

Laboratory. May 1991. 92pp 9106120165 ORNL/NSIC-200.

NUREG/CP-0114 V01: PROCEEDINGE OF THE EIGHTEENTH w

EN20M W2 absvact WATER REACTOR SAFETY INFORMATION MEETING WEISS.A.J. Brookhaven National Laboratory Apnl 1991.678pp NUREG/CR 3964 V02: TECHNIOUCE FOR DETERMINING 9105030130. 57622 001.

PROBABILITIES OF EVENTS AND PROCESSES AFFECTING TNs three-voume report contains 100 papers out of the 128 THE PERMRMANCF OF GEOLOGIC that were presented at the Eighteenth Water Reactor Safety in' REPOSITORIES A 'sted Approaches APOSTOLAKIS,G.

formation Meeting held at the Hohday Inn Crowne Plaza, Rock-Cahfornia, Univ. c*

4 Angeles, CA. DA AS R Raf ael Bras Con-ville, Mary and, dunng the week of October 22-24,1990 The sulting Engineers / RICE L.; et al. Sandia National Laboratones.

papers are pnnted in the order of their presentation iri each ses.

June 1991.184pp 9107010105. SAND 86-0196. $8285.035.

sion and desenbe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign The U S. Environmental Protection Agency has estabhshed a participation in the meeting included 16 different papers pre-standard for the performance of geologic repositones for the disposal of radioactive waste TNs standard is probabihstic in seted by researchers from Denmark. Egypt Germany. IAEA' taly, Japan, Norway, Taiwan, UK and USSR. The titles of the nature. but the methods for determining probabihtees of eversta g

papers and the names of the authors have been updated and still being developed Decision Theory, wNch involves Bayesian may er from those that appeared in the final program of the robabibty techniques, can serve as a framework for estimating the probabihty of occurrence of processes and events that are NUREG/CP-0114 V02: PROCEEDINGS OF THE EIGHTEENTH hkely to disrupt a geolog:c repository TNs report presents the WATER R5 ACTOR SAFETY INFORMATION MEETING mathern% cal base for such a methodology and demonstrates WEISS,A J Brookhaven National Laboratory. Apnl 1991 59500 an apphcation of it in three areas cismate change. tec'onic

)

0105150327. 57715 230 events and human intrumon l

- ---- u

Main Citations and Abstracts 5

NUREQ/CR-4219 V07 N1: HEAVY SECTION STEEL TECHNOL-

" normalized" Charpy impact energy. A correlation for the extent l.

OGY PROGRAM. Semiannual Progress Report For October of embnttlement at " saturation," to., the minimum impact l

1989 March 1990. PENNELL,W.E. Oak Ridge National Labora-energy that would be achieved for the matenal after long-term tory. March 1991. 103pp 9104220334. ORNLe TM-9593.

aging, is given in terms of a material parameter, 4, which is 57447.285.

determined from the chemical composition. The fracture tough-The Heavy Section Steet Technology (HSST) Program ts con-ness J R curve for the material is then obtained from coneta-ducted for the Nuclear Regulatory Commisson (NRC) by Oak tions between room. temperature Charpy impact energy and Ridge National Laboratory (OPNL). The program focus is on the fracture toughness parameters Fracture toughness as a func-development and vahdation of technology for the assessment oi 1on of time and temperatute of reactor service is estimated g

]

fracture prevention margins in commercial nuclear reactor pres.

from the kinetics of thermal embnttiement, wNch is determmed sure vessels. In the current reporting penod, reorgsntraton of the onginal HSST program into separate programs with empha-sis on fracture mechanics technology (HSST) and matenals erra-diation effects (HSSI) has been completed. The revised HSST tion is also defined for a given matenal specificaton, ferrrte con-program is organized in 10 Tasks. These are (1) Program Man.

tent, and temperature.

agement, (2) Fracture Methodology and Analysis, (3) Matenal NUREQ/CR 4551 V2 RIP 2: EVALUATION OF SEVERE ACCI-Charactenraton Tasks, (4) Special Technical Assistance, (5)

DENT RISKS. QUANTIFICATION OF MAJOR INPUT Crack Arrest Technology, (6) Cleavage Crack initiation (7) Clad-ding Evaluatons, (B) Pressunzed-Thermal Shock Techrvilogy, PARAMETERS Experts' Determinaton Of Containment Loads (9) Analysis Methods Validation, and (10) Fracture Evaluaton And Molten Cote Containment Interaction issues. HARPER.F.T.;

Tests. The program tasks have been structured to place em.

PAYNE,A C.; BREEDING,RA: et at Sandia Natonal Laborato-phasis on the resolution fracture issues with near term hcensing nes. April 1991. 469pp. 9105150319. SAND 86-1309. 57714.121, significance.

In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nu-NUREO/CR-4302 V02: AGING AND SERVICE WEAR OF CHECK VALVES USED IN ENGINEERED SAFETY FEATURE SYS-clear power plants in the U.S. reported in NUREG 1150, the TEMS OF NUCLEAR POWER PLANTS. Aging Assessments And Severe Accident Risk Rectucten Program (SARRP) has com-Monitonng Method Evaluatons. HAYNES,H D. Oak Ridge Na.

pleted a revised calculation of the nsk to the general public tional Laboratory. Apnl 1991. 73pp. 9104220317. ORNL-6193.

from severe accidents at five nuclear power plants: Sorry, Se-57448.278.

quoyah, Zon, Peach Bottom, and Grand Gulf. The emphasis in Check vatves are used extensively in nuclear power plant this nsk analysis was not on dete# mining a "so called" point es-safety systems and balance-of-plant systems The failures of timate of nsk. i.ather, it was to determine the distnbution of nsk, these valves have resulted in signif cant maintenance efforts and to $scover the uncertainties that account for the breadth of and, on occasion, have resulted in water hammer, overpressun-this distnbuton. Off. site nsk initiated by events, both internal to ration of low-pressure systems, and damage to flow system the power station and extemal to the power staten was as-components. These failures have largety been attnbuted to seased. Much of the important input to the logic models was severe degradaten of internal parts (e g, hinge pins, hinge generated by expert panels. This document presents the distn-arms, discs, and disc nut pens) resulting trom instability (Sutter) buttons and the ratonale supporting the distnbutions for ihe or check valve discs under normal plant operating conditions.

questions posed to the Containment loads and Molten Core Present surveillance requirements for nuclear power plant check Interaction Expert Panets.

valves have been inadequate for timely detecton and trending of such degradaten because neither the flutter nor the resulting NUREG/CR-4599 V01 N1; SHORT CRACKS IN PIPING AND wear can be detected pror to failure. Consequently, the LS' PlPING WELDS Semiannual Report, March-September 1990.

Nuclear Regulatory Commisson has had a continuing strong in-WILKOWSKI,G M.; AHMAD.J.; BRUST F.; et al Battelle Memon terest in resolving check valve problems in support of the Nu-al Instate.e. May 1991. 129pp. 9105300205 BMi-2173 clear Plant Aging Research Program Oak R.cy Natonal Labo-57867:354.

ratory has camed out an evaluation of several 1evelopmental This is the first semiannual report of the U S Nuclear Regula-and/or commercially available check valve diaginstic monitor.

ing methods, in particular, those based on met arements of tory Commission's Short Cracks in Piping and Piping Welds re-acoushc emisson, ultrasonics, and magnetic flux. In each case, search program The program began in March 1990 and will the evaluations have been focused on the capability of each ex' nd for 4 years. The intent of this program is to venty and method to provide diagnostic information useful in determining impove fracture analyses for circumferentially cracked large de check valve aging and service wear effects (degradaton), check ameter nuclear piping with crack sizes typically used in leak-valve failures, and undesirable operating modes. A descripton betore-break analyses or in-service flaw evaluations. Only quasi-of each monitonng method is provided in this report, including static loading rates are evaluated since the NRC's internattonal examples of test data acquired under controlled laboratory con-Piping integnty Research Group program is evaluating the of-ditions. In some cases, field test data acquired in situ are also fects of seismic loading rates on cracked piping systems. Addi-presented. The methods are compared, and suggested areas in tonal efforts involve investigating phenomena discovered dunng need of further development are identified.

the course of conducting the Degraded Piping program. These

^

NUREQ/CR-4513: ESTIMATION OF FRACTURE TOUGHNESS include the evaluaton of the occurrence of unstable crack OF CAST STAINLESS 6TEELS DURING THERMAL AGING IN jumps in femtic steels at LWR temperatures, and the occur.

LWR SYSTEMS. CHOPRA,0 K Argonne Natonal Laboratory _

rence of anisotropic fracture properties causing h# cal crack June 1991. 74pp. 9107010083. ANL 90/42. 58249-001.

growttt Both of these phenomena may affect the safety mar-A procedure and correlations are presented for predicting the gins imphett in leak-before-break 488) analyses. Other investi-change in fracture toughness of cast stainless steel compo-gations deal with the fracture behavior of bi-metallic welds, and nents due to thermal aging dunng service in hght water reactors improvements to crack opening area anatyses used in LBB.

(LWRs) at 280-330 C ($35-625 F). The fracture toughness J-R Since much of the work in this program was just beginning curve and Cha'py-impact energy of aged cast stainless steels dunng this hrst reporting penod and progress is limited, a com-are est! mated from known matenal informatiort Fracture tough-plete state nent of work for the whole program is provided in ness of a specific cast stainless steel is estimated from the this report extent and kinetics of thermat embntttornent The extent of ther.

mal embnttiement is charactenzed by the room-temperature L

I

l 6

Main Citations and Abstracts I

WUREG/CR 4666: CLOSEOUT OF IE BULLETIN 84-02. FAIL-weld metal at low stress intensity associated w:th crack growth URES OF GENERAL ELECTRIC TYPE HFA RELAYS IN USE in the inconel,182 weld metat Irradiated stainless steels from IN CLASS 1E SAFETY SYSTEMS. FOLEY,W,J ; DEAN.R S ;

absorber-rod tubes, control-rod cladding, and flux thimbles of HENNICK A.

PARAMETER.

Inc.

January 1991. 54pp several BWRs and PWRs were obtained to investigate the 9104300323. PARAMETER IE163. 57557.129.

nature and extent of radiation-induced segregation in the steels Documentation is provided in this report to close IE BuHetin and correlate it with susceptibility to intergranula failure in the 84-02 regarding the fadure of General Electne Type HFA relays matenals. Specimens have been prepared for Auger electroa in Class 1E safety systems. The relay failures were due to aging spectroscopy analyses of segregation of alloying elements on of cost wire insulaten and nylon or Lexan spools under certain intergranular fracture suriaces.

environmental conditions. The bulletin was issued to nuclear power reactor licensees and holders of constructen permits to NUREG/CR 4667 V11: ENVIRONMENTALLY ASSISTED CRACK.

provide assurance that the manufacturer's recommendations for ING IN LIGHT WATER REACTORS Semiannual Report,Apni-correctwo actions would be implemented. The bullet,n required September 1990 CHUNG,H.M., KASSNER,T.F.; SHACK,W J ;

four specific actons, plus a review of the general concerns of et al. Argonne National Laboratory. May 1991, 37pp.

tne bulletin even though some f acilities had ddferent relays from 9105300212. ANL 91/9 57867;316 those of bulletin concern. tvaluation of utility responses, NRC/

This report summanzes work performed by Argonne National Region inspection reports, and regional telephone calls has re-Laboratory on environmentally asststed cracking in light water suited in bulletin closoout of 116 (98%) of the lid facilities to reactors dunng the 6 months from April 1990 to September which the bulletin was issued for action. Facilities which were 1990. Crack-growth rate (CGR) tests were performed on a com-shut down or had construction halted indefinitely or permanentty posite A533-Gr B/inconel 182 specimen in which a stress cor-when the report was issued are not included in this review. A rosion crack in the inconel-182 weld metal penetratad and grew follow-up item is proposed in Appendix C for tne two facilities into the A533 Gr B steel. CGR tests were also coriducted on eth open status Background information is supplied in the in-conventonal (nonplated) and Ni-or Au-plated A533 Gr B spect-troduction and Appendix A.

mens. CGR data on the A533-Gr B specimens were compared NUREG/CR 4667 V09: ENVIRONMENTALLY ASSISTED CRACK-with the fatigue crack reference curves in the ASME Boder and ING IN LIGHT WATER REACTORS. Semiannual Raport, April-Pressure Vessel Code, Secton X!, Appendix A. High-and com-September 1989. KASSNER,T.F.; PARK,1Y.; RUTHER,W E.; et mercial-punty, HP and CP, respectively, specimens of Type 304 al.

Argonne Natona! Laboratory. March 1991. 30pp.

SS from BWR absorber rod tubes, irradiated dunng service to 9104220214. ANL 90/48. 57450:263.

fluence k veis of 6x10(20) 2x10(21) n cm(-2) (E 1 MeV) in two This report summarizes work performed by Argonne Natonal reactors, were examined by Auger electron spectroscopy to Laboratory on environmenta!!y assisted cracking in light water charactenze irradiaton-induced grain boundary segregation and reactors during the stx months from Apnl 1989 to September depletion of alloying and impunty elements, which have been 1989. Topics that were investigated include (It stress corrosion associated with irradiation-assisted stress corrosion cracking of cracking (SCC) of A533-Gr B steel in simulated boiling-water re-the steel Intergranular fracture surfaces in high-fluence CP ma-actor environments, (2) SCC of Types 347 and CF-3 cast tenal were charactenzed by relatwety high levels of Si, P, and Ni duplex stainless steel (SS), and (3) effects of heat to-heat vana-segregation. Segregaton of the impunty elements and intergran-tion on SCC of Type 304 SS Crack growth-rate (CGR) tests utar fa:iure in the HP matenal were negligible for a similar were performed on conventional (nonplated) and nickel-or gold' fluence level. However, grain boundary depletion of Cr was plated A533 Gr B specimens to provide insight into whether the more significant in HP matenal than in CP mater al, which indi-surface layer on the low-a!Ioy steel, either oxide corrosen prod-cates that irradiaten-induced segregaten of impunty elements ucts or a noble metal, influences the overall SCC process, CGR and depleton of alloying elements are interdependent.

tests were also conducted on specimens of Type 347 SS with different beat treatments, and a specimen of CF 3 cast SS with NUREG/CR-4744 V04 N1: LONG-TERM EMBRITTLEMENT OF a femte content of 15.6*.. CGR data on these specimens were CAST DUPLEX STAINLESS STEELS IN LWR compared with reference fatigue crack growth curves in the SYSTEMS Semiannual Report, October 1988 March 1989 ASME Boiler snd Pressure Vessel Code,Section XI, Appendix CHOPRA,0.K.; CHUNG,H M. Argonne National Laboratory. May A. The influence of annrnMaly 1.0 ppm of CuCl bdeorygen.

1991. 42pp. 9105300192. ANL-90/44. 57868 245.

tated water on the h, musceptibility of Types 316NG and 347 This progress report summarizes work periormed by Argonne SS and A533-Gr B and A106-Gr B ferritx: steels was deter-National Laboratory on long term embnttlement of cast duplex mined in constant-extension-rate tonsile (CERT) tests at 200 C stainless steels in LWR systems dunng the 6 months from Oc-The CERT results indicated tuat the alternative SSs were com tober 1988 to March 1989 Charpy-impact data are presented siderably more resistant to SCC than is sensetged Type 304 SS.

for several heats of cast sta niess steel aged at temperatures The low-alloy femtic steels exhibited only ductile fracture in this betw en 320 and 450 C for times up to 30.000 h. Thermal environment.

ag e decreases impact energy and shifts transition curves to NUREG/CR-4667 V10: ENVIRONMENTALLY ASSISTED CRACK-highar temperatures. A saturation effect is observed for room-ING IN LIGHT WATER REACTORS.

Semiannual temperature impact energy sad upper shelf energy. Charpy Report, October 1989 - March 1990.

RUTHER,W.E.;

data are analyzed to obtain the activaton energy of the kinetics SHACK,W.J.; CHUNG,H.M.; et al. Argonne National Laboratory.

of embrittlement. The results suggest that the actuation energy March 1991,30pp. 9104220294 ANL-91/5. 57450.231.

of embnttlement is not constant in the temperature range of This report summanzes work performed by Argonne National 290-400 C, but increases as temperature decreases A correla-Laboratory on environmentally assisted cracking in light water tion is presented for estimating the extent of embruttement of reactors dunng the six months from October 1389 to March cast stainless steels from known matenal parameters. The deg-1990. Low-cycle fatigue tests were performed on Type 316NG radaten in mechanical properties can be reversed by annealing SS to better understand we effects of cyclic strain range fre-the embnttled matenal for 1 h at 550 C and then water quench-quency, and temperature on fatigue life in air and in simulated ing BWR water, and to assess the degree of conservatism in the ASME Code Sectacn lit fatigue design curves Fracture-mechan-NUREG/CR 4744 V04 N2: LONG-TERM EMBRITTLEMENT OF ics crack-growth-rate tests were carned out on a composite CAST DUPLEX STAINLESS STEELS IN LW' specimen of A533-Gr B/Inconel-182/inconel-600, plated with SYSTEMS. Semiannual Report.Apni-September nickel, to estabhsh whethcr a transgranular crack will initiate in CHOPRA.O.K.; SATHER.A., BUSH.L.Y. Argonne National Labo-the femtic steel from an intergranular crack in the inconei-182 ratory June 1991. 341pp. 9107010128 ANL 90/49. 58251095

Main Citations and Abstracts 7

This progress report summantes work periormed by Argonne all seal cooling such as stoon blackout. Cost / benefit analysis National Laboratory on long-term thermal embnttlement of cast results are favorable for all items based on the established duplex stainless steels 6n LWR systems dunng the 6 months guideline of $1000/ person rem. This report along Technical from Apnl to September 1989. Tensile and fracture toughness Findings Document (NUREG/CR 4946) are intended to provide data are presented for several heats of cast stainins steel that background information and input to the regulatory analysis were aged up to 30,000 h at temperatures of 290 450 C. The report for GI-23 results indicate that thermal aging increases the tensile stress and decreases the fracture toughness of the matenals. In gen.

NUREG/CR 5300 V01: INTEGRATED RELIABILITY AND RISK etal. CF-3 steels are the least sensitive to thermal aging embnt-ANALYSIS SYSTEM (IRRAS) VERSION 2 5 Reference Manual.

I tiement and CF BM steels are the most sensitive. The increase RUSSELL,K.D.; MCKAY,M K.; SATTISON.M 0; et al EG&G in flow stress of fully aged cast stainless steels is ~10% for Idaho, inc- (subs of EG&G, Inc ) March 1991. 43Bpp.

CF-3 steels and - 20% for CF.8 and CF BM steo!s. The frac-9104220309 EGG-2613. 57448 348.

ture toughness J(IC) and average teanng modulus for heat i that The Integrated Reliabihty and Risk Analysis System (IRRAS) are sensitive to thermal aging (e-g. CF 8M steels) are as k w as is a state-of the-art. microcomputer-based probabdistic nsk as-

- 90 kJ/m(2) and - 60, respectively. Correlations are prese nted sessment (PRA) model development and ana!yss toof to ad-for estimahng the increase in flow stress of the steels from iata dress key nuclear plant safety issues IRPAS is an integrated for the kinetics of thermal embnttlement-schware tool that gives the user the ability to crriate and ana-lyze favit trees ano accident sequences using a microcomputer, NUREG/CR 4893: TECHNICAL FINDINGS REPORT FOR GE.

This program provides functions that range from graphical fault NERIC ISSUE 135. Steam Generator And Steam Une Overfin tree construction to cut set generaton and quantification Ver-issues.

• SCIENTECH Inc, May 1991. 112pp 9106040379.

sion 10 of tne nRRAS program was released in February of SCIE 42-89 57003.262.

1987. SincJ the tirT.u, many user comments and enhancements r

A detailed review of the tasks and available literature pertain, have been incorporated into the program providing a much ing to Genene issue 135 (Gl 135), Steam Generator and Steam more powerful and user-fnendiy system. This ve:sson has been Line Overfill issues, has been conducted and is documented in designated IRRAS 2.5 and is the subject of this Reference this technical hndings report. The purpose of the review was to Manual ' version 2.5 of IRRAS provides the same capabihties as evaluate the current status of the issues and to determine Version 1.0 and adds a relational data base facehty for manag-whether sufficient information exists for resolution, or whether additional work is required Based on the review, it is concluded ing the data, improved functionality, and improved algonthm per-that all issues are eithe' resolved or are being pursether addp

formance, tional work is lequired Based on the review, it is concluded that NUREG/CR-5395 V01: MULTILOOP INTEGRAL SYSTEM TEST all issues are either resolved or are being pursued as part of (MIST 1 FINAL REPORT. Summary GLOUDEMANS.J R. Babcock other activities. 'n addition, a data search and evaluation were conducted on the frequency and effects of steam generator

& Wilcox Co. Apnl 1991.184pp 9105220046-EPRl/NP-6480, 57826.165.

overhil events. Potential mitigating actions were considered It was concluded that the pubhc health and safety nsks associal.

The Multiloop integral System Test (M!S1) is part of a multh ed with these events are relatively minor and do not justity addL phase program started in 1983 to address small-break loss-of-Cooiant accidents (SBLOCAs) specific to Babcock and Wilcox tional mitigating actions or regulations.

designed plants. Mi3T is sponsored by the U.S. Nuclear Regu-g NUREG/CR 5128: EVALUATION AND REFINEMENT OF LEAK-RATE ESTIMATION MODELS.

PAUL.DD-AHM AD,J -

SCOTT,P.M.; et at Battelle Memonal Institute. Ap'ni 1991.98ph The unique features of the Babcock and Wilcox design, specih-9104290259 BMb2164. 57530173'mportant elements in devel-9

" " " " *

• 9** *

- Leak-rate estimation models are i "O

Oping a leak-before-break methodology in piping integnty and o amss me mmaMah %m psh W was safety analyses. Existing thermal hydrauhc and crack opening-area models used in current leak rate estimations have been in-existing facikty-the Once Through Integral System (OTIS)-was corporated into a single computer code for leak-rate estimation.

also used Data kun M and @S am used to wma*

The codo is called SOUIRT, which stands for Seepage Onntifi-the adequacy of system codes. such as RELAPS and TRAC. for cation of Upsets in Reactor Tubes. The SOUIRT program has predicting abnormal piant tiansients The MIST program is re-been vahdated by companng its thernal hydrauhc predictions ported in 11 volumes. Volumes 2 through 8 pertain to groups of with the hmited expenmental data that have been pubhshed on Phase 3 tests by type; Volume 9 pesents inter group compan-two phase flow through slits and cracks and by companng its sons, Volume 10 provides comFansons between the RELAPS/

crack-opening-area predictions with data from the Degraded MOD 2 calcufations and MIST observations, and volume 11 Piping Program. In addition, leak rate expenments were con-(with addendum) presents the later Phase 4 tests This is ducted to obtain vahdation data for a circumferential fat:gue Volume 1 of the MIST final report a summary of the ent:re crack in a carbon steel pipe girth weld.

MIST program. Major topics include, Test Advisory Group (T AG)

'4UREG/CR 5167: COST / BENEFIT ANALYSIS FOR GENERIC issues, facility scahng and design, test matnx, observations, ISSUE 23: REACTOR COOLANT PUMP SEAL FAILURE.

companson of RELAP5 calculations to MIST observations, and NEVE.R.G.; HEISELMANN,H.W. SCIENTECH, Inc. Apnl 1991.

MIST versus the TAG issues MIST generated consistent inte.

134pp.9104250014. SCIE NRC-00190 57490,089.

gral-system data covenng a wide range of transient interactions.

The cost / benefit anaiysis for Genenc issue (GI-23), " Reactor MIST provided insight into integral system behavior and assist-Coolant Pump Seal Failure " is presented. The cost /benett ed the code effort. The MIST observations addressed each of analysis compnses three items: (1) treat the reactor coolant the TAG issues.

pump (RCP) seat assembly as an item performing a safety-relat-ed function similar to other of the reactor coolant pressure NUREG/CR-5440: CRITICAL ASSESSMENT OF SEISMIC AND boundary, applytng quakty assurance requirements conssstent CEOMECHANICS LITERATURE RELATED TO A HIGH LEVEL with B of 10 CFR 50 and apphcable General Design Cntena of NUCLEAR WASTE UNDERGROUND REPOSITORY.

Appendix A. (2) provide RCP manufacturer recommended in-KANA,D.D. VANZANT,B W.; et al. Center for Nuclear Waste y

strumentation and instructions for monitonng RCP seal periorm-Regulatory Analyses BRADY,8 H G ltasca Consulting Group, ance and detecting incipient RCP seal failures and (3) provide inc June 1991.

176pp. 9106250161. CNWR A89-001.

RCP seat coohng dunng off-normal conditions involving loss of 58225.001.

1

8 Main Citations and Abstracts A comprehens!ve literature assessmer' has been conducted ducten potent a! and cost effectiveness of each potential im-to determine the nature and scope Si technical informahon provement. The analysis also investigated the cost / benefit as-available to charactorize the seismic r erformance of an under-pects of selected combinations of potential improvements.

ground repository and associated fac tities Significant dehcion.

cios were identified in current practico for prediction of seismic NUREG/CR 5537: APPROACHE S FOR THE VAllDATION OF response of underground excavutiors in tointed rock Conven-MODELS USED FOR PERFORMANCE ASSESSMENT OI tonal analytical methods, based or. a continuum representaton HIGH LEVEL NUCLEAR WASTE REPOSITORIES. DAVIS.P.A.;

of the host rock mass may have limited apphcabil.ty in a trae.

OLAOUE.N E. Sandia Nationaf Laboratones GOODRICH,M.T.

turej media Field observations and laboratory expenments ind,-

Gram, Inc. March 1991. 34pp 9104220336. SAND 90 0575.

cate that, in jointed rock, the behavior of the joints controls the 57447.246 overall performance of underground excavatons. Further, under The purpose of this report is to provide general approaches repetitive seismic loading shear displacement develops pro-and concepts that can be apphed in vahdation of models used gressively at block boundanes Field observations conelating in performance assessment of high-level waste (HLW) repositor-seismicrty and groundwater conditaons have provided segnificant ies The approaches are based on a vakdation strategy that information on hydrological response to seismic events Howev.

Sandia Natonai Laboratones (SNL) has implemented as partici-er, lack of a comprehensive model of geohydrological response pants in the international Transport Vahdation Study (tNTRA.

to seismicity has limited the transportability of conclusions from VAL). This strategy focuses on the demonstration that perform-field observatons, ance assessment roodels are adequate representations of the MUREG/CR 5456: ANALYSIS OF FLOW STRATIFICATION IN r g atcry requirements rather than proving absolute correct.

THE SURGE LINE C THE COMANCHE PEAK REACTOR-ws from tne purely scientific point of view Posrtions that are SUNJG.; SHEN.Y.H,; SHA.W.T. Argonne National Laboratory talen consist of the following- (1) due to the relevant time and Apnl 1991. 58pp. 9105160064 ANL-91/6. 57728 043-space scales, models that are used to assess the Mrformance A number of nuclear power plants have reported failure of re-et a HLW repository can never be vaidated, therefore, (2) vali-actor components due to flow stratification Therefore, a funda-daten is a process that consists of building confidence in these mental understanding of, and a capability to predict, flow stratif" models and not providing "vahdated" models; in this context, cation in a reactor system is entically important to reactor per-(3) model validation includes compansons to "reahty " however, formance and safety. The work presented here is the first step adequacy for the given purpose (assessing comphance with reg-in this direction and will contnbute to the resolution of the issue ulations) is the overall goal, (4) compansons to " reality" consist of flow stratification. An anatysis is performed using the of comparing model predictons against laboratory and field ex-COMMIX 1C computer program for the surge line of the Coman-penments, natural analogues, and site-specific information, (5) che Peak reactor. A compenson is made between the calculat' when companng expenmental data to model predictions, a ed results from the COMMIX code and the plant measured model can be either " invalid" or "not invahd," based on the nuti data, and the agreement is good.

hypothesis concept. however, conf dence in the model anses in NUREG/C9-5467: RISK-BASED INSPECTION bulDE FOR finding a model to be "not invahd" over a wide ra:.ge of condi-CRYSTAL RIVER UNIT 3 NUCLEAR POWER PLANT.

tons; (6) an attempt should be made to conseder in the valida.

SMITH,B W.; DUKELOW,J S.; VO T.V.; et al Battelle Memonal tion process all plausible conceptual models; and (7) when Institute, Pacific Northwest Laboratory. June 1991. 74pp.

companng expenmental data to model predictions, a logical sys-9107080262. PNL 7108. 58309:318.

tematic approach should be followed (ie., model input tested separa ty from model structure) This report discusses (1) the The Level 1 probabilstic nsk assessment (PRA) for Crystal n

River Unit 3 (CR-3) has been actaly7ed to identify plant systems definite ' of vahdation in the context of performance assess-and components important to minimizing pubhc nsk, as meas.

ment for HLW repositones, (2) the need for vahdaten, (3) an ured by system contnbutions to plant core dar tage frequency, approach to vahdation, and (4) an approach to companng and to identify the pnmary failure modes of these components.

model predictions with experimental data proposed by the au-The report presents a senes of tables, organized by system and thors.

prioritized by nsk importance, which identify components associ-ated with 98% of the inspectable nsk due to plaat operation.

NUREG/CR-5543: A SYSTEMATIC PROCESS FOR DEVELOP-The systems addressed, in descending order of nsk importance ING AND ASSESSING ACCIDENT MANAGEMENT PLANS.

are; Low Pressure inlection, AC Power, Service Water, Deminer, HANSON.D J.; BLACKMAN H S.; MEYER,0.R.; et al. EG&G ah2ed Water, High Pressee Injection, DC Power, Emergency Idaho, Inc. (subs, of EG&G, Inc.).

Ap il 1991. 94pp-Feedwater, Reactor Coolaint Pressure Control, and Power Con-9104290253. EGG-2595. 57530:271.

version. This ranking is based on the Fussell-Vesely measure of This document desenbes a lour step approach for developing nsk importance, i.e, the friction of the total core damage fre.

cnteria recommended for use in assessing the adequacy of ac-Quency which involves f ailures of the system of interest Cident management plans. Two steps of the approach have been completed and provide a prototype process that could be NUREG/CR 5526: ANALYSIS OF 6lSk FEDUCTION MEASURES used to develop an accident management plan. Based on this APPLIED TO SHARED ESSENTIAL SERVICE WATER SYS-process, a prehminary set of assessment criteria are denved.

}

TEMS AT MULTI UNIT SITES. KOHUT,P.; MUSICKLZ.;

These pichminary entena wn! be refined and iraproved when the FITZPATRICK,R Bro % haven National Laboratory June 1991-remaining steps of the approach are completed, thai Is, after 171pp 9107010104. BNL-NUREG-52225. 58250:245-the prototype process is vahdated through application.

This report summanzes a study performed by Brookhaven National Laboratory fur the U.S. Nuclear Regulatory Commis-NUREG/CR-5546: AN INVESTIGATION OF THE EFFECTS OF sion in support of the resolution of NRC Genenc tssue 130. GI-THERMAL AGING ON THE FIRE DAMAGEABILITY OF ELEC-130 is concerned with the potential core damage vulnerabihty TRIC CABLES. NOWLEN,S P. Sandia National Laboratones resulting from failure of the amergency service water (ESW)

May 1991. 96pp. 9106120194. SAND 90-0696. 58062:031.

System in selected multiplant units. These multiplant units are Thm report documents the findings of an expenmentalinvesti-all twin pressun2ed water reactor designs that have only two gation of the effects of thermal aging on the fire damageabWty ESW pumps per unit (one per train) backed up by a unit-to-unit of eiectnc cables lwo popular types of nuclear quahfied cables crosstie capability. This genenc issue apphes to seven U S.

were evaluated For each cable type, both unPged (ie., new off sites (14 plants). The study established and analyzed the core the reel) and thermally aged samples were exposed to steady-damage vulnerabihty and identified potential improvements for state elevated temperature environments until conductor to-con-the ESW system. It obtained genenc estimates of the nsk re-ductor electncal short ng was observed. Plots of the time to

Main Citations and Abstracts 9

electncal failure versus the exposure temperature were dev the development of correlation parameters that islate fracture oped and thermal damage thresholds were determined. For one toughness with nominal stren and strain states In the first cable type, the thermally aged cabies were less vulnerabie to phase of inia work, the scope of the investigaton is limited to thermal damage thari were the unaged samples as 1emonstrat-crack front constraint conditions that can be desenbed in terms ed by an increase in the thermal damage thrwhol ; ior the aged of conventonal one-parameter (K or J) irdplane near tip fields samples, and an extended survival time at exposure tempara-and the transverse strain Vahdaten checks of the arialysis tures above the damage threshold for aged samples compared methods against existing fracture data for cordtions of con-to unaged samples. For the second cable, the threshold of ther.

tained C#a%.ip yieldings are promising but incomplete Recom-mal damage was lowered somewhat by the aging process, an mertations tor subsequent phates of the work considered nec-indication of an increased vulnerability to thermal damage due essary to provide more precise estimates on the effects of post-to aging However, for the higher temperature exposures. no trve out-obplane straining on the crar.k initiation toughness of stat:stical d>fterence between the damage times for aged and circumferentially oriented flaws are included.

unaged cable samples was noted For both cable types. the NUREG/CR 5598: IMMERSION STUDIES ON CANDIDATE CON-i changes in the thermal damage threshold observed were not TAINER ALLOYS FOR THE TUFF REPOSITORY.

considered significant in terms of fire nsk, BEAVERS,JA; DURR,C L Cortest Columbus Technologies.

NUREG/CR 5565: THE RESPONSE OF BWR MARK 11 CONTAIN-May 1991.122pp 9105300197. 57868123 MENTS TO STATION BLACKOUT SEVERE ACCIDENT SE-Cortest Columbus Technologies is investigating the long-term q

OUENCES. GREENE,5 R.; HODGE.S A.; HYMAN C,Ra et al-performance of container matenals used for high level radioac-A Oak Ridge National Laboratory May 1991.313pp.9106210012-trve waste packages. This information is being developed for ORNL/TM 11548. 56167:216-the Nuclear Regulatory Commission to aid in thetr assessment This report describes the results of a series of calculations of the Department of Energy's appication to construct a geo-conducted to investigate the response of BWR Mark li contairF logic repository for disposal of high-level radcactive waste. This ments to short-term and long-term station blackout severe acci-report summarges the results of exposure studies performed on dont sequences. The BWR LTAS, BWRSAR. and MELCOR two copper-base and two Fe-Cr-Ni alloys in simutated Tutt Re-codes were employed to conduct quantitative accident se-povtory conditions Testing was performed at 90 degroes C in Quence progression and containment asponse analyses for three environments; simulated J-13 well water, and two environ-several =tation blackout scenanos. The m:cident mitigation ei-ments that simulated the chemical effects resulting from boug fectiveness of automatic depressurization system actuation-and irradiation of the groundwater. Creviced specimens and U-drywell flooding via containment spray operation, and debos bends were exposed to liquid, to vapor above the condensed quenching in Mark 'l suppression pools is assessed-phase, and to alternate immersion. A rod specimen was used to NUREG/CR 5565: THE HIGH LEVEL VIBRATION TEST monitor conosion at the vapor 4 quid interface. The specimens pROGR AM Final Report.

PARK,Y.J.;

CURRERI,J R.;

were evakited by electrochemical, gravimetnc, and metallogra-HOFMAYER,C.H. Brookhaven National Laboratory. May 1991.

phtc techniques following approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of expo.

488pp 9107030236 BNL NUREG 52240. 58295:349 sure. Results of the exposure tests indicated that all four alloys As part of a cooperative study between the United States and exhbited acceptable general corrosen rates in simulated J-13 Japan, the U S. Nuclear Regulatory Commission (USNRC) and well water. These rates decreased with time Incipient pitting the Ministry of intemational Trade and industry (MITI) of Japan was observed under deposits on Alloy 825 and pitting was ob-agreed to perform a test program that would subject to a large served on both Alloy CDA 102 and Alloy CDA 715 in the simu-scale piping model to significant plastic strains under excitation lated J-13 well water No stress corrosion cracking (SCC) was conditions greater than the design condition for nuclear power observed in U bend specimens of any of the alloys in simulated plants. The objective was to compare the results of the tests J-13 well water. General corrosion rates of the copper-base with state of the-art analyses. Compansons were done at differ, alloys in an active-corrosion environment wen moderate, and ent excitation levels from elast'c to elastic-plastic to levels no SCC was observed. However, severe pstting and crevice cor-

{

where cracking was induced in the test model The vibration roson occurred in this environment. Both Alloy 304L and Alloy tests and post-test examination were carned out in Japan by 825 exhibited low general corrosion rates with no evidence of the Nuclear Power Engineenng Test Center (NUPEC). Input localized corrosson (pitting. crevice corrosen or SCC)in a patting moton development and pre-and post test analysis were car, environment in the absence of hydrogen peroude (H(2)O(2)). a ned out in the United States at the Brookhaven National Labo.

Species added to simulate the effects of radiotysis. Alloy 825 ratory BNL and the Electric Power Research Institute EPRI. This continued to exhibst good corrosion performance after H(2tO(2) report descnbes the results of the cooperative studies per.

was added to the pitting environment, whereas, Alloy 304L ex-formed boBNL and the Electr:c Power Research Institute EPRL b bited both pitting and SCC e result of the H(2)O(2) add 3 tion.

This report desenbes the results of the cooperative studies per.

NUREG/CR-5601: EFFECTS OF PH ON THE RELEASE OF RA.

formed both in Japan and the United States.

DIONUCLIDES AND CHELATING AGENTS FROM CEMENT-NUREG/CR-5592: ANALYTICAL STUDIES OF TRANSVERSE SOLIDIFIED DECONTAMINATION ION EXCHANGE RESINS STRAIN EFFECTS ON FRACTURE TOUGHNESS FOR CIR-COLLECTED FROM OPERATING NUCLEAR POWER STA-CUMFERENTIALLY ORIENTED CRACKS.

SHUM.D.K.M ;

TIONS, MCISAAC,C,V.; AKERS,D,W.; MCCONNELLJ.W EG&G

}

MERKLE.J G.; KEENE% WALKER; et al Oak Ridge National Idaho, Inc. (subs. of EG&G, Inc ) June 1991. 316pp.

Laboratory _ Apnl 1991,151pp 9105t60051 ORNL/TM 1150 t.

9107080245. EGG-?605. 5830E229

'i 57729.023.

Data are presented on the physical stability and teachability The obicctive of this report is to desenbe the development of of radonuclides and chelating agents from cement solidifod de-analysis methods for estimating tne decrease in crack initiation contamination non-oxchange ressn wastes collecteo from two toughness, from a reference plane strain value, due to pos;tive operating commercial light water reactors Small scale waste-strainsng along ine crack front of a circumferential flaw in a re-form specimens collected dunng solidifications performed at the actor pressure vessel. The analysis methods are based on two Brunswick Steam Electnc Plant Unit 1 and at the James A. Fito different approaches that are currently being developed to ana-Patnck Nuclear Power Station were leach-tested and subjected lyze and to explain the effects of transverse strain and stress to compressive strength testing in accordance with the Nuciear states on tracture toughness The first approach is a micro-me-Regulatory Commission's " Technical Position on Waste Form" charucal approach that provides a relaton between fracture (Revision 1) Samples of untreated resin waste collected from toughness and more fundarnental matenal properto that can -

each soldfication vessel before the soliditcation process were be determined expenmentally The second approach focuses on analyzed for conceritrations of radionuclides, seiected transiton 1

10 Main Citations and Abstracts

. metals, and chelating agents to determine the quant:bes of N70E in agreement with a large body of crustat stress data these chemicals in the waste-form specimens The chelating nisewhere in eastern North Amenca Relocabon of earlier agents included osahc, citnc, anci picolinic acids in order to de.

events near Lancaster revealed an elongated and nearly NS termine the effect of teachant chemical composition and pH on trending Jane of seismicity The actvity seerns to be associated the staV"N and leachability of the waste forms, waste-to'm with cross stnke f<.1atures that intersect the ENE trend.ng lit %

specito t were leached in vanous teachants Results of this loge units of the Tr assic Basin in the Lancaster area Other ac-study irocate that difierences in pH do not affect roteases from tsvity dunng the monitonng interval of this report was confined t'a cementaohdified _docontamination bn exchange resin waste eastern Pennsytvan,a in general the earthquakes that occurred forms, but that Trferences in leachant chemistry and the pres-are located in arcas of past histonc se;smn;ity Block-tectonic ence of chelating agents may aftoct the releases of radionu-structures resu".ing frc<m pro Ordovician tectonc displacement 4

chdes and chelating agents Also, this study indicates that the appear to influence the distribution of contemporary scismicity j

cumulattve releases of radionuchdes and chotating agents are in Pennsylvania and surrounding areas simnar for waste form specimens that decomposed and those that retained their genere! physical form.

NUREG/CR 5630 PWR DRY CONTAINMENT PARAMETRIC 4

STUDIES GIDO,R G, WILLIAMS'D C.; GREGORY,J J Sandia NUREG/CR 5611: ISSUtES AND APPROACHES FOR USING Nat ona! Lateratones Apol 19J1 212pp 91051tiOO46 EQUIPMENT RELIAB LITY ALERT LEVELS. LOFGREN.E V4 SAND 90-2339 57726171, GREGORY,S.H. Science Apphcations International Corp (f o

Sur y was used as a representabve dry contonment plant to merly Science Applications, Inc )

• Brookhaven National Labo^

the evaluation of possible ways that containment performance ratory. June 1991. 137pp 9107000250. BNL NUREG 52251 could be improved Sens!t vity studies using the NUREG-1150 58308 218 models and methodologies were used to estimate the reduction This report desenbos work accomphshed to identify issues of nsk potent als resulting from bypass scrubbing and DCH par-and approaches to estabhsh alert levels for component reliabe tial depressurization. These studies showed that the greatest rx.

ity. Rehabihty alert levem are estabhshed on standby componont duction of nsk occurs when bypass relenses are mitigated by counts of success and failure, where equ>pment demands are scrubbing or prevented Hegh-pressure DCH are also irnportant.

monitored and counted to ascertain if assumptions about ac-The CON 1 AIN code was used to estimate reductior, in peak ceptable rehaothty are hkely to be correct. A Monte Carlo simu-containmer1 pressure resulting from mitigaton actions includtng lation was used to determine the detection responses and false venting partia! depressun2atcn, inorting and igniters Specifice alarm rates for several alert level systems. The detecten re' ty, the reos ons were -2 bar with ear 1y depressunration and%

sponses were obtained in response to a specified reliabihty deg-bar w th igniters Limited studies of the benefits of ventin0 and radation. Two of the alert systems were demonstrated with nerting were made, t>ut addtonal investigat.ons are needed to actual failue data on the Emergency Diesel Generator (EDG) complete this area of investigaton. A brief discussion regarding for five plants. Burden and nsk measures of effectiveness were concepts to mitigate the consequences of bypass is presented developed to compare different alert level schemes having d:f' CONT A!N-code calculations were perfonced to investigate the ferent detecten responses and false alarm rates.

possible overp dssunzation of the contarnment for the stahon NUREG/CR-6612: DEGRADATION MODELING WITH APPLICA.

Diackout scenario.

TION TO AGING AND MAINTENANCE EFFECTIVENESS EVALUATIONS. FA'

'T A,P.Kc, VESELY.W.EJ HSU F.: et at NUREG/CR 5647: FISSION PRODUCT PLATEOUT AND LIFT-Brookhaven N.

aboratory. March 1991.

73pp OFF IN THE MHTGR PRIMARY SYSTEM. A REVIEW.

WICHNER,A P. Oak Ridge National Latg.,ratory Apnl 1991.

9104220330 BN' 2252 57448 028 This report de, Jegradation modehng approach to 127pp.9105030145 ORNL/TM 11685. 57617:163 A review is presented of rnethods for predicting radioactivity analyte data on et

.f degradation and failure to under, release resutting from depressun2ation of an MHTGA parnary stand the processen n agmg of components As used here, system. The vanous types of depositon mechanisms effective degradation modehng is the anatysis of informaton on compo, for odine, cesiunt strontium, and silver are discussed in terms nent degradaten in order 10 develop 70defs of the process and of their chermcal charactenstics and the nature of the rnalanais its imphcations This particular modeling focuses on the analysis in the pnmary system Emphasis is given to odine behavior, sn-of the times of component degradations. to model how the rate of degradation changes with the age of the component. The ciuding the quantity available for release the types of "pla-teout" locations, and the effect of dust on distnbubon and re-methodology presented also discusses the effectiveness of lease The behavior of fisson products cesium, strontium and main'enance as appbcable to aging evaluations. The specific silver in such acctdents is presented qualitatNeiy. A major part apphcations whic presented also discusses the effectmeness of of the rowew deals with expected cust levels, types, and trans-maintenance as apphcable to aging evaluatons. The specrfic applications which are performed show quantitatrve models ot port. Available information on the level and nature of dust in the HTGR primary system rs reviewed A summary is presented of component degradation rates and component failure rates from dust deposition and httott mechanisms This study concludes plant-specific data. The statistical techniques which were deveb that iodine releases from dry depressunzation events are hety oped and apphed allow aging trends to be effectively identified to be extremely low. due to low degrees of chemical desorption, in the degradation data and in the failure data Initial estimates liftoff, and a low involvement of todene with dust. Mechanisms of the ettectiveness of maintenance in limiting degradatens controlling the distnbution and httoff of fission product matenr1 from becoming fattures also were developed These results are in the pnmary system, depend strongly on the cherMat natur?

important first steps in degradation modehng and show that of the indwidtpl eiements Therefore, both plateout and hfterf degradation can be modeled to identify aging trends.

models should rettect those unique chemical and physical prop-NUREG/CR-5628: PENNSYLVANIA SCISM:C MONITORING erties NETWORK AND RELATED TECTONIC STUDIES Final Report.

ALEXANDER.S S. Pennsylvania State Univ, University Para NUREG/CR-5648: TRANSPORT CALCULATIONS OF NEUTRON PA. June 1991. 37pp. 0107010103. 58251:056.

TRANSMISSION THROUGH STEEL USING ENDF/B-The magnitude 4.2 earthqualie that occurred near Lancaster.

V. REVISED ENDF/BN,AND ENOF/B-VI IRON EVALUATIONS Pennsylvania on Apnl 23. 1984 was among the largest in the WILLIAMS.M L.; ABOUGHANTOUS.C, ASGARI.M ; et al Louise histonc record for that area. The mainshod occurred as an ob-ana State Uvt, Baton Rouge, LA.

Apol 1991 56pp have thrust on a steeply dipping NS-stnMng lauft at a focat 9104290244. ORNL/TM-I t086. 57531005 depth ai 4 7 krn The associated pnncipal stress deterrninatens The ENDF/B-VI evaluated nuclear data fue has been recently showed a ma.amum compressive stress oriented approximately released by the U S Nationa! Nuclea. Data Center dunng 1990 l

l

Main Citations and Abstracts 11 Amo^0 the most eagerty awa'ted tv. cross tectori evaluations ersting fac6lrty the Once Through Integra! System (011S)4as en this dait, collecton are those for the natural tron isotopes, also used Data from MIST and OTis ars used to t+nchmark due to their importance in truclear systems ann ynes and te-the adevacy of system codes, such as (1 LAP 5 and TRAC, for s

cause the prevous ENDF/D data (version V, which was re-predicting abnorte,al plant transients The MIST Functonal leased 6n 19/9) are known to utrierestimate the transtrussion of Specif 9, ton cocuments as-truilt dewgn features, dimensons, fast neutront through steel structures such at teactor pressure instrumentatch, and test approach it also represents the scal-vessels and radiation shielding in this paper, a companr.on is eng basis for the fastify anc serves to Johne the scope of wcwk made of results obtained from nt-utron transncrt calculatons for the f acildy design and cor'structon performed with then two CNDF/B ver:Jons (V and VI) of iron NUREQ/CR467b A UNIFIED tNTE. tiG EXPERIM RpAETATION OF ONE FtrTH data as well as an intermediate, revised versich V evaluation s

TO f~ULL SCALE THERMAL MIM thal was pcposed in 1986 Several different response param.

10 PRESSURIZED THERMAL SHOOK. THf OFANOUS,7 G; eters that are sensitive to high energy neutrons are examined, YAN.H. Cahfornia, Urvv. of, Santa Barbara, CA Arti t e91.

for a variety of Geotactr6 cal configurations and soisce spectra 11 OE ENN N N is found that t's two ns>wer iron evaluations substantially in.

Thermal tmaing in telshon to Pressunted Thermal $ttck has crease the trans. Nation of hsgh energy neutrons throgh steel components with an inc6 dent fission spectrum source. Prelimi-toen examined expenmentTr throughout the world in a venety of scales These include the CREARE.1/6, the fv0/IVO (NRC)-

nary estimates indicate that the version Yi tron evalualon will 2/5, the PURDUE (UCSD)-1/2, the CREARE 1/2, the HDR 1/1 consderatAy improve the agreement between calculations ariit and the UPih1/1 test facilites The Regional Mixin0 HMet expenmental dosameter measutoments used in light water teat-and the associated computer pecgrams remix ar,d NEWMIX tor pressure vessel fluence analysis. The calculated leakage are used to interpret these data, in this ieport, in a comprehe's-spectrum of D.T fumon neutrons from an 6ron sphere is also 6m.

sive fashion. These interpretatons indicate that cooidown tran.

Moved for energies above 4 MeV, but largo discrepancies with sents and degree of stratificaton can be predicted with contt-the measured spectrum are still ob*erved at lower energies dence Universal stratification solutions are also provided, in 1

NUREG/CM666: SUDMERGCNCE add HIGH TEMPERATURE Oraphical form, and a simple procedure for hand calculaton is STEAM TESTING OF CLASS 1E ELECTRICAL CABLES.

a!so descoted JACODUS.M J. Sandia National Laboratones FUCHRER G F.

Science & Engirtering Assocotes, Inc. May 1901. 9Bpp NUREG/C46681: LOW LEVEL WASTE SOURCE TERM MODEL 9106100008. SAND 90-2629 58130143_

DEVELOPMENT AND TESTING. SULLIVAN.T Ma SUEN.C.J This report desenbes the results of high temperature steam Brookhaven Nat onal Laboratory. May 1991.

10tpp.

+

testing and submergence testing of 12 ddierent cable products 9105300183 BNL NUREG 62280. 57B68 287, thst are representative of typical cables used inede contain.

The low level waste source term model development protect ments of U S. bght water reactors Both tests were performed has adaptrt/ developed two computer codds to predict the ini-after the cables were exposed to simuftaneous thermat and ra, graton of radionuclides emplaced in shallow land bunal facih-diation aging. folicwed by suposure to loss-oftoolant accident ties The computer code FEMWATER es used to predict water flow and rnoisture content The computer code DLT is used to 4

simulatons The r. suits of the high.emperature steam test inds cate the approxL to thermal failure thresholds for each cable predct container Dreach, waste form Leaching, and contami-type. The results of the submergence test andcate that a nant Transport Recent work on this project focused on two number of cable types can withstari submergence at elevat,4 areas One involved improvements to the leaching models in.

temperatura, even 6fter exposure to a loss of coolant accident C04Wated in BLT. In partcular, this report desenbes an adde lonal model that was added to BLT which simulates the waste g.mulation.

form using the method of finite differences and treats the con-NUREQ/C&6$63: RELAP$ THERMAL.HYDRAULC ANALYSTS tacting soluton as a miring bath. Th#s model 6mproves upon the OF THE WNP1 PRESSURIZED WATER REACTOR.

prevous models in DLT in three areas. (a) it treats the release M ART!N.R P. EG&G Idahc. Inc (subs of EG&'3, ine) MaY processes of diffus6on, dissukiton, and surface nnse simulta.

1991,76pp. 9100040385. EGG 2633 57904 014-neously, (b) It allows for partitioning tietween the waste form Thermal-bydrauhc analyses of five hypothetecal accident sce~

and solution; and (c) 11 permits soluton feedback effects to in-nanos were performed with the RELAP5/ MOD 3 computer code fluence diffusive releasem Venficaton studies of the finite differ-for the Babcock and Wilcon Company Washes.gton Nucleaf ence/ mixing bath model are discussed in detail. The second Project Unit 1 (WNPt) peetturized wetor reactor This work was area of renarch involved companng DL1 (c odel predictons to sponsored by the U,S. Nudear Regulatory Commission (NRC) experimeetM data - This report presents the results of modeling and is being po'io' mod in conjunction with future anahtis work laboratory sca% wet / dry cycle teach expenments and lysimeter i

at the NRC Technical Training Center in Chattanooga, Tennes-expenments conducted at Pacific Northwest Laboratory, Based see The accident scenanos wm chosen to assess and bench-on this modehng work, tecommendalons for future areas of

?

mark 114 thermal hydrauhc capabilities of the Technical 't rainin9 study are given Center WNP1 Simulator to model abrormal tf ans ent conditions NUREQ/CR 6682: SPECIFIC TOPICS IN SEVERE ACCIDENT f

NUREG/CR-5670; MULTILOOP INTEGRAL SYSTEM TEST M ANAGEMENT. MEYER.J F4 CHUNG,D Ta PANCIERAVWa et i

(MIST) MIST FACILITY F UNCTION AL $PECirlCATION al. SCIENTECH, Inc. May 1991 200pp. 9106040392 HABIB,T.Fa KOKSAL C.Ga MOSKAL,T Ed et al Batcock &

57904:090 Wilcor Co Aprit 1991. 327pp 910522003E EPRl/NP.7105.

This report examines frve topical areas of concern to severe 37825 198.

accident management. The6e areas are as follows' Human Fac-3 The Muttsoop intogral System Test (MISi, -,, of a mutt" tors, Accident Management Dunng Shutdown. Informaton phase program started in 1983 to address sma...oreak loss of*

Needs. Long-term impucatons and Uncertainties The objective cooiant accidents (SBLOCAs) specific to Babcock and Wilcor of this report is to assist the NRC in performing its research designed plants. MIST is sponsored by the U.S Nuclear Regu-functor' and to provide guidance to the industry on accident tatory Commission, the Babcock & Wilcox Owr.ers Group, the management strategies, as weit es accident management pro.

Electnc Power Research Inst: tete and Babcock and Wilcox.

g7,,, in gen,,,i, The uruque features of the Babcock and Wilcou design, specife J

cally the hot leg U-bends and steam generators, preventer; the NUREG/CR 5683: LABORATORY TEST 6NG OF CEMENT i

use of existing integrat system data e' existing integral facilities GROUTING OF FRACTURES IN WELDED TUFF.

to add'est the thermal hydraulc SBLCCA ouestons MIST was SHARPE C Ja DAEMEN.J J K Antona, Univ. of. Tucson, AZ.

specifically designed and consttucted for this progtum, and an Marr.h 1991 163pp 9104220323. 57448115.

L

n.

12 Main Citations and Abstracts i

Tht obtuctive 6f tv. 'nvestgaton is to erpenmentally deter-ard the frac'ure is very small, channeling develops in the grout-mine the eHoctNenna of tracture sealer 3 in welded tuff uving ed fractures Preliminary results ind$cale that the permeatulity of ordinary portland cement and tnc+ofane MLGr.1 gouts. Labora a grouted fracture does not 6ncrease with time in more than 125 tory experiments have been performed on 17 tuff cyhnders with days. The f60w proporties of bentonite suspensions, v$cosity, tPr4 types of fractures. (1) tendorv6nduced cracks. (2) natural shocr stress, yeld stress and gelaton, ate 60vestgated Water frd turn A*d (3) sawcuts. prior to grouting, the hydraul6C con.

fith through ungrogted frattufes and rnovement of water en Juchily of the intact rocn and of the fractures es measured bentorute grout are studied The physn.si statulity or bipeding under a ranpo J normal stresses. The surface 30pography of capacity of tientonite sument ons is detormined tha fratture ts mapped, and the tehtts are used in Jetermine aperture drstnteons acide the tracturn Grouts are injected NUREQ/CR 6660: MECHANICAL CHARACT ERIZAllON OF 1:vough ana' ';oreholes at pressures of 0.3 ta 4,1 MPs wNie DENFELY WELDED APACHE LEAP TUFF. FUENKAJORN Aa i

hoVng fractires undar a constant.wrmat stress. Ftve group DAEulN.J J.K. Anzona. Univ of, Tucson, AZ. June 1991.

Icemuistions have been tested. 64entonite (O to 6 percent by 125pp 91070B0255. 68309 001.

weight) has been added to 1%se grouts to increase their stabalo An empincal entenori is formulated to describe the compres-i fr. Water-to cernent retion range from OA5 to 1.0 Permeability save strength of densely welded Apache leap tuff. It incorpo-l 1: sting of groutrid tractuvos is used to evaluate the efteettve-rates the effects of site, L/D rabo, loading tute and density van-no:s of fracture youting Post-tet visual inspection of Grout ations, and improves the correlation between the test results estnbution confirms that permeability testing in an i.qecton hole and the failure envelupe. Uniamial and inautal compressive la not a reliable method to assess the eftecttveness of grouting strengths, Dra20ian tensile strorgth and clastic properties of the Grout distribution is highly nord uniform densely welded brown unit of Apache Leap tuff have been de-NUREG/CR4684: ANALYSES AND FIELD TESTS OF THE HY, termined using the AS1M standard test methods. All tuff sam-DRAULIC PERFORMANCE OF CEMENT GROUT DOREHOLE p4e are tesM dy at room tempmature with the core amis SEALS. GREER.W B.; DAEMENJJ K.

Arizona. Univ. of, nond to the flow layms. The uniarial compressive strength to 73.21 16 6 MPa. The Brasilian tensile strength is 6.121 1.2 MPa.

Tucson, AZ.. April 1991, 627pp. 9104300328. 57557;105 Three tests for determining the hydraule properties of bore.

The Young's modulus and Poisson's est6o are 22 616 7 gps and i

0 30 1 0.03 Smoothness and perpendicularity oo not fully meet hole testa are anatyred m detail. Two consist of monitoring the injecton rate of water at constant pressure 6nto one end of a Ai" requirements fut all samples, due to voids and inclusions 88:1 and monitoring the collecten rate lnto a free drairung gone on sample surfaces and the sample preparation methods at the other end. The third test is performed by shutting in the The ' satigations of loading rete, L/D ratio and cyclic loading collection zone and monitoring the buildup in hydraulc head.

eHects on compressive strength and of the site efN1 on ten-One<hmensional and axisymmettc three-dimensional fiow sile strength are not conclusive. The Coulomb strength cnterson mesets are present d for analyring test recutts, in the one-dn adequately represents the failure envelope of the tuff under mensional modek the seat is homogeneous ard isotropic. In confining pressures from 0 to 62 MPs The tuff is highly hetero-the axisymmetnc models, the seat and rock mass are homoge.

geneous as suggested by larDe vanations in the results The necus and isotrope porous media. The equation for saturated.

vanability is probably caused by flow layers and by non-uniform confined ground-water flow is assumed to apply. The hydraul6c distntiutons of inclusions, vods pr'd degree of welding Similar properties of the seal are expressed by its hydraule conductivity vanaollity of propertiec has teen reported oisewhere for the To+

t,nd specife storage. In the axisymmetre models, the conductiv.

popah Spnng tuff at Yucca Mountain.

fty and spectfc storage of the rock mass are included in the for.

NUREG/CR4691: INSTRUMENTATION AVAILAullfiY FOR A mutatort Closed form solutons are presented for the one de PRESSURIZED WATER REACTOR WITH A LARGE DRY CON-mensenal models. Numental analysis with the axisymmetnc models uses an avaltab;a hntte element onde for Dround water TAINMENT DURING SEVERE ACCIDENTS. ARCIERI.W Ca flow. We examine the ofiocts of vanatons in hydraule param.

HANSON.DJ EG&G Idaho, Inc. (subs of EG&G, Inc ). March clus on the quantities measured in the tests (i e, flow rates o, 199t.128pp. 91061201D2. EGG 2638. 58062.133.

he:d) and compare the one dimensional and axisymmetic in support of the U S Nuclear Regulatory Commmaion (NRC) models. Meth9ds are presented for obtaining the hydrauhc prop.

Acc6 dent Management Research program, the availability of in-er1:es of the seal and/or rock mass by Matyvis of test results. A struments to supply accdont management mformation dunng a fourth test, a tracer travel-tire 141 presents a means for do, broad range of evere accdents is evaluated for a pressunted i

trcting any high-velocity fN pa b through or around the seal..

water re'. tor with a large dry containment. Results from this r

The test methods are applied to cement grovt borehole stials evaluation include the following (a)identifcaton of plant conds from 10 to 36 cm m length and 10 cm in diameter in a nearly l'ons that would impact Instrument performance and informaton hortrontal hole and m three vertcal holes.

needs dunng severs accdonte, (b) definiton of envelopes of parameters that eould be 6mportant m assessing the perform-NUREG/CR 6666: EFFECTIVENESS OF FRACTURE SEALING ance of plant instrumentaton for a broad range of severe acce WITH DENTONITE GROUTING. RAN C.; DAEMENJJ K. Anzo-dont seuvences, and (c) anessment o* Ine availability of plant rc, Univ. of, Tucson, AZ, June 1991,19?pp. 9107000258 instrumentaten dunng severe accdents; 58309126~

Bentonite is known to have an erttemel low permeability and NUREG/CR 5692: GENERIC RISK INSIGHTS FOR GENERAL J

f e setf-heaten0 stulity. It has therefore been selected as a maior ELECTRIC BOluNG WATER REACTOR $.

TRAVIS.Ra sealing component in several repository concepts. Dentonite TAYLORJ Grookhaven Netional Emboratory CHUNGJ Risk grouts have the following aAantages (1) small partcle size, Appleation Branen. *4i 1991. BBpp. 91062100t3 DNL-ccn be mjected into small fractures or vods, (2) suitable water NUREG 52282. 581:-

.R cbsorption properties, can produce gels at low concentrations, A methodology has w* leveloped to entract generc nsk-end (3) stable physical and chemical properties, may have Con-based information from probabilistc risk assessments (PRAs) of tderable longevity. Dentonite fracture grouting tests are per-General Electnc boihng water twctors and apply the insights formed on a model made of circular acryle plates with outer de gained to plants that have not been subocted to a PRA The t

cmeter of 30 cm and a central injecton hole of 2.5 cm diame-avaitable nsk assessments (sin plants) were examined to dents txt. Suspensons with bentonite concentration of 15% to 31%

fy 'he most probable,14, dominant accdont sequences at each have been injected into fractures with apertures of 9 to 90 tm plant The goal was to include all sequences which represented crons urder injecton pressures less than 0 6 MPa Grouting re-at least 80% of core damage frequency if the same plant spe-dWes the hydraule conductrvities of the fractures from the 10(-

cafe eminart er.cdont sogmnce appeared within this boundary

1) to the 10( 5) cm/s level When the suspension is thin enough in c' least two plant PRAs, the sequence was considered to be I

, = - -

Main Citations and Abstracts 13 a teptebentative r,egance Eight sequences met this dehrvtion NUREG/CR 6714: HYDROGEULOGIC PE RFORM ANCE AS.

From these sequences, the most important component f ailures SESSMENT ANAltSIS OF THi' LOW.LEVLL RADIOACifvE and human errors that contnbuted to each scQuence have been WASTE DISPOSAL F ACILITY NEAR SHEFFIELD, ILLINOIS pnontired Guidance is provided to pnonttre the representa9ve BERGERON.M P.; HOLFORD D Ja hEMNER.M L; et al. Dattelle Memonal institute Pacific Northwest lateratory. May 1991.

sequences and moddy nelected basic events that have tieen Shown to tie senweve to the plant specific design or operating 143pp 910b300168. PNL-7633. b7869165 A hydrogeologc pedormance assessment was conducted frv vanatons of thu contributir.g PRAs This nsk based guidance the commercial k>*. level radioactive waste disposal site located can te uts4 tot utshty and NRC actrvtties including operator about 3 mi southwest of the town of Shotheid, m Bureau trairwng. maintenance, design review, and inspersons.

County, northwestuen lilmois The site has 21 trenches, wtuch NUREGICR4702: ACCIDENT MANAGEMENT INFOPMATION contain atout 900.000 m(3), of buned waste and about 60,000 NEEDS FOR A DWR WITH A MARK I CONTAINMENT.

C4 of menear by product ma'enal The d*posal trenches cut CHIEN D N4 HANSON,D J. EG&G idaho Inc, (subs. of EG&G, th'ough a complex senes of Guaternary depowts, and are com-Inc) May 1991.100pp. 9105220020 EGG 2639. 67824 000 posed pomarily of allts. clays, and sands. Ground water beneath Pe s% which ranges in depth from t.5 to 14 m, generally In support of the U S. Nuclear Regulatory Commisson Acc5 moves in two directions northeast to east toward a stno mine dent Management Research Prog'am, informatsu needs dunng lake and south to southeast toward small inbutary channels te-severe accdents have teen evaluated for Boiling Water Reac.

longing W Lawson M whch weMuah & mins No be stnp-tors (DWRs) with MARK I containments This evaluaton was trune take southeast of the sits.1he results tn the periormance performed uwng a methodology that identifics plant informaton essessment, which focused on the site ground water pathway, needs necessary for personrel to- (a) diagnose that an accdont suggest met inWnt W. and W woud W Pe onh Mon #

is in progress, (b) select and implement strategies to prevent or clides released from the Sheffield arte in any signifscant concen.

mitigate the accident, and (c) monitor the effecttveness of these Vatons A compense of sinua d inun concenvatons east slogress. (b) select and 6mplement strategies to prevent or mite Pe sh m bme hans d N W Nsm wM nW gate the accident, and (c) monitor the effectiveress of these 9"

strategies The 6ntormation needs and capabilites identified are a fa w

e screpancy Mwwn aNat aM M Intended to term a baws for more comprehen.tve rnformation het model results are greater than the highest measured values needs assessments. TNrse assessments will be petto med by a factor of 2 or 3. The discrepancy t)etween actual and pre.

dunng the analyvs and development of specific strategies, dicted concentrations like!y reflects errors in the assumed tnte wh6ch will be used 6n accident management prevention and mit' um inventory estimates, availahlity in the 6nventory, and/or the gaton.

actual release from the multitude of waste forms conssdered 6n

"*#'**"#*""""*" ^ * "U""" " ' " " " ' " " * " "

NUREQ/CR 670s: POTENTIAL SArETY RELATED PUMP LOSS AN ASSESSMENT OF INDUSTRY DATA NRC Bulletin 88 04

'" E CASADA,0 A. Oak Rdge Natonal Laborstory June 1991 $2pp.

9107010081. ORNLm670 6824ft 305 NUREQ/CR 6716: MODEL VALIDAllON AT THE LAf CRUCES This repor1 documents the resulte of a study of the nuclear 1RENCH SITE. HILLS.R G. Nw* Mexico State Univ, Las industry's response to NRC Bulletin 80 04. The work was con-Cruces, NM WlERENGA.P.J Antona. Urw of Tucson, AZ.

ducted for the U S Nuclear Regulatory Commission (NRC) Nu.

June 1991. 95pp. 9107080234 68307:134 clear Plant Aging Research Program All wntten correspond-A senes of dynamic field expenments have been performed once between utilities and tne NRC was reviewed and classi.

at the Las Cruces Trench site to provide data to test determinis.

tic and stochastic models for water flow and solute transport in fied. Major pump vendors were 6nterviewed to discuss their per.

spectives on low. flow degradation of pumps Individual sites spatially vanable unsaturated soils lwo experiments were pet-formed to provide support for model valdatson efforts dunng were vivled to review the details of system design anti oroce.

Phase 1 of IfJRAVAL (an international ettort towards valdation --

dural controls relative to the Bulletin tasues.

of pr+osphere mod 6s for transport of radionuclides) and a third NUREG/CR 6713: A REVIEW OF ENVIRONMENT AL CONDI.

expenment is currently underway to support the INTRAVAL TIONS AND PERFORMANCE OF THE COMMERCIAL LOW.

Phase 11 efforts. The third ogenment utilized different boundary LEVEL RADIOACTIVE WASTE DISPOSAL F ACILITY NEAR and 6nitial conditions and additional chemical tracers The data SHEFFIELD.lLLINOIS, MURPHY.E M.; BERGERON.M P. Dat.

from the third experiment along with model predictons from telle Memonal Institute. Pacihc Northwest lateratory. May several modeling groups will be used to test models int water flow and solute transport dunng infiltestion and redistnbuton.

1991.137pp 9105300177. PNL 7621 57869 028 This report Summantes the las Cruces Trench $ste model vali-4 The Shefoeld low.ls ael radcactive waste disposal site is 10 daten efforts and presents the INTRAVAL Phase 11 vahdation cated about 6 km southwest of the town of Shettield, Bureau plans. The Phase il vahdation strategy is discussed in detail.

County, in northwestern Illinois. Lo*4evel radioactrve waste wa, buried at the arte between August 1067 and Aprd 1978. The NUREG/CR 67t7; PACKAGING SUPPLIER INSFECTION GUIDE.

ground-water system beneath the Sheff end site can b<; concep' STROMBERG,H M.; GREGG.R L; KlDO.C; et al EG&G Idaho, tuattrod as containing two separate aqueter systems. a regional inc (subs, of CG&G. Inc) May 1991 53pp. 9107010119. EGG-conhnod bedrock aquifer system and a local unconhned naviter PMI. 68274 001.

system in the shallow Sequence of unconsohdated quaternaT This document is a gude for corxtucting gaality assurance in-aged sediments The most signihcant hydrogeologie unit on the spect,ons of transportation packaging suppliers, where suppleers site is a pebbly sand unit found within the Toulon Member of are defined as designers, latnatort. distnbutors, users. or the Glastord Formation that grades into a coarse gravel with owners of transportat on packaging This cocument can be used sand and pebbles east of the disposal site in an area east of donng an inspection to determine regulttory comphance within the site, a narrow, channellike depression is filled with coarse, the requirements of 10 Code of Federal Regulat:ons, Part 71.

gravelty Sand of the pebbly-sand unit of tne Toulon Memba:.

Subpar 1 H (10 CFR 71.10171.135). The gudance described in provding a hydraulic connection between the site and a nearby this document provides e framework for an inspection 11 pro-stnp mine lake. Three major problems resutung kom t!.e waste vides the inspector with the flombility to adapt the methods and burial at the Sheffield site 6nclude subsdence of trench covers.

concepts presented here to meet the needs of the particolar fa-signifiCant erosion, and elevated concentratons of tntium in the cihty being inspected The gude was developed to ensure a vadose Tone and ground water at Shethold structured and consistent approach for inspections The me3od

14 Main Citations and Abstracts treats each act+vity at a suppher facmty as a separate entity tor dective purposes by demonstratina their ability to p' edict vahda-funcional element), and cornbanes the actrvaties within the lion de e %t used for fitting s

framewc4 of an "inspecton t'oe " The method separate s each NUREQ/CR473h HYDROGE OLOGIC p[ RF ORMANCE A S-functonal vement into several s'eas of peMormance and then SESSVE NT ANALYSIS Of 1HE COMMERCIAL LOW LEVEL Klentihet guidehnet. based on regulatory requirements. to be RADIOACTIVE WASTE DibPOSAL F ACILIT Y NE AR WES1 used to Qualitativey rate each t.nea This document was devel.

V AL LEY,NEW YORK DE RGE RON M P SMOOT J L or d to serve as a fold manual to faciktale the woo of inspec-M MM R# L, d W Dm% Mew MN pm NM' west Laboratory June 1991 110pp. 910701N79 PNL 7bMi E NUREQ/CR472h CHLORIDE 104 Df rVSION IN LO

$3248196 TO-SOLID CEMENT PASTES CLIFTON.J R ; M4 AD.L I; A hydrogeologic performance assessment of the commercial GARDOCZl,E J et at Nabonal institute of Standards & Tech.

le* level maste site hear West Valley, New York, was per, nology (formerly National Bureau of Standa June 1991 3tpp fortned for two pathways a shauo* lateral pathway where 91070B024B NISTlR 4649 SB30818$

trench noter can potentially mig' ate laterally through fractured Otffuvon coeffoonts of 0 3 mater to sches ratio (*/s) hydrat, and weathered tili to neaty streams and a deep vertical path-ed portland cement paste specimens were measured using a way whora leathate can migrate downward through unweath-conventional doluson cell Specimens were made from toth cred till and laterally offsite 6n a lacustone unit Along the shal.

ASTM Type I and Type il portland cements and blends contain.

tow pathway, little physice s'te evidence is available to indicate tog mineral admixtures (fir ash, granulated blastfurnace slag, or what the degree of lateral migrabon can be Past modekng sihca fume) The average ortfuson coethcient for the portland showed that overflowing trench water would trugrate laterally cement paste specimens was 14:10( 13) m(2)/a The diffswon some d stance before mig'ating downward into the unweathered coethcients for the specimens containing mineral admixtures tiH If water did reach a nearby stream, calculabons show that were much more vanable than those for the portland coment decay, adsorption, and streeni d.lvtson would reduce teachate paste spectmens. A probable cause of the var,abibty to the test concentrabon to acceptable le.els Within the deep pathway,,,

retutts was the presence of cracks obser ed in the test specu inhum and cartson 14 were the only radionuclides released in v

mens The effects of the depth of concrete cover over reinforc.

any $sgnihcant concent'abons Predicted intium levels are well mg steel and of the chlonde ton diffusion coefficient on the below regulatory hmits, ho*rvor predicted peak C 14 concen.

service life of reinforced concrete esposed to chlonde sons were trations, whde meebng the b nrem/yr bmit using the onnhng-predicteo based on a diffusion model Dased on the model, the water-only exposure scenano, ciceed the kmit for full garden effect of the cover was shown to be proportonal to the square scenano. Site information on C 14 release rates and geochemi-of the ccder depth A 10-fold do?.rease in the diffuson coeffi.

cal behavior has considerable uncertainty and would need to be cient of concrete was predicted to result in a 10. fold increase more fully evaluated in a hcensing situaton in the predicted service life Dased on the results of the present NUREG/CR4742 V01: FE ASIBILITY ASSESSMENT OF A RISK-study, it is recommended that a new chlonde diffusivity test BASED APPROACH TO T ECHNICAL should be developed which is apphcable to concrete A cand" SPE CIFICATIONS Esecutive Suminary.

ATEllB; date test method is proposed GALLAGHER D W. Scence Apphestens Internatonal Corp (fnr.

NUREG/CR 5729: MULTIVARIABLE MODELING OF PRESSURE mody Science Apphcatons, Inc ) May M 12pp 9m00%

VESSEL AND PIPING J R DAT A E ASON.E D ; WRIGHT.J E.,

S AW00400. 581301 N The first phase of the assessment concentrales on (1) identi-NELSON.E E. Modeling & Computer Services May 1991.

11Bpp 91061201B0 MCS 910401. 58063 227, heaton of selected riskbased approaches for improving current tEhnical specihcations (2) appraisal of charactonstics of each Multivanable mode:S were developed for predichng J R curves from available data, such as malenal chemistry, radiabon approach, including advantages and $$ advantages, and (3) rec-esposure, temperature, and Charpy V notch energy The ommndabon d one or more approaches that might result in present work involved collectinn of pubhc test data, apphcation improving cuant techmcal bpecihcatiois requirements The of advanced pattern recognition tools, and cahbrabon of im-second phase of the work concentrates on assessment of the proved multivanable models Separate models were fitted for kaW% of unphantaton of a pdot program to study detailed charamnshcs of he prdened approact; The real time risk-different matenal groups, including HPV welds Linde 80 welds, FtPV base metals, piping welds, piping base metals, and the based approach was 6dentihed as the preferred approach to combined database Three eff arent types of nodnis were de-twhnical bpMdicatons for controuing plant operatonal nsk veloped, involving d4fferent combinabons of vanablM that might There oc not appear to be any technical or 6nstitutional obsta-be available for apphcahons a Charpy model, a preitradiation clos to prevent intbation of a pdat program to esms the ct;ar.

Charpy modet, and a copper-fluence model in general, the best actenstics and effectiveness of such an approach results were obtained with the preirradiaton Charpy model. The NUREG/CR 5742 V02: FEASIBILITY ASSESSMENT OF A RISK-copper fluence model is recommended only if Charpy data are BASED APPROACH TO TECHNICAL SPECIFICATIONS Main unavailable, and then only for Linde 80 welds. Relatrvely. good Report ATEFtB; G ALL ACHE R,D W.

Science Appkcal ON fits were obtained, capable of predicting the values of J for Internahonal Corp (formerly Scence Apphcabons, Inc ) May pressure vessel steels to with a standard deviaton of 1318%

1991 B4pp 9106180007 SAIC404400 58130 043 over the range of test data The models were quakhod for pre-See NUREG/CR 5742,V01 abt. tract

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

SECONDARY REPORT NUMBER REPORT NUMDER

$tCONDARY REPORT NUMBER Rt PORT NUMBER lib h4+2 NUALG/CH46%

ANL-99/ 42 nun (.G/CH 4513 il l' M 4Y'4 NUHI G 'C 'i l'7%

ANL+0/ 44 NUHf G/CR 4744 VD4 N1 D 9440I NM b O U29 ANL99/ 48 NURI G/C H 4%7 V09 ANL 90/49 NURE G/CR 4744 V04 N2 hI[ dh#'

fh V02 i3 ANL 91/5 NURf G/CH 4%7 VIO onyt.g y i Ngp gecN tyg ANL -91/6 NUR[ G/C84 t,4%

DONL/NSIC 2CO NUW G'( R 2CW.0 V10 N2 ANL -91/ 9 NUR[G/CR 4M7 Vil OHNL /NS)C Pf v)

NUR( G/LH 2000 V10 N3 liAW 2023 NURt.G/CR 5395 V01 OHNLINSiC 230 NUHI G/CH 2'#A Vip N4 flM6 2164 IRE G/C H $128 OHNL/1M 11f 48 NUHf G/CR M45 OHNL/1M-M!*1 NUH( G/CR %9?

BMI 2173 NURE G/CR-45W VOI Ni UUNL 'IM ' M'M NUUIU'kN %d?

BNL NUHEG t222%

NVALG/CR St26 M

6 f

R DNL-NUHf G 52240 NJhtG/CR %B5 g

p V07 N1 BNL NUAE G $225i NUHfG/CR 5611 T' ARA 6M 11 H li.103 NUHf G'CR 4(4

'6NLWURE G 522h2 NURE G/CR %12 PNb7100 NUHi G /C84440,7 (4NI. NUhlG L2283 NURf G/CR 5M1 PNL 7621 NUf4f G!CH 5713 DNL-NUhl G 527tt?

NU4E G/CR %92 PNL-7ta) f4Uitt G/CH $714 CNWH AB9-001 NURE G/CR f,440 PNL 7(*6 Nunt G/CH 5737 5AlG 93/1400 NUlti G/CF4 5742 V01 f.GG 2$95 NURfG/CR M43 b A C 99/14 t>0 NUHE G/CH 5742 V02 i GG 2613 NUHf G/C;R f,3CO V01 kA ff hpy I GG 2b05 NUHE G/C ri f691 (GG 2633 NUHE G /CR tu,3 ggggggg73 gggg gfgn g37 i GG 2638 NUH[G/CH %91 S ANNO MW, NUH( G/CR %46 i GG 2639 NUHLG/CR 5702

$AND90 2359 NUniG/CR %30

[ GG 2641 NURf G/CF4 5717

% ANDuo-2t.29 NUHiG/C4 % %

i PHl.'NP4460 NURE G/CR 5395 V01 Scil 42 99 NUni G>CH 4p3

[Phl'NP 7165 NUREG/CHf470 Y W NHG.00190 NUHf G/CR 5167 a

15

\\

(

4 t1 i

b s

4 1

1

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

)

ABOUGHANTOUS.C.

NUREG/CR 5737 HYDROGE OLOGIC PE RF ORMANCE ASSE bSME NT NUREG/CR %48 1R ANS80RT CALCULA10NS OF NEU1RON ANAL Y SIS OF THE COMME RCI AL LOW-L E VEL R ADOACTIVE TRANSMIS$lON THROUGH STEEL USING E NDF/D V, REY!SE D WASTE DISPOSAL F Aclu'y NE AR Wt $1 VALLEYht W YORK I

ENDF/B.V.AND ENDF/B Vt IRON EVALVATIONS BLACKM AN.H S.

AHM AD.J.

NUREG/CR 5543 A SYSTEMATC PROCESS FOR DEVELOPING AND NUREG'CR.4599 V01 N1. SHORT CRACKS IN PIPING AND PIPING ASSESSING ACCIDEN1 MANAGEMENT PLANS WELDS Som annual Repo/t March Semiemter 1D90 NUREG/CR 5128 EVAi UATION AND ROINEMENT OF LE AK. RATE BOTLE.C D.

ESilMATION MODELS NUREG/CR 5717. PACKAGING BUPPUER iNSPE Ci.ON GUIDE.

AKERS,0 W.

'O "

NUREG/CR %01. EFF ECTS OF PH ON THE RELE ASE CI RADIONU-NUREG/CR 6440 CRITICAL ASSESSMLNT OF bEISMiG AND GEOME-CUDES AND CHELATING AGENTS F RDM CE MENT SOLIDlF1ED DE.

CHANICS LITERATURE RELAtED IO A HiGH LEVEL NUCLE AR CONTAMit4ATION ION EXCHANGE RESINS COLLECTED FROM Op.

W ASTE UNDERGROUND REPOSi10RY ERATING NUCLEAR FOWER ST ATONS ALE K ANDE R.S.S.

BRASA NUREG/CR %29 PENNSYLVANIA SEISM C MONITORING NETWORK NUREG/CR %64 V02 TECHNOUES FOR DETERMINING PRODABIL-AND RE LAT Eo 1ECTONC STUDIES Final Report ITIES OF EVEN1B AND PROCESSES AFFECTING THE PERFORM-ANCE OF GEOLOGtC REPOSITORit S Suggested Apswoachen AMOS.CR NUREG/CR 4551 V2H1P2 EV ALU AT ON OF SEVERE ACCOLNT BRE E DING R.J.

RISKS. QUANTIFICATON OF MAJOR INPUT PARAMETERS Emperts" NUREG/CR 4551 VPRtP2 EVALUATION E# SEVE RE ACCIDENT Determmaton Of Contamment Leeds And Molten Co's Contamment RISKS OUANTIFICATON OF MAJOR INPUT PARAMETERS Emperts' interaction issues Determination Os Containment LcTds And Monen Core Omtamment APOSTOLAKit,G.

NUREG/CR 3964 V02. TECHNtOVES FOR DETERMINING PROBADit.

BROWN,T.0, (TIES OF EVENTS AND PROCESSES AFf ECTING THE PERFORM' NUREG/CR 4551 V2 RIP 2 EVALUATON OF SE VE RE ACCIDE NT ANCE OF CTOLOGC REPOSITORIES Suggested Approaches RtSKS OVANTIFICATION OF MAJOR INPUT PARAMETERS Emports' Dowmmaton Of Containn'ont Loads And Monen Cm Containment ARCIERLW.C.

NUREG/CR-5691 INSTRUMENTATON AVAILABluTY FOR A PRES-SUR12ED WATER REACTOR WITH A LARGE DRY CONTAINVENT BRUST F DURING SEVERE ACCIDENTS ~

NUREG/CR 4599 V01 N1; SHORT CR\\CKS IN PIPING AND PtPING ASGARt,M, WELDS Semannua' keport. Ma*ch-September 1990 NUREG/CR 5646 TRANSPORT CALCULATIONS OF NEUTRON TRANSM!SSON THROUGH STEEL USING ENDF /B-V. REVISE D BUSH,LY.

NUREG/CR-4744 V04 N2 LONG-TERM EMBRITTLEMENT OF CAST ENDF/D V,AND ENDF/B Vi lRON EVALUATIONS DUPLEX ST AINLE S3 STEELS IN LWR SYSTF M3 Sem annual ATEFt.B.

Report,Apr4Septenter 1989 NUREG/CR 5742 V01. FEASIDluTY ASSESSMENT OF A RISK-BASED APPROACH TO 1ECHNCAL SPECIFICATIONS Esecutwe Summary CASADA.0A, NUREG/CR-5742 V02: FEASIBluTY ASSESSMENT OF A RISK. BASED NUREG/CR 5706. POTENTIAL SAFETY RE LATED PUMP LOSS AN AS-APPROACH TO TECHNIC 4t. TPECIFICATIONS Mam Report SESSMENT OF INDUSTRY DAT A NRC Bulietm 88 04 8 ASDE K AS,0.

CHIEN.D N NUREG-1421 REGULAYORY ANAL,VSIS FOR THE RESOLUTION OF NUREGICR 5702 ACCIDENT MANAGEMENT INFORMATON NEEDS GEt4ERIC IS4UE 130 ESSENTLAL SERVICE WATER SYSTEM Fall-FOR A DWR WITH A MAhK i CONI AINMENT.

URES AT MULTiUNIT SITES.

CHOKSH W BASS.B R'CR 5592 ANALYTCAL STUDIES OF TRANSVERSE STRAIN NURM75 S34 SAW MWN WRT WM M THE NUREG/

EFFECTS ON FRACTURr TOUGHNESS FOR CIRCUMFERENTIALLY 1AND2 et Nos 2 5 W 50 323 Fa* Gas And EMm ORIENTED CRACKS Company)

BE A VE RS.J.A.

CHOPRA.OK.

NUREG/CR-5596. IMMERSION STUD:ES ON CANDCATE CONT AINER NURE G'CR-45 t 3 ESilMATICN OF FRACTURE TOUGHNESS OF ALLOYS FOR THE TUFF REPOSITORY.

CAST STAINLESS STEELS D.HING T'iERMAL AGING IN LWR SYS-BERGERON,M.P.

TE MS NUREG/CR 5713: A REVIEW OF ENVIRONMENTAL CONDITIONS AND NUREG/CR 4744 VD4 N1 LONG4 TERM EMBRITTLEMENT OF CAST PERFORMANCE OF THE COMMERCIAL LOW-LEVEL RADIOACTIVE DUPLEX ST AINLESS STEELS IN LWR SYST EMS Semiannual W ASTE DISPOSAL FACluTY NEAR SHEFFIELD.tLUNOtS Report Octoter 1968 March 1989 NUREG/CR-5714. HYDROGEOLOGC PERFORMANCE ASSESSMENT NUREG/CR-4744 VO4 N2 LONG-TERM EMBRITTLEMENT OF CAST ANALYSIS OF THE L.OW4EVEL RADIOACTIVE W ASTE DsSPOSAL DUPLEX ST AINLE SS STEELS IN LWn SYSTEMS Semannual FACIUTY NEAR SHEFFIELD. ILLINOIS ReportApil Septomter 1989 17

18 Personal Author index CHUNO.D Y, FUEHRE R.O.F.

NUREG/CR %42 SPECIFIC TOPtCS IN SEVERE ACCIDENT MANAG6 NUREG/CR %% SUBut RGENCE AND HiGH TEMPERATURE S1[AM MENT.

TESTING OF CLASS 1E ELECTRICAL CABLES CHUNO.H M F UENK AJORN,K.

NUREG/CR 4667 V10 ENVIRONMENTALLY AS$1STED CRACKING IN NUREG/CR %88 MECHANLCAL CHARACTER 12ATON OF DENSELY LIGHT WATER RE ACTORS Sonennual Report October 1989 Mtth WELDED APACHE LE AP TUFF.

1990 NUREG/CR 4%7 Vit: ENYlRONMENTALLY AS$1S1ED CRACKING IN G AL8,AQHE R,0.W.

LIGHT W ATER REACTOR $ Semiannual Report AprtSeptemtier 19M NUREG/CR 5742 V01: FE ASIBILITY ASJSSMENT OF A Al$K BASED NUREG/CR4744 V04 N1 LONG-TERM EMBRITTLEMENT OF cab 1 APPROACH TO TECHNICAL SPECIFICATONL Eacutsve Sommary OUPLEX ST AINLf SS STEELS IN LWR $) ST EMS Semiannua!

NUREG/CR $742 v02 FE AS BluTY ASSES 5 MENT OF A RISK pAWD

(

Report October 1968 + March 1989.

APPAGACH TO TECHNICAL SPECirtCATONS Main Report OHUNO.J IC N

TE REA O NUR G/C E727: CHLOROE ON DiF FUSON IN LOW WATER-TO-SOLIO CEMENT PASTES CLIFTONJR.

NUREG/CR 5727. CHLORIDE ON Dif FUSON IN LOW WATER TO.

QHADIALt.N.

SOUD CEMENT PASTES NUREG'CR 4699 V01 N1 SHORT CRACAS IN PIP:NG AND PIPING WELDS Semiannual apport. March September 1990 CRONIN,W.E.

NUREG/CR 6737 HYDROGEOLOGIC PERFORMANCE ASSESSMFNt GIDO.R.O.

ANALYSIS OF THE COMMERCIAL LOW LE VEL RAD 60ANE NUREG/CR.5630 PWR DRY CONTAINMENT PARAMETRIC STUD!ES WASTE DISPOSAL FACIUTY NEAR WEST VALLEY.NEW YOR%

GLOUDE M ANS.J.R.

CURRENI.J.R.

NUREG/CR4395 Vot: MULTILOOP INTEGRAL JYSTEM TEST NURE G/CR 55e5 THE HIGH LEVEL VIBRATON TEST P,40 GRAM Finn!

(M:st) FINAL clEPORT Sammary Report NUREG/CR $670 MULTILOOP INTEGRAL SYSTEM TEST (MIST) MIST b

DAEMEN,JJ K.

NUREG/CR4663 LABORATORY TESTING O' CEMENT GROUTING 0000 RICH,M.T.

I b

^

R E

MENT GR TP HOLE SE AL AR WASTE REPOSITORIES HUREG/CRMhe EFFEUTIVENESS OF FRACTURE SEAUNG WITH DENTONITE GROUTING NU EG'/CR 4651 V2R t P2: EVALUATION OF SEVERE ACCOENT WELDE A C TO F' R15k$ OUANTIFICATON OF MAJOR INPUT PARAMETERS Luperts' DAVD,PA Determination Of Containment Loads And Monen Core Containment HUREG/CR 5637: APPROACH'.S FOR THE VALOATION OF MODELS intme neten issues USED FOR PERFORMANC% ASSESSMENT Or HIGH LEVEL NUCLE-AR WASTE REPOSITORir.6 GAE E NE,$.R.

NUREG/CR 5%5 THE RESPONSE OF BWR MARK 11 CONTAINMENTS DEANAS.

TO STATON BLACKOUT SEiERE ACCOENT SEQUENCES NUREG/CR-4668 CLO',EOUT OF IE BULLETIN 84 02 FAILURES OF GENERAL ELECTRO TYPE HF A RELAiS IN USE IN CLASS 1E GREIFs W.B.

SAFETY SYSTEMS NUREGICR-%64 ANALYSES AND FIELD TESTS OF fHE HYORAULIC PERFORMANCE OF CEMENT "sROUT BOREFOLE SE ALS NUREG/CR 6467.11SK-BASED INSPEC10N GUCE FOR CRYSTAL.

OREOG.R F RIVER UNIT 3 N9CLE AR POWER PLANT, NUREG/CR 87R PACKAGING SUPPUER INSPECTION OUOE.

DURR.C.L GRaOORYJJ.

NUREG/CR.%98 IMMERSON STUDIES ON CANDOATE CONTAINER NUREG/CR.4%1 V2 RIP 2 EVALUADON OF SEVERE ACCOENT ALLOYS FOR

• HE TUFF REPOSITORY, RISAS QUANTIFICATON OF MAJOR INPUT PARAKETERT, E aperts' Determination Of Containment Loads And Mol% Cwe O.Wainment R G dR-67hp-MULTIV ARIABL E MODEUNG OF PRESSURE N

f[R "['PWR DRY CONTAINMENT PARAMETmc $ROiES 3

VESSEL AND PtPING J.R DATA.

GREGORY,$.H.

E SSGT.H NUREG 1301: OFFSITE DOSE CALCULATON MANUAL GUOANCE NUREG/CR Mit: ISSUES AND APPROACHES FOn WPG EQUIP.

MENT REUADIUTY ALERT LEVELS STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR PRES, SURIZED W%TER REACTORS Generic Lener 89-01tupp6ement No H ABID.TI.

NUREG/CR $670 MULTILOOP INTEGRAL SYSTEM TEST (MIST) MIST NUREG 1302. DFFSITE DOSE CALCULATON MANUAL QUCANCE FACluTY FUNCilONAL SPECiflCATON STANDARD 1ADIOLOGICAL EFFLUENT CONTROLS FOR BOluNG WATER REA? TORS Genenc letter 89 01. Supplement No.1, hANSON,0.J.

PITZPATRICK,R.

NUREG/CR.6543 A SYSTEMAtlC PROCESh FOR DEVELOPING AND NOREG/CR %2S ANALYSIS OF RISK REDUCTION MEASURES Ap.

ASSESSING AcCOENT MANAGEMENT PLANS PUED TO SHARED ESSENTIAL SERVICE WATER SYSTEMS AT NUREG/CR4601: INSTRUMENTAT6ON AVAILABILITY FOR A PRES-

' MULTEUNIT Srds.

SURIZED WATER RE ACTOR WITH A LARGE DRY CONTAINMENT DURING SEVERE ACCOENTS

~ FLANICAN.LF, NUREGICR 6702 ACCOENT MANAGEMENT INFORMATON NEEDS NUREG/CR-5128-JVALUATION AND REFINEMENT OF LEAK-RATE FOR A BWR WITH A MARK I CONTAINMENT.

ESTIMATION MOLUS.

HARPE R.F.T.

FOLE w.WJ.

NUREG/CR-4H1 V2RtP2 EVALUATION OF SEVERE ACCWENT NUREGICR 4666 CLL'SEOUT Or IE BULLETIN 84-02 FAILURES OF RISKS-QUANilF6 CATION OF MAJOH INPUT PARAME fERS E parts' GENERAL ELECTRIC TYPE HFA RELAYS IN USE tN CLASS 1E Determination Of Containment Loads And M1 ten Core Contasnment SAFETY SYSTEMS interaction Iwuet

--m

,y.

-f

,w n.c

=m,7-.-.qw,y

-_.,9_

y

,m-9

,.,7y-y,,

7h

~

-~_._ _ _ _ _

i Personal Authof index 19 H A V NE S.H.D.

NURt GTR e%7 Vit ( NVIRONMENf AL LY ASSIS1ED CRACMNG IN NURI G/CR 4X,2 V02 AGtNG AND SERVICE WEAR Of CHlCK UGHT W AllR RC ACTOR $ Senpannua! Reget Arnl Septww 1990 1

VALVES USED IN LNGINElRED SAFE 1Y1C ATURE SYSTEMS OF NUCLE Ali POWE R PLAN 1b Aging Anenments Ard Morntonng kiENEY WALK 1R Method ( valuateont NURIG/CR 5%2 ANALYliCAL STUDIE S Of TRANSVERSl' 51 RAIN E7ii CTS ON FRACiU54E 1DUGHNI$5 IOR C48GUWE REN11 ALLY Nt DGE S.D.

06UEN11 D CA ACA5 NUREG 120 PDL OVAUTY ASSullANCE GUIDANCE $0R A LOA LEVEL HADOAC1tVE W ASTE DibPOSAL F AC UTY KE MNt R.M L 6

NUREG/CR 5714 HYDROOt OLOGIC PiIV ORMANCE ASSI SSMI NT f

UREG A 1 COST /BENENT ANALYS!S FOR GEN [RIC ISSUE g

3 9

g 23 HE ACTOR COOLANT PUMP SE AL F A! LURE NUREG/CR 5737 HYDROGE OLOG'c PERFORMANCE ASST SSMt NT Ht NNICK,A.

ANAL YSIS Of THE COMM6 RCIAL LOW LEVEL RADIDACTNE NUREG/CR 4%6 CLOSEOUT Or il BULLETIN 84 02 f AltuRt S Or W ASTE DISPOSAL f ACILITY NEAR WEST VAtlEY,Nt W YORK GENE RAL l'LECTRtC TVPE Ht A Rf lay $ it4 USF IN ct ASS 1E SAF ETY SYSTEMS K OO.C.

NUREG/CR 5717 PACP AGtNG SUPPil[ R sNSP(.C1 TON GUIDE.

HILLS.R.O.

NURE G/CR-571tt MODE L VALOATION AT THE LAS CHUCfS k N AB.LL TRENCH SITE.

NUREG'CR 5727 CHLORIDI lON Dif 3 USON IN LOW WA1ER TO-SOLIO Cf Mf NT PA51[$

HISE R.A L NUREG 1426 V01 COMPILATON OF REPORTS FROM RE SE ARCH KOHUT,P.

SUPPORTED DY THE M AT E Ri AL S E NGINE E HtNG NURE G/CR4526 ANALYSIS OF f4tbt HE DUCilON ME ASURE S AP-BRANCH.DtVISION OF ENGINEERING 1965 1990 PUED TO SHARf D ESSENTIAL St $1VICE WATER SYSTEMS At HODGE.S.A.

NUREG/CR.5565 THE RE SPONSE OF E4WR MARK tl CONT AINME NTS KOKSALCO.

TO STATON DLACKOUT SEVERE ACCOENT SE QUEf4CES NUREG/CR4670 MULTILOOP INTE GRAL SYSTf M TEST (mis 1;MIB1

1. MU OW ##

• HOF W A Y E R.C.H.

NUREG/CR %85 THE HIGH LEVEL VIBRA 10N TEST PROGRAM hnal K RISHN A$ W A W Y,P.

"*WU NURE G/CR 4599 VOI N1 SHORT CRACKS IN PIPING AND PIPING HOLFORD.D.J.

WELDS Semannua! Report March September 1990 NUREG/CR 5714 HYDROGTOLOQiC PERFORMANCE ASSESSME NT ANALYSIS OF THE LOW LEVEL RADIOACitVE WASTE DISPOSAL LANDOW,M F ACluTY NEAR SHEf flEl.D. ILUNOf$

NUREG/CR 4599 VOI N1 SHDR1 CRACKS IN PtPING AND PIPING WELDS Samiannual Report Ma@. Sop 1 ember 1rn HOST E TLE R.C.J.

NMEG/CR 57f 4 HYDROGEOLOGIC PE Rf'ORM ANCE ASSE SSME NT

LEUNON, ANa. YSIS OF THE LOW LEVEL RADIOACTNE W ASTE DOOSAL NUREG 1421 REGULATORY ANALYSIS FOR THE RESOLU10N OF F ACIUTY NE AR SHErrtELD, ILLINOIS GENERIC ISSUE 130 E SSENilAL SERVICE WATER SYSTE M F All-URES Al MULTI UN11 Si1ES NUREG/CR4612. DEGRADATON MODELING WITH APPUCATON 10 LOf GRE N.E.V.

AGING AND MAINTENANCE ErFECTIVENESS EVALUATONS.

NUREG/CR S611 ISSUES AND APPROACHES FOR USING EQUIP-HUMPHRIE S.O.&.

NUREG/CR 5682. SPECIFIC TOPICS IN SEVERE ACCOENT MANAGE' M A R SCHALLC,W, MENT.

NUREG/CR 4W9 Vot N1 SHORT CRACKS IN PIPING AND PIPING HYM AN,C.H WELDS Semawal Report Mao Septembe W NUREGICR 5565 THE RESPONSE OF BWR MARK 11 CONTAINMENTS M ARTIN R P TO STATON DLACKOUT SEVERE ACCOENT SEQUENCES NUREG/CR SWI RELAPS THERL.AL-HYDRAUL6C ANAL.YSIS OF THE J AC KSON.J.E.

WNP1 PRE SSUf412E D W ATER RE ACTOR NUREG 1401 DRFT FC RE GULATORY ANALYSIS FOR GENERIC MA ET iSSU 23 REACTOR COC4 ANT PUMP SE AL F AILURE Oraft Repart g

41 REGULATORY ANALYSIS FOR THE RESOLUTON Of GENERIC ISSUE 130 ESSENTIAL SERVICE W Af ER SYSf!M F AIL-J ACOBUS.M.J.

URES AT MULil-UNIT SITES NUREGrCR4655 SUBMERGENCE AND HIGH TEMPERATURE STE AM TESTING OF CLASS 1E ELECTRICAL CABLES MCCONNELL,J W.

NUREG/CR4601. EFFECl$ OF PH ON THE RELEASE OF RADICNU-JOLICOEUR.J.R-CUDES AND CHELA!iNG AGENTS F ROM CEMENT-SOLO 6FIED DE.

NUREG 1394 Fiui: (MERGENC) RESPONSE DATA SYSTEM (ERDS)

CONTAVINATON ON E* CHANGE RESINS COLLECTED FROM OP.

. IMPLEMENTATON.

ERAfING NUCLEAR POWER STATONS K AM F.B.K.

MCISAACAV NUREG/CR 5648. TRANSPORT CALCULATONS OF NE UTRON NURM/C $601 EFFECTS OF PH ON THE RELE ASE OF RADONU TRANSMISSON THROUGH STEEL USING E NDF /B-V,RE viGED CUDES AND $HELATING AGENTS FROM (VMEf4SOUDiF4ED DE-ENDF/B V AND ENDF /B vi IRON EVALUAIONS.

CONI AMINATON ON EVCHANGC RESINS COLLECTED FROM OP-K AN A.D.D.

ERATING NUCLE AR POWER STATIONS NUREG/CR $440 CRITICAL ASSESSMENT OF StiSMIC AND GEOME.

MCKAY.M K, CHAN6CS LITERATURE RELATED TO A HIGH-LEVEL NUCLE AR W ASTE UNDE RGROUND RE POSITORY NUREG/CR 5300 V01 INTEGRATED REUABluTY AND RISK ANALY-SIS SYSTEM (IRRASI VCRSON 2 5 Reference Manuat K ASSNER,T.F. -

NUREG/CR-4667 V09 ENVIRONMENTALLY ASSISTED CRAChlNG IN MCMULL E N.R.

LtGHT WATER REACTORS Semeannual Report Apr*Septomter 19Aa NUREG 0675 S34 SAFETY EVALUATON REPORT ret ATED TO THE i

NUREG/CR-4ti67 V10- ENVIRONMENT ALLY ASSISTED CRACKING IN OPERATION OF DIABLO CANYON NUCLE AR POWER PLANT. UNITS UGHT WATER RE AC10R$ Semannual keportOctober 1989 March 1 AND 2 Drxnel Nos 50 275 And $4323 (Pact: Gas Ad Electnc 1990 Company 1 I

i 20 Personal Au* hor index MCNAM AR A.N.

P ARK,Y,J.

NUREG4837 V10 NS4 f4RC TLD DIRECT RADIATION MON 110 RING NUREG/CR $56$ THE HIGH LEVEL Vl0RATON 1EST PROGRAM Final NETWORK Progress Report Octoter-Decernter 1990 Raget ME tNK E,W.W.

pgggg g NUREG 1301; OFFSITE DOSE CALCULATON MANUAL GUIDANCE 4

NURE G'CR $128 EVALUATON AND REFINEMENT OF LE AK RATE STANDARD RADOLOG CAL EF FLUENT CONTROLS FOR PRES-ggy;ygggy ygggg SURilE D WAllR RE ACTOR $ Generc Letter 69 01,$appiernent No PAYNE A C.

NUREG 1302 OF FStTE DOSE CALCULATON JANUAL GutDANCE STANDARD RADOLOGCAL EF FLUENT CONTROLS F OR DOILING NVRE G/CR-465 6 V2RtP2 [VALUATON OF SE VERE ACCIDENT WATER RE ACTORS. Gerert letter 69 01. Supplement No.1.

AtskS QUANTIFCATION OF MAJOR INPUT PARAMETERS E4.erts' Determmaton Of Contamment Loads And Malten Core Containment

(

MERKLE J G.

Inteartion tasacs NUREG/CR $t92. ANALYTCAL STUDTS Or TRANSVIRSE STRAtN EFFEC 16 ON FRACTURE TOUGHNESS FOR CIRCUMFERENTIALLY PE NNE LL,Wt.

ORIENTED CRACKS NUREG/CR-4219 V07 N1 HE AVY SECTON STEEL 1[CHNOLOGY PROGRAM Se% annual Prcycss Repcd1 For Octoter 1909 March ME YEM.J.F.

1990.

NUREG/CR 6682-SPECIFIC TOPICS IN SEVERE ACC' DENT MANAGE-MENT.

PtTT60VO,C.L NUMG 1293 RO1 OVALITY ASSURANCE GUIDANCE F OR A LOW.

ME YE3.0.R.

N MNUDN NUREG/CR 5543 A SYSrEMAf tC PROCESS FOR DEVELOPING AND ASSES $ LNG ACCIDENT MANAGEMENT PLANS PFUCEL MDSKAL,T.E.

NUREG/CR.3964 V02 1[CHNOVES FOR DETERMINING PROBABIL.

NUREG/CR 6670 MULTILOOP fNTEGRAL SYSTEM TEST (MIST)M:ST ITsES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-F ACluTY FUNCTIONAL SPECIFCATON ANCE OF GE OLOGIC REPOSITORIE 5 SwJ;;ested Ar$noedes CURFIN.G.W-R AN C.

NURE G/CR 4561 V2R1P2 E VALUATION OF SEVE RE ACCIDE NT NUREG/CR !MG EFF ECTIVENESS OF FRACTURE SE ALING W!'tH RISK % QUANilFCAT60N OF MAJOR INPUT PARAMETERS Egerts' BENTON11E GROUTING Determinston Of Containment loads And Mvton Core Containment interaction issues-R ASMUSON.D.M.

NUREG/CR 6300 V01; INTEGRATED REllADILITY AND RISK ANALY.

UREG

$713 A REVIEW OF ENVIRONMENT AL CONDITIONS AND PERFORMANCE OF THE ( OMMERCIAL LOW. LEVEL RADIOACTIVE RIGHTLE Y,0 WASTE DISPOSAL F ACluTY NEAR bHEFFIELD ILLINOIS NUREG/CR-4561 V2 RIP 2 EVALUATION Or LEVERE /SCIDE NT CUSIC%l,Z.

RISKS OUANTIFICAllON Or MAJOR INPUT PARAME1ERSExrerts' NUREG/CR $526 ANALYSIS OF RISK REDUCTION MEASURES AP.

hnnaton @ Coniainment Loads And Motten Cose Contamment PLIED TO 5 HARED ESSENTIAL SERVICE WATER SYSTEMS AT

'"I"'*;on issues MULT1-UNIT SITES pgg NAl?,P.K.

NUREG-067s $34' SAFETY EVALUATION REPORT RELATED TO THE NUREG/CR 6440 CRITICAL ASSESSMENT OF SEISMIC AND GEOME.

OPERATION OF DIAHLO CANYON NUCLEAR POWER PLANT,UN115 CHANICS UTERATURE hEI ATED TO A HIGH. LEVEL NUCLEAR 1 AND 2 Docket Noe 50 275 And 60 323(Pacilm Gas And Electnc WASTE UNDERGROUND REPOSITORY.

Compend NELSON.E.E, RUSH.0 C.

NUREGICA.6729 MULTIVARIABLE MODELING OF PRESSURE NUREG/CH $670: MUlllLOOP INTEGRAL SYSTEM TEST (MIST) MIST VESSEL AND PIPING J-R DATA FACluTY FUNCTIONAL ' NICATON NE VE.R.G.

RUSSE LL,K.D.

NUREG/CR 5167: COST / BENEFIT ANALYSIS FOR GENERIC ISSUE NUREG/CR 5300 V01: INTEGRA?EO RrLIABILITY AND RISK ANALY-23 REACTOR COOLANT PUMD SE AL F AILORE' SIS SYSTE M (IRRAS) VERSION 2 $ Reference Manual NOWLEN,$.P.

NUREG'#E' "I"

NUREG/CR 5546. AN INVESTIGATION OF THE EFFECTS OF THER-

/CR-4667 V09 ENVIRONMENTALLY AS$1STED CRACKWG IN MAL AGING ON THE FIRE DAMAGEABluTY OF ELECTRIC CABLES UGHT WATER REACTORS Semiannual ReportApril September 1989 OLA,00E,N.E.

NUREGICR-4667 V10 ENVIRONMENfALLY ASSISTED CRACKING IN NUREG/CR 6537: APPROACHES FOR THE VALtDATION OF MODnS LIGHT WATER REACTORS Semennual ReportOctober 1989 - March USED FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL NUCLE-19 %

. AR WASTE REPOSITORIES NUREG/CR-4667 VII. ENVIRONMENTALLY ASSISTED CRACKING IN UGHT WATER FtEACTORS. Senwannual ReporLApril Septemter 1990 1UREG 1360 V03 NUCLEAh REGULATORY COMM!SSON INFORMA.

SAMANTA,P.K.

TON D' GEST 1991 Edstion.

NUREG/CR.5(12 DEGRADATON MODEUNG WITH APPUCATON TO AQNG AND MAINTENANCE EFFECTIVENESS EVALUATIONS

' PAGE.J.D.

NUREG-1374. TECHNICAL FINDINGS RELATED TO GENERIC ISSUE SANECKI,J.E.

79 An Evaluation Of PWR Reactor Vessel Thermal Stess Dunng Natu.

NUREG/CR-4f47 Vit; ENVIRONMENTALLY ASSISTED CRACK!NG IN Conecten Ndown LIGHT WATER REACTORS Semiannual ReportApni. September 1990 PANCIERA,V W.

NUREG/CR 5682 SPECIFIC TOP 6CS IN SEVERE ACCIDENT MANAGE.

N REG R-4744 V04 N2. LONG TERM EMDRITTLEMENT OF CAST DUPLEX STAINLESS CTEELS IN LWR SYSTEMS Semiantwal PA9K,J.Y.

ReportApetSeptember 1989 NUREG/CR-4667 V09 ENVIRONMEN1 ALLY ASS STED CRACKING IN OGHT WATER RE ACTOR $ Semiannual ReportApni-September 1989 SATTISON.M B.

NUREG/CR-4667 V11: ENVIRONMENTALLY ASSISTED GRACKING IN NUREG/CH-5300 V01 INTEGRATED REUABluTY AND RISK ANALY.

LOHT WATER RE ACTORS. Semannual Report Apr* September 1990 SIS SYSTEM (IRRAS) VERSON 2 $ Reference Manual

Personal Author Index 21 SCOTT.P.

T A YLOR.J.

NUREG/CR 4599 V01 N1 5604T CRACKS IN PIPING AND PIP 1NG NUREG/CR %92 GE NERIC RISK INSIGHTS FOR GENE RAL ELEC-WELDS Semtarwwa! Report. Ma'ch $stiemier 19M 1RIC BOILING AATER RE ACTORS SCOTT.P.M THATCHER.DL NURE G/CR 51W EV ALUATON AND REFINEMENT Of LE AkRATE NUREG 1401 DR5 T S C RE GULAT OH Y ANALYSIS FOR Gl NERIC ESTIMATON MODELS ISSUE 23 M ACTOR COOLANT PUMP SE AL F ALLURE Dean Regert SH A, W.T.

F or Conwont NUREGrCR $456 ANALYSIS OF flOvv STRATIFICATON IN THE HtO A S 0 SURGE LINE OF THE COMANCHE PE AK RE ACTOR qg. 9 g y7 A UNIFIED INTERPRE1 ATON OF ONE#if TH 10

& HACK.WJ FULL SCAL E THERMAL M! RING E RPE RtMi NTS HELATED 10 8 HE S NUREG/CR 4667 V09 ENVIRONVENTAL6Y ASSISfED CRACMNG IN SURIZED THERMAL SHOCK.

UGHT W Atl R RE ACTORS Semannual Report.Arni September 1989 NUREG/CR4t47 V1D ENVIRONMENTALLY AS$lSTLD CHACMNG IN TOBIAS.M L.

)

UGHT WATER REACTORS Seawannual Report.0ctotee 1989. March NURL G/C4 %C5 1HE RE SPONSL OF tmR MARK 11 CONT AINuiNTS 1990 TO ST ATION DLACkOUT SE VERE ACCOE NT SE QUENCES NUFIEG/CR.4687 VII ENVIRONMENTALLY ASSISTED CRACKING IN UGHT WATE A REACTORS Serraarinual Report.Atwil.Septemter 1990 TR AVERLE.

NUREG/CR %B2 SPECIFIC TOP!CS IN SEVERE ACCOENT MANAGE.

p NUFIFG/CR %83 LABORATORY TESTING Or CEMENT GROuttNG OF FRACTURES IN WELDE D TUFF f n Ayl3,g, NUREG/CR StiD2 GE NERIC RISK INSIGHTS FOR GENERAL ELEC.

$HAUKAT,5 K NUREG-1405 DAFT FC. REGULATORY ANALYSIS FOR GENLRC M A A ORS ISSUE 23 REACTOR COOLANT PUMP SE AL F AILURE Orsft Floport V ALDE S,J.

Comnet NURE GrCR 3964 V02 1ECHN OUES FOR DETERMINtNG PROBABib

$HE N.Y.H.

tiles OF EVEN15 AND PROCESSES AFFECilNG THE PERFORM-NUREG/CR $446 ANALYSIS OF FLOW STRATIFICATON IN THE ANCE OF GEOLOGIC REPOS110RilS Sugpstod Apswoactes SURGE LINE Of THE UOMANCHE PE Al( REAC1CR VANZANT.B.W.

SHUM.D.K M.

NUREG/CR 5440 CRITICAL ASSE SSMENT OF SEIS"1C AND GEOME-NUREG/CR %92 ANALYTICAL STUDIES OF TRANSVERSE STRAIN CHANICE UTERATURE RELATFD 'O A HIGruEVEL NUCLE AR EFFECTS ON FRACTURE TOUGHNESS FOR CtRCUMFERENTIAL LY W AS1E UNDERGROUND RE POSITORY.

ORIEN1ED CRACKS.

VE SE LY,1F.E.

SKINNER N L NUREG/CR 6612. DEGRADATION MODEllNG WITH APPLICATION TO NUREG/CR4300 V01: INTEGRATED RELIABlVTY AND RISK ANALY-AGING AND M AINTENANCE EFF ECilVENESS EVALUATIONS SIS SYSTEM (IRRAS) VERSION 2 6 Reference Manual VIETH,P.

SMITH.B.W'R 5467:

NUREG/CR-4599 V01 N1. SHORT CRACKS N PIP'NG AND PIPING NUREG/C LISK. BASED INSPECTON GUOE F OR CRYSTAL WLLDS Senuantwal Roport. March Septemtuirr 6990 RIVER UNIT 3 NUCLE AR POWER PLANT.

VO T V

^

W Fj N E /CR4737. HYDROGEOLOGIC PERFORMANCE ASSES $ MEN 1 E

T3N AR F N

ANALYSIS OF THE COMME RCI AL LOW. LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY NEAR WEST VALLEY.NE W YORK wAgg,g, goppgy,w,g huREG/CA 3964 V02. TECHNIQUE S FOR DETERMINING PROBABIL-NUREG/CN4667 V09 ENVIRONMENTALLY ASSISTED CHACAING IN ITIES OF EVENTS AND PROCESSES AFF ECTING THE PERFORM-UGHT WATER REACTORS Semiantual Report.Apr(September 1909 ANCE OF GEOLOGIC REPOSif 0 RIES Suppstod Approaches NUREG/CR 4667 V10 ENVIRONMLNT ALLY ASSISTED CHAChlNG IN UG T WATLR REACTORS Senuannual ReporLOctober 1989. March W ARD L ASSES $1NG ACCOLnT MANAGEMENT PLANS

$TROMDERQ H M.

NUREG/CR4717. PACKAGING SUPPUER INSPECTION GUCE WEB 8.E.

NUREG/CR-3964 V02: TECHNIQUES FOR DETERMINING PROBA0lb

$fRUCKMEYER,R.

ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM.

NUREG4837 V10 NO4. NHC TLD DIRECT RADIATON MONITORING ANCE OF GEOLOGIC REPOSITORIES suggested Approactes NETWORK Progress Repod October December 1990 WE tsS,A.J.

SUBUDHl.M.

NUREG/CP0114 V01 PROCEEDINGS OF THE E GHTEENTH WATER NUREG/CR 6612. OEGRADATION MODEUNG WITH APPUCAtlON TO REACTOR SAFETY INFORMATION MEETING AGING AND MAINTENANCE EFFECTIVENESS EVALUATIONS.

NUREG/CP 0114 V02 PROCEEDtNGS OF THE EIGHTEENTH WATER RE ACTOR SAF ETY INFORMATION ME ETING NUN GrCR 6681. LOW. LEVEL WASTE SOURCE TERM MODEL DE+

REACTOR SAFETY INFORMATION MEETINu[

"E VELOPMENT AND TESTING.

SULLIVAN.T M.

WHITE,J.E.

NvREGiCR 5681: LOW tEVEL WASTE SOURCE TERM MODEL DE.

NUREG/CR 5648 TRANSPORT CALCULATONS OF NEUTRON VELOPMENT ANO TESTING TRANSMISSON THROUGH STEEL USING FNDF/D V. REVISE D ENDr/B V.AND ENDF/B VI1RON LVALUATIONS SUN.J 0.

NOREG/CR $4%: ANALYS!$ OF FLOW STRATIFICATON IN THE WICHNER.R P.

SURGE UNE OF THE COMANCHE PEAK REACTOR NUREGICR4647. FISSON PRODUCT PL A1EOUT AND UFTOf F IN THE MHTGR PRIMARY SYSTEM A REVIEW TAM.P S NUREG4847 S06. SAFETY EVALUATON REPORT RELATED TO THE WlE RE NG A,P.J.

OPERATION OF WATTS BAR NUCLEAR PLANT. UNITS 1 f.ND NUREGICR$DB MODEL VAllDATION AT THE LAS CRUCES 2 DotAet Nos $0 390 And 50-3914Tenressee Valley Authoritd TRENCH SITE

~

Personal Author index WILHOWSKl,Q.M.

WR6GHT.J E.

NUREG/CR-4?>99 VQ1 N1. SHORT CRACKS IN PIPING AND PtPiNG NUAE G/CR $729 MULTI. ARiABLE MODE LING OF PRISSURE WE LDS Semiannua! Report. March Septemteit 1990 YESSEL AND PlPIN3 J R DAT A NUREG/CR4128 EVALUATION AND RLFit4EMENT OF LE ALR ATE E SilMATiON MODE t.S WRIGHT R Q.

NURLGICR 5645 1RANSPORT C ALCUL ATIDNS OF NEUTRON WlEl. LAMS.D.C.

T M ANSM15SION THROUGH STEIL U$iN3 LNDF /9 V Al VIS!D b-KTRIC STUDIES ENDr/B V.AND ( NDFiB VI IRON la ALUATIONS NUREG/CR-5630 PAR DRY CONT AtNMENT WILLIAMS.M L XIONG.LX.

NUREG/CR4048 TRANSPORT CALCUL At TONS OF NtufRON NUREG/CR $727 CHLORIDE lON DiF FUSION IN LOW W ATE R TO.

TRANSM!$5 TON THROUGH STEEL USING E NDF /D V. REVISE D

$0 LID CEVE NT PAS 1LS

("

ENDF/B V.AND ENDF /B V1 IRON EVALVATtONS Y AN.H.

WOOO.S.T.

NUREG!CR $677 A UN(FIED INTI APRt 1 AllON OF ONE FIFTH TO NUREQ/CR $300 V01 INTEGRATED RELIABtLITY AND RiSA ANAA F ULL SCAtt. THERVAL M nIN3 I XPE R!ME NTS Rf 1 ATLD TO PRE 5 SIS SVSTEM (IRRAS) VEkSiON 2 $ R+1wome Man al SURi?CLTHLhMALSHOCA u

E

Subject Index This index was developed from keywords and word strings in titles and abriracts. During this development period, there will be some redundancy, which wiU be removed lator when a roa-sonable thesaurus has been developed through expwience. Suggestions for improvoments are welcome.

ACR$ Repod Cement NUREG 1126 V12 A COMPILATION OF Rt POR15 OF THE ADVISORY NUREGiCR f.h01 (FFECTI. OF PH ON THE ftEll ASE Of RADONU.

COMMITTE E ON RE ACTOR SAF EGUARDS 1990 Annual CUDL 6 AND CHEL AHND AGt NTS F ROM CE ML NT SOUD4 IED Dis Accident Management CONT AMINATION ON E KCHANGE REl. INS COLLE CT! D f ROM OP.

L RATING NUCLE AR POWE R ST ATONS NUREG/CR 5702 ACCIDENT MANAGEMENT INFORMATON NEE DS F OR A BWR WITH A MARK 1 CONT AINMENT.

Coment Grout AccideK Hanagement Plan NUREG/CR %lu ANAL YSt S AND FIELD TISTS Of THE HVDRAULIC PERFORMANCE OF Cf MlNT GROUT IORf HOLE SE ALS NUREG J4 5543 A SiSTEMATIC PROCE SS FOR D&Vt LOPING AND ASSEbSING ACCIDENT MANAGEMENT PLANS Cement GroutinD Aging NUR[G/CR%to LAllDRA10RY TI STING Or C(MINT GROUflNG OF f RACTURt S IN WI LDI D TUFF NUREGICFv4302 V02 AGING AND SE RVICE WEAR OF CHECK VALVES LISED IN ENGINEERED SAFETY FE ATURE SYSTEMS OF Cement Peste NUCLEAR POWER PLANTS Agmg Aspasments And Monitorrig NUREG/CR t 727 CHLOHIDE ON DJf USION IN LOW WAT[R TO-Metted Evalustone SOLID Ct MENT PASTt 3 NUREG/CR M12. DEGRADATION MODELING WITH APPLICATION TO i

AGING AND MAINTENANCE f FFECTIVENESS EVALUATONS Check Valve Aled Eevel NUREG/CH=4302 V02 AGING AND SL AVICE WE AR OF CHECK NUREG/CR !411: ISSUES AND APPROACHES FOR USING [OUIP-y4tyg g psty gN [N3 NrtRtp gAst rya g AtuRE SysT[MS Or NUCLE AR POWI R PLAN 1B Awho Aspsanents And Monitorwig MENT REUAfiluTY ALERT LEVELS Mm hautens Ausinary Feedwater

^

l I AN A ~

lE /C 01 EFi[ CTS CF PH ON THE R(Lt ASt:. OF RADIONU-ES I

RY DA A NR CLIDES AND CHL LAtlNG AGENTS FROM Cf MENT SOLIDifliD DE-BWR CONTAMINATION lON EXCHANGE krSINS COLLICTED FROM OP NUREG 1302 OFF SITE DOSE CALCULATION MANUAL GUIDANCE.

[ RATING WCLE AR POWER STATONS.

STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR BOfLING WATER REACTORS Gorene letter 8941' Supplement No 1 Chloride lon NURE G/CR 4561 V2 RIP 2 EVALUATION OF SEVERE ACCIDENT NUREG/CR 5127 CHLORIDE ON Dir rVSION IN LOW W ATER TO-RISKS. QUANTIFICATION OF MAJOR INPUT PARAMETE AS Emperts, SOLID CEMENT PASTES erminst Containment Loads And Mollen Core Contanrnant Circumferential Flaw NUREG/CR 5565 THE RESPONSE OF GWR MARK 14 CON? AINMENTS NUREG/CR 5592 ANAL YflCAL STUDIFS OF 1RANSVERSL S1 RAIN TO ST ATION DLACkOUT SEVLF4 ACCOENT SEQUENCES (FFECTb ON FRACTURE TOUGHNE% FOR CIRCUMFERENTIALLY NUREGICR %92 GENERIC RISK INSIGHTS FOR GENERAL ELEC.

ORIENTED CHACKS TRIC BOlUNG WATER RE ACTORS NUREG/CR 5702 ACCfDENT MANAGEMENT INFORMATON NEEDS Ctaos it Safe 4 System FOR A BWR WITH A MARK I CONT AINMENT.

NUREG/CR.4%e CLOSEOUT Of it BULLETIN 6442 F ALLURE $ OF GENERAL ELECTRIC TYPE HFA RELAVS IN USE IN CLASS 1E Bentonite Grosting SAFETY SYSTEMS NUREG/CR 5666 EFFECTIVENESS OF FRACTURE SEAUNG WITH BENTONITE GROUTING Closeout NURE G/CR 4666 CLOSEOUT OF IE BULLETIN 84-02 F AILURES OF Bolhn0 Water Reactor GENERAL ELECTRIC TYPE HF A RELAYS IN USE IN CLASS IE NURE G-1302 OFFSITE DOSE CALCULATION MANUAL GUIDANCE SAFETY SYSit MS STANDARD RAD.0 LOGICAL EFFLUENT CONTROLS FOR BO4UNG WATER REACTORS Genere Letter B241 Suppiement No.1.

Container Material NURE G/CR-4551 V2R t P2. EVAL U ATION OF SEVERE ACCIDENT NUREG/CH 5598 IMMERSON btUDIES ON CANDIDATE CONTAINER RISKS QUANilrlCATION OF MAJOR INPLIT PARAMETERS Esports-MLOYS FOR THE TUFF REPOSITORY.

E%ermmaton Of Conynment Loads And Molten Cao Containment interaction issues C#"lAln**"I NUREG/CR M6b THE RESPONSE OF BWR MARK ll OONTA:NMENTS NUREG/CR-45'41 V2R1P2 EVALUATON OF SEVERE ACCCE NT T"> STATION DLACKOUT SEVERE ACCIDENT SEQUENCES RISKS QUANTIFICATION OF MAJOR INPUT PARAMETERS Esports' NUREG/CP-5602; GENERIC RISK INSIGHTS For. GENERAL ELEC.

Determination Of Conwnment Loads And Motten Core Containment TRIC BOILING WATER REACTORS 6nteracton issues NUREG/CR-5702, ACCCENT MANAGEMENT INFORMATON NEEDS NUREG'CR 5630 PWR DRV CONTAINMENT PARAMETRIC STUDIES FOR A BWR WITH A MARK I CONTAINMENT, NUREGICR 5691 INSTRUMENTATION AVAILABillTY FOR A PRES-SUR12ED WATER RE ACTOR WITH A LARGE DRY CONTAINMENT Borehole Plug DURING SEVERE ACCIDENTS NUREGICH %84 ANALYSES AND FIELD TESTS OF THE HYDRAVUC PERFORMANCE OF CEMENT GROUT ttOREHOLE SEALS Contract Research NUREG4975 V08 COMPILATION OF CONTR ACT RESEARCH FOR CONT AIN Coco THE MATERIALS ENGINE ERING BRANCH.DIVislON OF NUREG/CR M30 PWR DRY CONTAINMENT PARAMETRIC STUDIES ENGIN( ERIN 3 Annual Report For FY 1910 23

24 Subject index toutpment ouenhcetion Coreoswa NUOLGeCH t727 CHL Of41Di lON D4iUSi0N IN LOW W ATE R 10 NJHE G/CH MAS SutWi hGE NCE AND HIGH TE MPERA1URE $1E AM bOI.lD LE ME NT F AST E S TE $1tNG Os CLASS 1E ELE C1hlCAL CAME S Crut E quipment Reliabluty NUHE G/CR 4W9 V01 N1 640HT CRAC6.5 6N PtPING AND f*NG NunEGICR Mit ISSUI S AND APP 40 ACHES 8 0H USING EOviP-WE LD$ Se%nnnual RePart Ma'ch Septemter 1990 tg N1 p[(gAgitiy y 4([ p1 g[yg(g NUGEGICl4 6128 E VALUAllON AND HEFINEMlNT OF LE/(HATE E SilMATION MDDE LS g y,ng NUW G/GRLE92 ANALYTICAL SfvDIES Of TRANSVE RSE STFtAIN m yM n

MSf@ M M PhWK Et FECTS ON FRACfunE TOUGHNESS FOR CiHCUMFEREN1 TALLY n iE S OF E VE N15 AND PROC E SSE S Af I E C11NG T HE PE f4F OHM.

Oh!E NTE D CRACF S ANL E OF GEOLOGIC ME POSl1DHtES Smested APubedes Crun Gt *wth NUHFG/Cf4-4fA7 V09 E NVIHONMENT ALLY ASSiS1E D CRACANG IN CA %46 AN IN E$ilGATION Or THE EFF ECTS OF THE R LIGHT W ATE R RE ACTOh5 Sc%ennoat heput Apm Septemter tW M AL AG43 ON THF F AE DAMAGEAhlLITY OF ELECTHiC CAHLE S NUMEG/CR 4%7 V10 ENVAONME NT ALLY AS$thilD CRACAING IN Lt i W Afl H RE ACTOHS Semiannual ReportOctoter 1909 Math NUNE G/C4 %47 FISSION PRODUC1 PLATEOUT AND LIF10FF IN 1HC MHfGR PRIMARV TYSTEM A FtEviEW Degr adetsort NUREG/CR Mit DEGRADAtlON h4DDELlNG Wi1H APPUCAllCW 10 Flow strettricetton AGtNG AND M AIN1E NANCE EF F EC11VE NE SS E V ALU A1)ONS NUFIEG/CR $4% ANALYSIS OF F L OW STRAllFiCATION IN THE SURGE LINE OF THE COMANCHE PE AA RE ACf DR Density NUNI G/Cf4 EM8 MECHANICAL CHARACTER 12AllON OF DENSELY Fracture WE LDED APACHE LE AP TUF F NUAEG/CR %83 LADORATORY 1ESTING OF CEMENT GROUTING Depressortsst6on Or F RACTUHES IN WE LDt D TUFF NUREG/GR447. FISSION PRODUCT PLATEOUT AND 38' Cr F IN THF MHTGR PRfMARY SYSTE M A REVIEW Freciure Mechantr.e NUREG/CR %47 FISSION PHODUCT PLATEOUT AND elf TOf f IN NUdI G 142fi V01 COMPILAllON OF RE POHTS F ROM RE SE ARCH lHE MH1GH PRIMARY SYSTE.M A REVIEW cAIPPOH T ED BY THE M AT E Hi ALS ENGWLE nttt3 fMANCH DfVislON Or ENGINE E RING 1965 1990 G/CR 5727 CHLORIDE lON DIF FUSION IN LOW W ATER-TO-WE LDS Sc% annual Report Ma ch Septemter 1990 SOLID GEMENT PASTES f UNEGICR 5128 EVALUAllON AND HrflNEMENT Of LE AA RATE ESTIMA160N MODELS ERDS NUREG 1394 Roi EMERGENCY RESPONSE DAT A SYSTE M ll HDS) actum Seanng IMPL E ME N1 ATION NUREG/CR %B6 EFF ECTIVE NESS OF FRACTURE SE AllNG W11H EiENTONITE GROUllNG Earthourke NUHEG/CR $$65 THE HIGH LEVEL VlBRAllON TEST PROGRAM hnal f racture Toughness p,pg,q NUHEG 1374 TECHNICAL FINDINGS RELATE D TO GENERIC ISSUE 79 An Evaluation Of PWR Reactw Vessel Therma! Stress Dunng Nal+

Efftuent Monitoring NURE G-1301 OF FSITE DOSE cat CULAllON l'A 'UAL GUIDANCE ra! Convection Cooldown ST ANDARD RADIOLOGICAL EFFLUENT CONMJLS FOR PRES NUHEG/CR 45tJ ESilM ATION OF FRACTUnE TOUGHNESS Of CAST STAINLESS STEELS DUHiNG THL AMAL AGING IN LWR SYS-SUR12ED WATER RE ACTORS Genenc Letter b9-01,Supp6ement No TEMS t4UREG 1302 OF FSITE DOSE CALCULATION MANUAL GUIDANCE.

NUHEG/CR4744 VD4 N1 LONG TERM EMBRITTLEMENT OF CAST

~

1 ST AND',RD RADIOLOGICAL EFFLUENT CONTROLS FOR BOtLING DUPL EX ST AINL E SS STEELS LWH SYSTEMS Semiannuai a

Report Octater 1968 March 1989 W AT E R RE ACTORS Genanc letter B9 01,Sappmmer1 No.1 NUREG/CR 4744 V04 N2 LONG TERM EMBRi1TLE MENT OF CAST Electric Cab 6e DUPL E K ST AINL E SS STEELS IN LWH SY ST EMS Semiannual NUREG/CR M46 AN INVESTIGATION OF THE El8 ECTS OF THER-Report.Apnl Septemter 1989 MAL AGING ON THE FIRE DAMAGE ABILITY Of ECTRIC CADLES NUHEGiCR 6592 ANALYTICAL STUDIES Or TRANSVERSE STRAIN EF FECTS ON FRACTURE TOUGHNESS f OR CIRCUMf ERENTIALLY Electrical Cable ORit NTED CRACAS NUREG/GR-56% SUBME4GENCE AND HiGH TEMPERATithE STE AM NUREG/CR-57?9 MULTIVAntABLE MODELING OF PRESSURE TESTING OF CLASS it ELECTRSCAL CAD!ES VESSEL AND PIPtNG J R DAT A Embrittlement Generne issue 023 NUREG'CR-4744 V04 N1 LONGAERM EMbFUTTLEMENT OF CAST NU4E G 1401 DRFT FC REGULATORY ANALYS$ i JR GENERIC DUPLE X S1 A'NLESS STEELS IN LWR SYS T E MS Ser%n. la' ISSUE 23 RE ACTOR COOLANT PUMP SE AL l'F LUl4E Dra t Report r

RotatOctotier 19BB March 1989 NUHEG/CH 4744 VC4 N2 LONG 1ERM EMOR 1TLE MENT OF CAST NUF E CR

67. COST /DENE FIT ANALYSIS F OR GENERIC ISSUE j

DUPLEX ST AINL ESS STEELS IN LWR SY ST E MS 3emiannual 23 RE ACTOR COOL ANT PUMP SE AL F AltVRE Report April SeNemter 1989 Gener6c lasue 079 Emergency Resporste Data System NUREG 1374 TECHNICAL FINDINGS PE LATED TO GENERIC ISSUE NUREG 1394 Rot JMERGENCY RESDONSE DATA SYSTEM (ERDS) 79 An Entuation Of PWR Reactor vesso! Thermal Svets During Nat+

IMPLEVEN1 AllON f a: Convucten Goodown Enforcement Actions Generic issue 130 NUREG-0040 V10 N01 Er# OHCEMENT ACTIONS SIGNtriCANT AC.

NUHEG 1421. REGULATORY ANALYSTS FOR THE RESOLUTION OF TIONS RESOLVED Qua'tedy Prope% ReportJanuaq March 1991 GENERIC ISSUE 00 ESSENTIAL SEHVICE W ATER SYSTEM F AIL-Engineering Sa'ety Fester

• System UhE S AT MUL TI UN!T SITE S NUREG/CR 4302 V02 AGtNG AND SERVICE WEAR OF CHECA VALVES USED IN ENGINEERED SAFETYTEATURE SYSTE MS OF Generic f asue 135 NUCLEAR POWER PLANTS Agmg Apessrrents And Mannonny NUREG'CR 4893 TECHNICAL FINDINGS REPOHT FOR GE NE RIC ISSUE 135 Steam Genwabr And Steam Lme OverNi issues Metra! Ev alushons g,

--n Subject inder 25 Genenc Setery im.

twH NUREG-t4M VH SlATUS OF SAUTY iSbVL S OT L ICI N$tV N MI G '{ R-45 4 III8M AT I N DI M CIUNI IOUGH'd U JI POM R PL ANT S Genene bakty IM6 CA51 l' AINLESb ST'.! LS DU4 NO THI HMAL AG'NU IN LWR 15 llMS Geologic Repository NunlG/E H ak? vel (Ndi )NMENTALLY ASMS1t D CHAC kfNG W NUHE G/CR 39f>4 %(2 TECHNid JE S 6 OR Di fiflMINWO PRCDAbtL.

(IGHT w All H Al ACTORS Sommal 74s.;vartApril S@ts.mte t949 P!L S OF EVENTS AND 8'HOCE SM 9 MI(CT Nfl 1HE PEm OHM NU4tO<Cn 4Mr V10 EwinONMt NVLL Y Ab95tlD CHAOING 'id ANCE Of GE OLOGIC HL POSITORT R Emes

• 4 A4hroat em LIGH1 w A i[R Rt ACTDNS Sem:4nnus' f%gv1.0ctate 19W. V.a'ch tion Ground Release NUm G'CH 46f.7 VII ( NVW74 MENT AL L Y AS$1SilD (I AEAtNG IN NUREG/CJ4 5661 L.CPA lt' VEL WA$1L P JURM TE Af 4 MXtl Dt-l ( HT W Ait i At ACTAS !>um. annual Row 1 Atwil 5.eptemter 190 VELOPMENT ANO TE STING Ngka }/($t.4744 VO4 N1 L E4G TE 50 E MBHtf1LE MENT OF CA5T

('UPLE A STA NLE% WTEEls IN LWH bi4TI MS f ee onWat Heavy Section Steet Technology Prtyprs'"i Rert (W ** 1W. Math t M9 NUAEG/CR 42tt V07 N1 HE AVY SECTON Of EEL TM4NOLOGf NurqG/Cn 4744 yo4 Ny LONG T[Ry [MFiqif tLI Mein or Cui PROGRAM Semien%el Pru; rete Report For Octater 100 Math DUPLE R ST A'Ni E SS STIELS IN LWR SYSit MS Serennuai 1970 lbportApril Seplemtmt 1DS H6grFlet t fluclear Weste l.epositorY

.at CNces Treach Alte NUREG/CR 55F APPnOAfMS FOH THE VAitEs. TON OF MODE.S NUKE G/CR b7tb MCD1L V ALOA hon AT H40 LAS Cf" #CE S USLV FOH PERFCOMANCE sSSESSMINT OF HG4 LEV ('t NUOW inENcs gitt AR W ASTE REPOSITOTES LeathlN High-Lev ei W e *te NUHTl/JH LM1; LOW LEVE L W 4TE SOUR 01 1EHM MODEL DE-NUREG/CR49^4 V02 TECr440UE S FOR DE TERMIP tNG 8'HOBADIL.

yg topMENT ANO f.SttNG ITIE S OF EVI% S AND N40GESSE S AF F FSTif R, THE Pt RTORM.

ANCE TiF GEQt.OGIC RE POSITORif S Suggested.\\ppenJet Leek Rete NUREG.CH 51H EVf EUATKt4 AND HL&'NLMt NT Of Ld AK RATE Hotan FacV1

[ $TIMATON VODW NUHEG'CR4L1 A 13YSTF#1'G PRUCESfi f ON bEVE LONNG AND ASSESSING ACCIOCH f VANAGEMEN1 PL ANS mi inunce, NUREG 0750 V32 le? IND9ES To NuCLI AH HEGULATORV COM.

Hydraulic Creducy rity 1

g g y,g y g g g g

14UH(G/CR 50U4 A64Y RJ AleD flELD TES'$ Or TPf HYDRAUUC ggjpg g g7gy, y.j) ggj ggg(ggg gggi,ggyggy )ggy;gggq gg PERFORMANCE OF CEMENT GR)JT DORE OLE SE ALS NURI G/CR 5u 4 Ef f EE 'lVENElt & /Raf'fURE SE A.iNG MTH SJMCES f OR FE bDU APY 199 8. Pagn 61173 p,UAEG0750 513 NO3 NUCL E AR Pf GULATOHY COMMISSGI IS BENTONITE GROUTING SUANCE S FO4 M ARCH 1991 Pages 17f,232 Wde@

NUHEG47f>0 V33 N04 NUCLE AR 9EG JLATORY CDMMISSION l$

"W # #

NUREG/Cf4 S/ ' A HYDROGLOLOGIC PEMORMAi40E Assf r$ MENT ANALYSIS OF THE LOWJ.EVG RAD'OWTIVE W AP E DISPO5 AL Uconne t we4 Report F ACILUY NEs 4 SHE F FILLD lLLitto.3 y9ggg,crQ 000 V10 f kt LICE NM E E vit4T REPOV (L I R)

Hydrmo6og COMPILATION For Mcnth Of f struay l?91 NUAEGi7A 5717 HYDRCrJEOLOGIC PERS$MAfCE A%EssulNT

1. 1. N# \\I' IU "

ANAL Mis OF THE COMMERUAL LOW.L EVEN R ADCAU.vf f

V[

L(I N E L'. E NT REPORT (LE RI W ASTE Ett POSAL F AULfiY NE AR WEST VALL{ Y,tjiW YORw.

p y g gyp,g g g g 399,E IE 11J.+tirt 44 02 NURE0'CR-4666 CLOSEOUT 011E DULLETIN 6402 F AILUHES OF 3gg gfog on,,,,ISkiON PRODUCT PLATECUT AND LIF TO7 F IN E O/CRM ;7: F t

GENERAL ELECTRC TYPE HF A RELAYS N USE i CLtSS 1E ggy gyggy g qcgg g CAFETY $(STEMS.

46 RAS L6ght Water Reactor NUREG Cfi 5300 V01 INTEGRATED RE UABIL11 Y ANL.IISK ANALY.

NURE G/C~t 4513-E STM A1.ON OF FRACTURE TOUGHNESS OF SIS SYS f fN flRRAS: VERSON ? 5 Rot m ace Marrni C. ST ST AINLE33 STETL A DURING f HERMAL AGING IN LWR SYS-t TiMS

~ hiformauor Dige64 NUHEG/Ulo4667 VD9 ENVIRONMENTALLY AS$1STED CRACK 6NG IN NUF4EG-13Mi V03 NUCLEAR RECWATORV CCMMISSON INFORMsp LIGHT W A TE R RE ACTORS Semiannual Recort Aprii4mtemter 1989 TON DICLST 1991 Edition NUREG/CR 4667 Vi0 E NVIRONMENTALLY AS$1STED CRACtfNG IN

'IGHT W ATER REACTORS Sennannual ReportOctot* 1989 March inspection E4.ide 990 NUREG/CR 5467; RISK-DASED IN9 ECf 0N GuCli FOR CRYSTAL NUREG/CR.4667 Vit ENVIRONN ENTALLY ASSISTED CRACKING IN RIVER UNIT f NUC I AR POWER PLA.4T LIGHT WATER RE ACTORS Semiannual ReportApoi Septamter 1990 NUREG/CR.5717 NCAAGING SyrtjER )NsetCTON GUIDE NUHEG/CR-4744 V04 NU LONG lERM EMDRITTLt'MLNT OF CAST DUPLEX ST AINL E SS STEELS IN LWR SY ST E MS Semiannual lor >Eachange Resh haste Report Octater 1968 March 1989 NUREG#CR 560*: EFFECTS OF PH CW THE RELEASE OF RADIONU.

NUREG/CR 4744 V04 N2 LONG TERM EMBRITTLEMENT OF CAST CLtDES AND CHELATING AGENTS FFOM CEMENT. SOLID 1FfED DE.

DUPLEX ST AINLL SS STEELS IN LWR S Y S TE MS Someannual CONTAMINATION ON EXCHANGE RFSINS COLLECTED FRCM OP, Report,Aprt$eptemter 1989 ERATING NUCLE AR POWEH STATlONS Loss OOCoolart Accident J-R Curve NUREG/CR 5395 Vn1 MATILOOP INTE GR AL SYSTEM TEST NUREG/CR 5729 MULTIV ARIABLE MODELING OF PRESSURE (M:ST) FINAL REPORT Summary VESSEL AND PlF4NG J.R DATA NOREGICR 5670 MULTILOOP INTEGRAL SfSTEM TEST (MIST) MIST F ACILITY FUNCilONAL SPECIFICATON LER NURE G /CR-2000 V10 N2 LICENSE E EVENT REPORT (LE R)

Low Levei ttadioactive Waste Disposal COMPILATION For Month Of February 1991 NUREG 1293 601-OuALITY ASSURANCE GUIDANCE FOR A LOW.

NUREG/CR-2000 b l0 N3.

LICENSEE EVENT REPORT (L E R)

LEVEL RADIOACTIVE WASTE DISPOSAL F ACILITY.

COMPILATON For Month Of March 1991 NUREG/CR-5713 A REVIEW OF ENVIRONMENTAL CONDITIONS AND NUREG/CR 2000 V10 N4 LICE NSEE EVENT REPORT (LE R)

PERFORMANCE OF THE COMMERCIAL LOW-LEVEL HADCACTIVE COMPILATON For Month O' Apol 1991.

WASTE DISPOSAL F ACILITY NE AR SHEF FIELDALINOl$

26 Subject Index NukIG/C H $79 HitmOGI OLCuic Pt 4F OsdMANCE AS$l %M( NT NUnEGrCH(47 IPsk H ASE D INsPI C 160N GuiDL (O4 Chi tr1 AL AN Al1 sis OF 1ML COMVL HClAL LOA ([ VI L H ADO ACilit RgiH UNIT 3 NUCLt Ah POAl 4 PL AN1 W ASTE DISPOSAL F ACILliv Ni A4 WL S1 V ALLf 4.N! W VOhk NUhl GIC H (42 SP' Cl6 IC IDPICS IN Si nl 8'<[ ACODI N1 M AN AGI -

Loelevel Wette NUklG/C h %B1 LOW LEV (L W ASTE SOUNC( T[hy MODtl DL.

PwR VE LOPMINT AND itStiNa NusqG t t i Os F S11E DOst CALCUL AtiON M ANU AL GU0AN;(

ST ANDAAD RADO(OGICAL [ t ? t Ut N1 GONf00LS FOR Pht S t

t R

4 OGE DL(GIC i[4F DhM ANr t A%f SSMt NT AN Alv$iS OF THE LOW LLvti R ADiOACthi n A51l D!SPOSAL NM G iW MWW f IWW M W D TO W W ed F AC1UTY NL AR LHI T Fl[LD, U POS 3 gy g, n g,,,g 9 3

j g

raf Gonveeton (bnihn M ARK l Containment NUht Gth M PWH dry CONT AM N1 PAR AMI thiC MMnE S NUPf G'OR t102 ACC1DL NT M AN AGI ME N' IN8 C'RM ATON Nt ( DS NN NL AN M NM*lONAUA IC Ab*lDb @ IHI FOR A N %R WITH A MAhr i CONT AINMLNT ANP1 Phi %UR;I[D n Alf R hl ACTO 4 NuhE Gil. %9 t INSiliUME NT ATION AVAIL ADIUTY I DH A PFil B-MHTQR NUHEG/Ch M47 F iSSON PS DOUCT PL A T E OUT AND til TOf F IN SUWlE D Mit 4 HE ACIL*R WitH A L A4GL D4Y CONT A!NVl NT THE MHTGA PRIMA 54v SYSitM A At MW J AtK M Vaht ACf4(NTS g

NUhE GIC81 %47 f lSSION PHDLitlCT PL A1( OUT AND ta' Toff IN THE MH1GH PAtM AHV SY5 tim A RL%"Ei%

8 8t+e9e BMP' t' NL Nf rFCR ' ti ? PAC AAf JNG SUPPue H INSPL CilON guide NJhE G!CR SM$ V01 MUL1WW IN1[ GR A( $ /l f t M 1L SI pertomerere AtmsmerV ftMT) FINAL Hf POAT Summa's NU4E G'C R M U ADH4 ACHLh IOH THE V AlIDATION Or MOD [ L$

NUHL G/CH %70 MULTkCOP INTEGR Al SYSTIM 11 Si t%5f Mit (151 D 8 00 PLRFO4MANCE AT St PML NT Of HIGH Li vil NUCtl.

t F ACILilY FUNC10NAL bPL ClhCAflON gg ggggg ytppgigggt g

1. ad 11 ContMnment NUREG/CR LMS THE HESPON$t OF %4 MAAk ti CON 1MNM[NTfi 1 N40 Hf GUL A10Hf AGtNDAtha1mty TO $1 AflON DLAckOU1 SET (HE ADCIDLNT St OUl NC[$

g g

y g

Mottel Val 6dation NUH1 G/CR 5716 MODFL V AUDAT ON A1 THE i% C AUC[ h I'P' NUKE G/CR %% TR HIGH Lt Vit VtDHA10N itst PHOGRAM e inal TR( NCH SITg Opc 1 Muttttoop flitogral lystem Test NUH( G/CH t3185 V01 M JLT hDOP iYlGRAL SY STE M T E ri -

Pte CracHng

MlST) FINAL HE PORT Summa NURE G 0975 v0P WMPIL AllON Of CONTR ACT HL St ARCH 'OR NOHI G'CR *C0 MJL11L OOP IN'yT[GH AL SY51[ M TE ST (M ST) M

ST T HE Mall HL AL S E NGlNt [ HING Dh ANCH DivtSION or F ACIUTY f UNCTONAl SPECIFICAiON lNGINE FRING Anw be vt iof F Y t943 NAC 3ulletin $444 Pipmg NUREG/CR 5706 POf f N1IAL SAf ETY AlL All D PUMP LOSS AN AS qy;4[gfgp 49) ygg qq g,ppy (pAgy3 gq pipjqq Aq3 p,yggg SF SSME NT OF INDUSTHV DA1 A NHC D#chn t+04 A t LDS 'mannual hetoi M irch SePtemt.cr 1W3 D UIG O 6I29 MullAb'"Ull MODIUNO OI INIbbUNI Navler Stoke NbbILANU #

• NUAIA NUREG/CR S456 ANALYS!S OF F LOW $1 H A11F IC AfiON IN 1HE SUHGE LINL OF THE COMANCHE PE AA Of ACTOh Pressure Vettel NUREGt97b VDB COMPILATION OF CONTRACT RESEARCH FOR Neutron NUREG/CH %46 1RANSPORT CAL CUL ATIONS OF NEUTRON IHf MAIINAlb ENOhEIkNO NMNCH U'V! BON T R ANSMiSSION TH40VGH ST(t L USING I NDf, B-V Ri vtSE D

( NG'NE E RING Annuai heport f or F v 1990 NUht G/CH 4219 V07 N1 HE AVY.Sf CTION STEEL ffCHNOLOGY LNDFiB V.AND ENDF /B Vi lRON f V ALU AT ONS PHOGR AM Semiennual Prc yesa hepart F cw CKtot.cr 1989 March 1940 Nuclear Regulatory Research NUREG 1266 V05 tMC SAF ETY RE SE ARCH IN SUPPorif Or REGU.

NURE G'OR %40 1RAN5POH1 C AL CUL AT ONS OF NEUTHON LAf TON F v 1990 1 R ANSMiSSION THROUGH STEEL USING E NDF /B V.hi vtSE D ENDrtB V.AND LNDF /D V4 IRON ( VALUAllONS Nuclear weste Repoelto'Y NUHE G'CR 's729 MUL T IV Ahl AI".E MODE LING OF PhE SSURE NUREG'CR 6440 ChiilCAL ASSESSMENT Or SELSME AND GEOME -

VE SSE L AND PiPIN's J R DAT A CHANIC3 LITERATUAE hi LATE:D TO A HtG,4 LL VEL NUCt( AR W ASTE UNDERGROUND HiPOst10RY Presourtsed Thermal Shock NURI G'CH4677 A UN!F if.D IN1t hPRE T A10N OF ONE 8~lFTH TO Office Of The inspector General FUL L SCALE THE RMAL Mix!NG f RPf RMEN15 kl L ATED TO PHLS-NUREG-1415 V03 N32 OF FICE OF THE INSPt CTOH SUM D M HW M%A GE NER AL Semiannual ReportOctober 1M3 March 1991

1. • *""'

• d * * N #

Of tstt9 Oone Calculation Manual NURG 1M1 OFFS!TE DOSE CALCULATION MANUAL GuiDANCf NUhE G 1301-Of f Silf DOSE CAL CUL ATION M ANUAL GUIDANCE AN RADOLO UW N

S F OR NS ST ANDARD RAD *0 LOGICAL EF F LUL NT CONTROLS FOR PRE S k"#

• W N *CN O*"

W " M*""I

• SURIZED W ATE H RE ACTORS Genenc L etter 6941 Sappicment No t

NUREG 1374 TICHNICAL FINDrNGS ht L ATED TO GINLRIC ISSUE NURE G 1L2 OFFSITE DOSE CALCUL ATON MANUAL GUIDANCE U ^" N"abun Of PWH Reactar Venw Thermat St$cu Dunrg Nat#

ST ANDARD AADOLOGICAL EF F LUENT CONTROL $ FOR BOIUNG

'*' M * * " O *

• HTE H RE AClORS Genent ietter 6 01.S4peomont No 1' NURE G'CR %30 PWH DHY CONT AtNME NT F ARAME THIC STUDil5 NUH[ G/CR 5M3 NE L AP5 TH[RMAL H1'DbAULIC AN ALYSiS OF THf Operational &afety WNPt PRE SSURt2E'D W ATIH RE ACTOR NUMEG'CR 5742 V01 FEAS@LITY ASSESSMENT Of A kSA DASED WEO MD1 INSf HUMI NT ATON AV AIL AbillTY FDr.

'Ro S.

AP5 AOACH TO TECH 4 CAL SPECif lCATIONS E secut~e Sarrrtar I4J4f GtR $142 V02' F L ASeUTY ASSESSME NT Or A HGr eAkt DSuhtl( D W AT L R RE ACTO 4 WiTH A L AHGE DRf GONT AINMt NT APPROACH TO 1ECHNICAL SPECirICAtlONS Mam Report DvNNG SEVE DE ACCIDEN15 i

PHA Proc eeding NUAEG'C4 feXO V01 INTEGRATED RE UAB:UTY AND RS ANAlv.

Nuke G tP 0114 VD1 PHCCE t DINGS Of THE [lGH1f I NTH W ATE R S15 SYSTEM pnHAS! VE HSON 2 5 Retvence Ma%at Al ACTOR SM Eiv INr ORM ATON MEE1tNG

Subject index 27 94 PHI G TP et14 VN Nat [ DtNGS OF T HE E OHTLI N1H W Ali H I4elay Hi AC T OH $ f "T v int (*MA10N Mi l 11N in NahtGiH4 W Cid$ LOUT 05 i Lill!N 35402 F AIL Uht 5 N NUH( G / CPS 4

'M 6%K (( DINGS Of THE ItGHillNIH W AIL H C [ N[ H AL ( L ( C14 HG T V P O \\ %.A % b 14 Ubi IN (LA M 'I f ti AC 1DH SAS ( Y v INFOHM A1 DN Mt i 1'NG SAF i1Y b)bliVh l' ump Rehet@t y NUHIG/C H ND6 POf( NitAL SAF(l v HI L Alf D 8 UMP L OM AN Ab gyngarcH pa; got p ( At,twiy A%( f Mt N1 OF A HILA b Abt D t[LLM[ NT Of INDU$ f HY DAT A NHO HAtm t*ta APPHDACHTO1(t:HNK 4 ( %Dt Cif lC A1KWS t septeve %mma'y NUH[ G/C H 8.747 VO2 F[ Witti fil Ah$f $ WI,NT Of A Hlb> IL Att D lusitty Attuf ente APPHO ACH 10 f((4 M At ElO # lC ATIONS Mmn Howt NUH[ G 170) hcl QUAUIV A$$UHAT E GuipAy7[ 6 (in A { OW LI V{ L HADiDACilVL W ASTI DISPOSAL 8 ACillit Rete 64tiRepod NU16 0-14Tf; yet MMF1L Af 0N $ ht POR'S $ DOY Hi s[ ANCH

ggppyg,

'b L

• NUNE W CH ' WI HI L AP5 TH( HMAL HYDH AULIC ANAL Yht$ Of 1 Hi

^ " NN '

INWI W"

l WND t PHl 8 Suit?[ D W Afl H Hf AC10H Mesidual Heat Remte el ggq gg W H( M H W H @AL

[ h MB A% n V n W M-NURE Gd 40 5Af L TV L VAL UA15GN HL PUHf HI L All D TO THt Phi U N UI N

'A # U M N C#

'W

-1Y D.hKAN (4 THL ST ANDAHD NUtal AH itt AM LUPPLY Fi T 4 UrnT[.M Hf6AH $P19 (h ht Nu % Mt (WpWg g

i 46.tte r, Gorpa pun. km I p

g jg p p

.gg Radioactive Weste lily l H UNA : NW f \\h POWf PI 1

NUH[ G;t 84 5714 H VD40Gl Ot OGIC Pt RF OHM AN ( A%tMMiNT ANC Yfv5 Of THE LOW Livfl RADiOACTivi WAbit DISPOSAL Hish Analysis $ystent F A(W *Y NE AH SHl f f l[ LD. alt nog NUHL G CH *MJ V0' IN11GHATED HillAbitth WD Ru ' AN\\W.

515 S1 S" M iT '.51 VI HSION " f He' cwa 'tav el NuriGMH moi ( F F FC15 OF PH ON THE ht t[ Att OF HApiONU.

Rl9h Redot'lan f LIDE b a 4D CHE L A11Na AGE N15 FHOM Cl Mt N1 LDL ID4 4 D Di-NUHf (Mt W4 ANAthis O' F+ A HiDUC1 DN Iet Ahp(3 JON1%I 4AflON ION I

• CHANGE ht t1NS Colll(il D f HOM OP.

Pill D TO $HAPI D ( %f NilAL Li nitC l W t T F H SY 61, W AT 4 HAT:% NUCLt AH POwt H $T A1:ONs MU;11UNt*S!ft5 Redmtw#se Transport Roth Mef' 4 #c M $c G/CH 570 A HEitt W Or (N0HUNMLNT AL C ONDitlONS AND NUHf GQ 4 5440 (811 CAL W s5MtNT Di SISMC AND M OME-Pt HF ORMANCE OF THE COMME RCIAL LOW Livil HADIDACifvt CH ANCL L11L F4 A1Uht HfLAfED 10 A } )tGH t i Vi l NUCLIM W ASit (n5PO5AL F ACILITY NE AR SHI & I 4 L D it t INOis M A STL UND: HGHOUND HL P; SITDHV NUHE G/C84 5714 HTDHOGf OtOGIC It HF OHM ANCL A%E % MINT ANAL 4 5'S OF THE t OW Lt vl'L HADIOACityt W Asti DrLPOLAt fl le F ACittf Y Nt. AN NHI F rit LD tt DNDIS NUA G tA04 vt0 N NOC HE GLt ATOHV AA t4DA tAadsdir NUHE G/GN U37 H f DHOGl OLOGIG PE HF OHM ANCE A%L 55MI NT

%yut.lano n Man h 1W1 AN AL Y sis Or l if 3OMME HCI AL LOW l.L Vf L H ADtOAC11VL W ASIL DISPOSAL F Af ILITV NE AH WE ST V ALLE V.NE W YOHA SQUtHT Cenpu et i sde NUilf U/LH 5 @ f V At U AliON AND HC FWL VI Hi Of Ll M H t i Reactot Att6 dent g siiM AliON pqpt t s NUNIG/CP.0114 Voi PHOCF iDINGS Of T H E IGHTIi N1H W A1i H Hi AC104 SAF t TV lN6 OHM A TON Mt [ TINA hat ty a lluellotlFMo$

NUHt G'CH f 692 GI NL HIG HT % IN5tGH f 5 T OH GI NI H AL l ll C POH! M M 04 3AFi f t f VA lA:

4 HliOOT $1LAT D 10 THE

'HiG ODeLING W ATE H Hl.AC10HS OPf H AYtON Of D4 ABL ' a f iN T t >N i CL E AH POM H PL ANT.UN110 Heactor Component NURE G'CH $611' ISSUE S AND APPHOACHl5 F OR USING f OUiP-N "E G 0 4 306 5 Art 1Y (.v ALUATION uf "0H1 HEL ATID 10 THE MLNT hiLIABILITY Alf hi llV(($

0 H A. t( 4 DF W AT f S li A t JCLf AH PL ANT,UNii5 1 AND

? Dodel Nm 60 & 3 Ai150 3s 1 l snntLwe Vanev AuttmM Ni G 4 1 [

FC HE GUL ATOH V ANAliSis (OH GE Nf Hic

'50 M1 mesting 155UL 23 HE ACTON COOLANT DUMP SE AL F AtLUHF tha't Hewrt His HI NUE SiSit M F $ t BP % twet No g%g e

x waM 4 4.I NUh( GiCH tifJ COST /0EN(LIT ANAL Y$1$ f OH GLNE HIC 15SU(

D HL ACTOR COOL ANT PUMP $1 AL F A4UHf gmp,,

Reactor Core NUhlG 14M Vfl M AIL OF S Afl TV t%UI S Af ilC( NSE D NUHf GICR M2f5 ANALYS15 Of FUSA HIDUCWN ME A'l NES Ap.

WT H MM U N AedLaMyle g PLIED TO SHARED ESSE Nt6AL $[HviCE W All:H Sffi us AT t

$stery R warn MULTI UNIT SIT [S f UHEG-1?t4 Vy NHC S AF E ? Y HE SE ANCH iN SUPPOHf OF HLGU-Reactor Maintenance L A '154 i Y i WO NUHLG/CH %12 Of GRADATION MODL A3 WAH APPO Al N TO Beal f allute AGING AND MAINTf NANCE f b rity[N $$ li ALUAllON3 NUH[G 1401 DMT Fj HF GUL ATOH f AN AL Y sis I DH Gt NE HIC Renttor Preature Veteel 6; SUE n F.L ACTOH GO4LANT l' UMP $f AL F AILURE Ota't Report NUHf G 14?6 V01 CfWPIL A ' ION OF HEPOHT3 FROM H15( A t1CH F o' C.nmment SUPPORTED By THE MATEHtALS

[NG m tscN; NUW G/CH $16? CO ). / EE NI l li A.AlfS6 F OR GENT HIC ISSUf BH ANCH DM$ ION ) iN@NElHING iiM5 tim n H0 ACiOH COOLANT PUMP Lt AL i AllUHE Reactor Vessel Seitm6s NURE G 137a le CHt GAL F tND'NGS Pt'l Ait D TO LE Nt hic ISSUE NUHI GtH $443 CRITICAL AS5t %ML NT (v

.f 6MtC AND GLOME-79 An E.sAate Of PWR Heactw Veuei Themei j veu Dunry Nata CHANtOS tillH ATUHf HE LATE D TO A e%H L EVE L NUCLt Ak rat Con rebon L oloomm WGTE UNDI H3 HOUND HE POSl10HY v

Regu:ator igenda feestmic t ffect Ni f i G4tJ6 1 10 Not NHC Rt f.JLATOh r AfO9AQuawr NiW G'CH %fo THE HIM LE VLL v1DR ATION 11 ST PHOGRAM f anal Reg 6xUnvy MawtiIW1 H pt n

s.

s.

-n

'3 Subject index Seismac Monitortry Tectonic Study NJRE G'CR %2e PE NNSYLV AN!A SE fSViC MONITORM NETWOF4 NURE G'CR %28 S ENNSYLVAN A SE 1SMIC MDN:TOhiNG NE TWOR*

AND RELATE D T ECTONIC STUDIES rinal Repm AND RE LAT ED TECTONIC STUD'E S Fma: Report

$ntomic Program Tensile Strength NUHEG 0075 S34 SAF E TV E VALUATION PEPORT REL ATED TO THE NUREGeCR SMB ME CH ANCAL CH AR AC TI R'? AT ON OF DE NSE L Y OPE RAtlON OF D ADLO CANYON NUCLE AR POWER PL ANT.UNilS WE LDED AFACHE LE AP TUF F i AND ? Dxtet Nas 50 275 Ard SO 323 FaAc Gas And Electoc Companyt Thermal Aging Nus,EG/LH 4513 E ST IM A TION or 6 H ACT URE T OUGHNE SS 05 Service Water System CAST ST AINLESS STEELS DUHING THE RMAL AGtNG IN LW84 SYS NUREG 1421. 84E GULATORY ANALYSIS 4 0R THE RESOLUT60N OF TEMS GENERIC iS5UE 133 ESMNhAL SERV 6CE W ATEP DSTEM F Alt-NURE rdCR-5546 AN INd STIGATION OF THE E F F E CT S Of T HE R URE S AT MULTI-UNIT SITE S MAL AGIN3 ON TH[ FIRE DAMAGE ABlUT Y Or ELECT HFC CABL E S NU9E G 'CR th26 ANALYS;S OF ArSK REDUCTION MEASURES AP-PLIED TO SHARED ESSENTIAL SE RiiCE W ATER SYSTEMS AT Tlarmal Mining MULTibN;T SITES NJRE GiCR %77 A UNTIED INTEHPf4ET ATON Or ONE FIF TH TO F ULL SCALE THE kMAL M > LNG E XPER'MENTS RELATE D TO PRE S Severe Acc6 dent S'JRi?E D THE RM AL SHOCK NURE PCR45$1 V?R1P2 (T ALU ATON OF SEVERE ACCID [NT 841% S OUANiir ICATiON OF MAJOR 4NPUT PAk AME TERS E aperis Therma 6-Hydraulac EMermmation Of Containment Lbads And Maiten Core Contamment NURE G/CR %63 RELAP$ THERMAL HVDRAULIC ANALYSIS OF 1HE mWactKm l& hues WNP1 P9ESSURi?E D W ATE R RE ACTOR NUNEG/GR 65t.$ THE RE $DONSE Of PWH M ARK ll CONT AINMENT S TO St ATCa DL ACFOUT S( VEDE ANDENT SECUENCES Thermoluminescent Don 6me'er NUREG/CH $655 SUWEHGE NCE A ND HiGH T EMPERATURE STE AM NUREG 0637 V10 N04 NRC TLD DihECT RADIATON MON!TOTNG TE STING Or CL ASS if ELECTMAt CABLES NETWORK Pryess Report Octater Ehember 19M NURE G'CR 56B2 SPECIHC 1OPICS IN SEVERE ACCIDE NT M AN AGE -

Mi N1 Title Ust NURE G/CR $691 INSTHUMENT ATON AVAILADIUTY FOR A PRE S NUREG-Otto V13 N12 TITLE UST OF DOCUME NTS MADE PUDUCLY SURIZED W ATER RE ACTOF WITH A LARGE DRY CONT AINMENT A v AIL ABL E F ebruary 1 28.1991 DURING SEVERE ACCIDENTS NUREGM40 Vt3 N33 TITLE UST OF DOCUMENTS MADE PUDtiCLY

1. VA'l#Ull M#'hi31 199I Stainless $ teel "I

"3 #

Ub b

NO NUhE G/CR4513 E STIMATION Or 4RACTURE TOUGHNESS OF

^# # #

CAST ST AINLESS STEELS DURING THi nMAL AG1NG IN LWR SYS.

II MS Transport Calculation NUTG /CR 5648 TRANSPORT CALCULATIONS OF NEUTRON Stattori Bisckoug T R ANSM!dslON THROUGH STELL U9NG E NDF/B V REVISED NURE G 1401 DAFT FC HE GUL AT OR Y ANALYS;S FOR GE NE RIC B $teamGenerator IN UANO

$ YI I

ISSUE 23 RE ACTOH COOL ANT PUMP SE AL F A LURE D'att Ryert Transportation Package NUHEG/CR $717 PACKAGING SUPPUER INSPECTION GUIDE NUHEG 0975 V0e COMPILATION OF CONTRACT DESE AaCH FOH

"^

t E C 2 ANALYTICAL STUD ES OF TRANSVERSE STRA4N E INEEF N al R I c i rF 1 90 EF F ECTS ON F R ACTURE TOUGHNESS F OR C4HCUMf ERENTIALLY NPEG-1426 V01: COMPILA1 ION Or HlPOHTS F ROM RESE ARCH ORIENTE D CRACAS h..PPLR T E D BY THE M AT E RI ALS ENGINE ER'NG DRANCH DivislON OF E NGINE F RING 1965 19M Tube Rupture NUHLG'CR 4B33 T E CHNICAL. F INDINGS REPORT FOR GENEhiC NURE GrCR-4893 TE CHNICAL FINDINGS Rf PORT FOR GE NE RIC 1%UE 135 Steam Generator An15taam Ur.c overMi two NUHE G /CH'5M VO I. MULTiLOOP INT E GR AL SYSTEM 1EST ISSUE 135 Steam Genorator And Steam Line OverNI isses (MISI) f IN AL REPORT Summary NUREG'CRA670 MULTILOOP INTEG4 AL SYSTEM TEST tMiST) M!ST TuH Repository NURE G/CR 5$98 IVMERSION STUD!CS ON CANDIDATE CONTAINER F ACluTY F UNCTlONAL SPECWICATION ALLOYS FOR THE TUFF REPOSITORY Stratification NURE G 'CR 4677 A UNIFlED !NTERPRET ATION OF ONE FIF T H T O V'" dor inspection TULL SCALE THE RMAL MnlNG f >PE R:MLNT S RE LATE D TO PRE S.

NUREG 0040 V15 Not UCENSEE CONTRACTOR AND VENDOR IN-SURi?ED THERMAL SHOCA SPE CTION STATUS REPORT Ouarledy Hepoa January Mrch f

1991(White Rcon I

$ tress Corrooton Cracung l

NUREG/CR-4667 V09 ENVIRONMENT ALLY ASSISTED CRACMNG IN VD'ation UGHT A ATE H RE ACTOHS Som annua! Report Apni Septemt,or 1W9 NUREGICR $5e5 THE HGH LEVEL vlGRATiON TEST PROGRAM Final NUREG!CR-AM7 V10 ENViHONMENTALLY ASSISTED CRACMNG IN Report LIGHT W ATER RE ACTORS Semtannua! Report.Octaber 1989 March Watet flow 19w0 NUHE G/CR-4667 Vi t E NyiHONMENT ALL Y ASS!STED CRACMN3 IN NURE G/CR 4716 MODE L V AUDAT ON AT THE LAS CRUCES LIGHT W AT E R FIE ACTORS Semiannual Report. AW Sartemt er 19e TRE NCH StTE NUHEG/CR 5%B IMMERSION STUD:E 5 ON CANDIDATE CONT AINE R ALLOYS FOR THE TUFF REPOSITORY.

Water Reactor Safety NURE G 'CP-0114 V01 PROCE EDINGS OF THE EIGHTEENTH W ATER Surge Une RE ACTOR SAFE TY INFORM AT ON MEETING NUREG Dt 5456 ANALYSIS OF FLOW S T R AliFICATION IN THE NURE GiCP 0114 V02 PROCEI DINGS OF THE EIGHTEENTH WATER SURGE LINE OF THE COMANCHE PE AK RE ACTOR RE ArTOR SAF ETY INrORM ATION Mf ETING NUhEG/CP 0114 V03 PROCE E DINGS OF THE EIGHTE ENTH WATE R TLD HL ACTOR SArET) INFORMATION MEETING NUREG OB37 V10 N04 NRC TLD DIRECT RADsATION MON' TOR!NG NETWORA Pryess Heport Octottr-Ducember 1990 Welded Apache Leap Tuff NUREG'CR 5668 MECHANCAL CHARACTER!?ATION OF DE NSE LY T echnical Specthcations WELDED APACHE LE AP TUr F NUREG /ER 5742 VO) FE A$iBtUTY ASSESSMENT OF A RtSQASED APPROACH TO TECHNICAL SPECIFICATIONS E secutwe Summa Welded Tuff NUREG'CR 5 742 V02 F L ASIBluT Y ASSE SSMI N1 OF A R!Sk b Ag;ED NUREGrCR5fra LABORATORY TESTING Or CEMENT GROUTING APPFtOAC 4 TO TE CHNIC AL SPECIFICATONS Mam Hepart OF FR ACiUPES IN WELDED TUF F

NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar.

ranged alphabetically by ma or NRC organizations (e.g., program offices) and then by sub-sections of those (e.g., divis ons, branchos) where appropriate. Each entry is followed by a NUREG nurnber and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

ADVISORY COMMIT'TE t N

()tVISON OF i NG!Nt i HING (DOS 1 P 704 01 ACHS ADV60HY COMW11t E ON HE ACTOR SAf LGUAHDS NUHlGW76 V0B COMPil AllON Of CONthACT H(St AHCH f Dh NUREG 11?S V12 A COMPitATON N HI POHTS CW THE ADVISO THE M Afl Hi AL S l t4GiNi l HING BRANCH DIVISION Of HV COMWTTEE ON HEAC104 SArt'UARDS 49W Annuet

[ NTNT f HING Annuel Hegot f or i V 1990 t4UHf G 14?6 V01 COMPILA10N OF HiICHTS F HOM Rf St AHCH OFFICE OF iXtCUTIVE DIRECTOR FOR OPERAflONS (EDO)

SUPPOH1('O BY THE MAf t HiAt 5

( NGINt litWU Ht GION 1 (POST 820201)

Im ANCH DtilSON OF E NGINF !4ING 1905 19W NUHE G 0B37 V10 N04 NHC TlO Dint C1 RADIATON MONtfOhiNG DhnbirW of' SAr t TY iSSut Ht bilt utON (W;51 M07171 NE TWORT ( Progress Honort Octat.coDecomte 1940 NUNIG 1314 T E CHNICAL 8 INDWGS HL L All D 10 bl Nt HlC 1%Ut OFC OF ENFOHClME NT (POST B704131 79 An t valuation Of PWH Henctor vessel Therma! Ltic66 Donng NUHE G-0940 V10 Not E NIOHCEME NT AC10NS SIGNIFIC441 AC-Naturs Gonymtenn Cmiden TONS HE SOLVED Cu lui, Prayets Roport January March 1991 NUHt ts 1401 (>Hf t F C Hl GUL A104V Af4ALYb!$ ION GI NtHIC ISSUE F3 hl ACTOR C(X3LANT PUMP SE AL $ AILUH[ Drott Hoport EDO OFFICE OF ADMINISTRATION (PRE $70413 & POST 990706)

F or comment DIVISON OF F REE DOM OF INFOHMAilON & PAluCATIONS siRV-NUHE G 1421 ht GUL ATOHY ANAL YSis FOfi 1HE f ttbOLUilON Or ICE S (POST 190205 GE NC HIC ISSUE 130 E SSE Ntl At SE kVICE WAT[H SYst[M NUREG 0540 V13 No? TITLE LtSi OF DOCUME NTS MADE PUBLIC-F AILUnr % AT MUL TI UNtf Sill S LY AVAILABLE Fet,ruary 170.1991 PRDbAulustic Ht$k ANAL vFab itHANCH NUH0G 0540 V13 NO3111LE LIST OF DOCUMLNTS MADE PUDLIC.

NUHE G/CA SD0 V01 INflGLAT[D HILIADiL11Y AND HISK ANAL-LY Av AIL ABLE March 131.1991 YSIS SYSil M (IRRAS) VL HS404 ? 5 Heteren(e Manual NUREG 0$40 V13 Nod TITLE LIST OF DOCUMEN15 MADE PUBLIC-LY AV AILABLE' April 1-30.1991 (DO OFFICE OF NUCLE AR Rt ACTOR RIGULATION (POST 4/28/bo)

NUREG-0750 V32 602 INDEXES TO NUCLE AR REDULATORY COM PHOGRAM M ANAGL Mt NT. POUCY Of VL LOPMLNi & AN Alv blS MISSION ISSUANCE S July-Decemta 1990

$T Af F (POST $70411)

NURE G 07DO V33 t402 NUCLEAR HEGULATORY COMWSSION IS NUHEG-143$ V02 ST ATUS Of LAF E TY 1%UES Al LICENS(D SUANCE S f 04 F EtsRUARY 1991 Pa es61-173 PO*EN PLANISU"'TA1U% OfemoNed baiety issues NUHE G.1435 V03 S bAFETY ISSU[S At UCE N$lD NUHEG 0750 V33 NOJ NUCLE AR HL ULATORY COMWSSION IS.

SUANGE S FOO M AHCH 1991 Pages I'5 732 POWE R PL ANTS Genonc Safet tasuen NUREG-0750 V33 N04 NUCLE AR HEGULATOHY COMMSSION IS (ho ))L

^

VA[U ll1"RELAfl0TO

$F Y

THE OPE RATON Of WAf f S DAR NUCtf An Pt ANT,UNtis 1 AND NUREG 36 V10 41 NHC E ULAl OR Y AGENDA 0u:1 911Y peport. January March 1991' P D%Aet Not W390 And !.0 391 (1ervetiboe Valley Authority)

DIVISION OF HE ACTOH PHOJt CIS tilWV (POST 9012166 EDO OFFICE OF THE CONTROLLER (PRE 820418 & POST 990205)

DIVISON OF BUDGET & ANAL vbi$ (POST Sa0205) 1HE OPER A tlON OF DiABLO CANYON NUCLEAR POWER NURE G-1350 V03 NUCLE AR HEGULATO4Y COMWS$10N INFOR, PL ANT.UN1151 AND 2 lbc.ket Nvt 50 ??S And 60 323 (Pach Gas MATON DIGEST 1991 E$ ton

^

DW DA ( Hl ACTORS & SPtCIAL PHOJECIS (DOS 1 EDO O FICE FOF, ANALYSIS & EVALUATION OF OPERATIONAL G[f413 SAF E1V EVALUAllON f4EPOA1 HE L ATID TO THE f4 OF FICE FOR ANALYSIS & EVALUATON OF OPE RATIONAL DAT A, DI.

CMARY DES 6GN OF THE 6' ANDAHD NUCLE AR Sit AM RECTON SUPULY HEi l RE NCE SYSTE M nESAH SP/90 Dxket No-W NUREG 1394 RO1 EMERGENCY DESPONSE DAY A SYSTEM (ERDS)

D! visit,NW M'OF*"f**e 06ecinc Coporehort inc )

HEAC10H INbPt C160N & hAF IGU ARDS (POSI typlE MENT ATION 87D411)

EDO. OFFICE OF NUCLEAR MATERIAL SAFETV & SAFEGUARDS NUNEG-0040 V15 Not-UCE NSE E CONTRACTOR AND VE NDOR IN-DIV'SION OF LOW LEVEL WASTE MANAGEMLNT & DLCOMWSSION SPE CTION STATUS RE PO"1. Quartetty Relot, January March ING (POST 8704133 1991 EWNte Dooy NUREG 1293 F401. QUAllTY ASSunANCE GUCANCE FOR A LOW.

DIVISON OF HADIATON *ROllCTION & E MERGENCY PREPANED.

LEVEL RAOCACTIVE WASTE DISPOSAL F ACIUTY NESS (POST 87N uj NUHt G 1301. OFF SITt. DOSE C ALCUL ATON MANUAL GUIDANCE U1 NUCLE AR REGULATORY COMMISSION

?f ANDARD RADOLOG6 CAL [FFLUENT fi)NTROLS F OR PRES, OFFICE OF THE INSPt CTOR GE NERAL (POST 190417)

SURllED A ATER REACTORS Genenc Lener B901, Supplement two NUH E G-1415 V03 NO2 OF FICE OF 191C INSPE CT OR 1

GENERAL Semsannual Report Octote 1990

• March 1991 NUNEG'1302 OF F Si1E DOM CALCULATON MANUAL GUIDANCE-STANDARD RADOLOGIGAL EFFLUENT CONTROLS FOR DJit-EDO OFFICE OF NUCLE AR REQULATORY RESE ARCH (POST 820405)

ING W ATE R RE ACTORS Gerenc tetiw 89-01.Suppian ent No 1 OF FICE OF NUCLLAR REGULATOHY HESEARCH (POST B607?N RISK APPLICAllON BRANCH NUHEG-1?66 V05 NRC SAFETY RESEARCH IN SUPPORT OF REG.

NUALG/CR 5602 GE NL HIC RISK INS GHTS FOR GENE RAL E LEC-ULATON FY 1990 ThiC BOILING WATE R RE ACTORS 29

1 9

4

NRC Originating Organization Index (hlternational Agreements)

This index lists those NRC organizations that have published international agrooment re-ports. The index is arranged alphabotically by major NRC organizations (e.g., program of-ficos) and then by subsections of thoso (e.g., divisions, branchos) whero appropriato. Each entry is followed by a NUREG number and titio of the report (s). If further information is needed, refer to the main citation by NUREG number.

There were no NURf 0/lA reports for tNo quartet.

31

l 1

i E

t

I NRC Contract Sponsor Index (Contractor Reports)

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

EDO OFFICE FOR ANALY$ll & [VALVATION OF OPERATIONAL Nunt G/Ch E4e c h;1iCAL A%t sLMLNT Os SE AMK. AND Gt o DATA MT U4ANICS Litt 4 AT Uh[ $4[ L Atl D T O A HIGH (( Vi t NL[ AH 0$ F U:t F04 ANAlv 95 & L VALUAflON OF OPi HATIDN AL DAT A. D1 W Astt UNDt 4 GROUND ht P05i1091 Ilf C104 NUALO 'Ch B46 AN INVE $1GAiION Of 'tHt t F F [ CIS Of 1HE 4 NUhEG/GR 2')D6 V10 N2 LICt NSE E (\\[NT D[POHf (t L in MAL Agy, ON THE FiHE DAMAGE Ahalf t OF tt( Cinic COMPil ATiON 8 (p Manth (if Fctc.ay 1991 cam [$

NURE G'C H 2N3 V10 N3 Ut ( N5t l [ VE NT OfPO41 n! ry NUME G TH E'M T HE HGH t [ Vl t vih4 A f ION tlST COMrut AliON & or M inin Of Me 1991 p,ggggy, m pg NU4(O'CA 2000 V10 N4 UC f, N 3t>

[ d N1 H[POHT n [ In NUHf GTn $'a2 ANAL vTIC AL STUD'l 5 Of TRANSVID$ E STHAIN

[ F f CT S ON F R ACTUhl TOUSHN[ SS F OH UNCUMf I hi Nil Al-DM F$ (1 F

. AM F ST 870413p F OW Sf haldiCATION 14 TH(

Lv Ohrt NT[D (R AO S NURI G rCR L4% AN AL Y SIS Of L

SURGE LINE Or THE COMANCHE Pt At RL ACTO 4

""N N W D'M MUN 5 N WU C

f h Al L Of b i OH TH[ Tllf I hl PO5ilONY

!DO OFF6CE OF NUCLE AR MATERIAL $AFETY & SAf f OUARDS NUh[ G th WH f 5 f L CTS OF PH ON T HE All f ASL Of H AD10N DN151DN OF 5Af t GUANDS & THAN5Ki4T AT OC (DOST 004th UC4lDI S AND CHL L AtiNS AGE NT5 f NOM Cl VE NT-bOUU7 II D

. NURt G/CR4717 P ACh AGWG SUPPLit 4 IN5%dh0N GUiDF Df CONT AMW ATION ION lxCHANGE hlhiN5 COM f CT! D F MOM DIVM>N OF HIGH LI V( L W AS1f M AN AG(M(NT (PCST $7041h gp{ p49;qq qtg_g g gq ppgg q gygyggqq NUh[ G!CR 344 V02 T L CHNIC, 25 i Oh DC il RMWiNG F HDD NUREG%4 MN Pt NNSYLb AN!A 5615M'C MON f 041NG NL T-ALULIOE S Of EVENTS AND PRCCf SSE S AtiECTING THE PLH WO6k AND kt L ATE D 1i CTONIC STUDitS F mW Retv1 F ORM ANCL OF GE OLOGIC RE POsiTOhl[ S Saggosted Approact" Nur4 G'Ch %4 1RANSPOHf CAL CUL ATIONS OF M U T H ?N N 8 E G/CR M37 APP 40ACH[$ FOR THE V AL ID A tlON OF-

[ NDF / B V AND [.ND8 /B VI IRON f V ALU ATIONS MODELS USl'D FOR PERIORMANCE AS5ESSMENT OF HIGH.

ggg g,C4 m SuhM[ RM NQ AND HOH TLMDtHATURt L E VEL NUCLL AR W ASTE HF POVf 0RT S DM 3N LC E t L W ASTE M ANAGE MI NT A DE COMV?$$ TON Sif AM 11 SW OF G ASS tt tilUNCAL CAfuls NUMLG!CR SMI LOW L E VEL W ASif SOUNCI TE hu MODEL DI.

NUkEG/CHf>713 A Rf Vif W Or f.NWHONME NT AL CONDITIONS yf U

T RY it StWG OF CE MI NT GROUitNG AND Pi nFOHMANCE OF THE COMME RCI AL LOW LE vf L H ADIO-O& h ACTURf' S IN W[l DE D TUF F AC11VE W AST[ DISPOSAL F ACILITY N[ AR SH[ FF iE t D n UN%

N""f 4 ^N^L S^"

'" K "E

""^

NURI G'CR 5714 HY DRCEL OLOGtC Pi RF ORM ANil A%l bS MENT ANALYSIS OF THE LOW 4EVEL R ADIOACTIVE W ASTE D15 t C PLHF 04VANCE OF CE MENT GROUT l'OR[HDif 5[ At S PO5AL F ACILITY NE AR SH[F F l( LD (LUNOlg bN IIIk C I

NUAE G/CH S737 H YD40GC OL OGIC 8'C HI ORM ANC E ASSIS$

lit NTONii[ GHout:NG MLN T ANALYSIS Or THE COMME RCIAL LOW LE V[ L R ADIOAC-NUHf G'CR %M MI CHANiCAL CHAHACT[hlZATION OT Dt f6 fly 11 W ASTE DtSPOSAL F ACILiiY NLAR WLST V ALL E Y,NE W N

C F Of f NT L SAF( TY Hf L ATE D PUMP LOSS AN A%E S5ME N1 Or INDUsinY DA f A NHC Dmn im 04 EDO OFFICE OF NUCLE AR RtGULATORY Rf SE ARCH (P _f$20405)

NURE KR W WDR VAUDAHON AT M W, N fS OfVNON OF ( NWNE t HING (POS T 6704133 ikf NCH SITL l

NUREG/CH 42t9 V07 N1 HL AVY 5E CTION STLEL T[CHNOgny NUHE GTR 5727 CHLORIDE ION DJ FUSION IN LOW W ATI R TO PROGR AM 5emiannut Progre+s Repyt f or Octotier 1M9 Manh SOLID CIMLNi PASif S 10 %

NURLWCh 5729 MUL TiV Ah1 ABL E MODE L !NG OF PHE 55URE NUHE G'CR 4302 VO2 AGING AND SL AVICE WLAH Of check VE SSE't AND PIPING J H DAT A VALVE S USED IN INGINEE RED SAFE 1Y 8 L ATURE SYSTEMS Or DNISION 05 hiGULATORY APPLIC ATIONS (POST F041h NUCLE AR POWE R 5'LANIS Aging Aaessments And M wiorng NUHL G/CR %4 7 FibSiON PHODUCT PL All OUT AND UF IDFF IN Memod F vetusteong THE MHf GR PR MAHY SYSTE M A hf V:t W NUREG/Ch 4513 ( SilM ATION OF FRACTURE TOUGHNESS OF DMDON Gr S AF ET Y ISSUE RE SOL UTION (POST 6k0717)

CAST ST AINLESS STEELS DUHWG THL4 MAL AGING IN LWH NUH[G'CR a893 TF CHNICAL F INDiNGS RE PORT 104 GF NtniC

%v AT F us ISSUC 13', Steam Gereator And Stoam t ine OvvfS lessM I

NUREG CH 4599 V01 Nt. SHORT CRACnS IN PIP!NG AND PIPIN3 NUHLG'CR 51U COST cliLNE FIT ANAL YSIS F 04 Gf NL HIC ISSUE WE t DS Sam.annu1 Report Maret'Sertemte 1990 23 fu ACTOR COOLAN1 PUMP SE AL F AILUHf-NVREG/CR 4M7 vl. L NvlRONME N f t t L Y ASS;STLD CR ACP 'NG NURE G'CR M2t> AN AL YSiS Of hiSK RE DUCTION ME ASuRE S AP.

IN LIGHT W ATER RE ACTORS Sermannual Repor1 Apol 5cotemte Puf D TO SHAhED ESSE NHAL SE RVICL W A1L R Sy STEMS AT 1969 MJLin UNIT S;il 5 NUhtGrCH-4M7 V10 ENVIRONMENT ALLY ASSIGTLD CRACK'NG NUHE G/CR 'p5 THE RE SPONSE OF BWH MARK 11 CONTAW IN UGHT W ATER R[ ACTOHS Sermannual Report October 19e9 MENTS 10 ST A fiON BL ACF OUT SE Vt hE ACCIDt NT SE.

March 1990 OutNCts NUHtGiCH 4MJ V11. [NVIRONMENT ALLY A55fS1[D CRAC> iNG NURLG'CH %30 PWR DHY CONT AINM{ NT PARAME THC ST UD-IN UGHT W ATER RE ACTORS Semaannual RepartApni SgtomW

![ $

im DMSiDN Or sySTE MS RE SE AOCH (Post M0717)

NU4f G'CH 4744 V04 N1 LONG TERM EMBR:1TLEME NT Of CAST NukfG CR4%1 V2R1P2 EvAt uATION OF 50 VE RL: ACCIDE NT DUPLE X S T AINLL S S STEELS IN LWR S r S TE MS Semiannsa' Rf 5* S QUANtirit AtiON Or MAJOh INDUT beport October 19h8 - Ma th 190)

PAR AME TE RS E aperts DetermnaSon Of Comamment Loah AM NUHf G/Ch 4744 VD4 N2 LONCeTERM EMBR!TTLE MLNT OF CAST M11on Core Contamment htwat tion es DUPL E X ST AINL E SS STE FLS !N LWR SYSit MS semannuar Nuhi G'CR $'00 VC1 INTE GN ATE D l'E LI AB1UT v AND N!Sk ANAL-heport AMI Snetember 1989 YS:S SY STIM OhRASi V E R5rO4 2 5 Reimm Ma%M NURt G/Clk 512tp E V ALUADON AND RI F WEME NT Or LE AA AATE NUHlGtR5W5 V01 M.JL T iL ODP INT E GR AL S v STE M TEST ESilM ATION MODELS iMtSij rWAL AE PORT SmaN 33

l 34 HRC Contract Sponsor index NUHEG/CH %43 A SY ST[ M A16C PROCC SS F OR DE i[ LOPING NURE G'E R S702 ALODE NT M AN AGE ME NT INr ORM A1 ON N(t DS AND ASS [ SSnNG ACCIDE NT MANAGE Mt NT PLAN 5 FOR A CAR wt1H A M AHK I CONT AINMt NT.

EDO OFFICE OF NUCLE AR Rt ACTOR REGULATION (POST 4/28/60)

ENTA L Billif A ER LE E S F4UHLG/CR Mt? DEGRADATION MOD (LING WITH APPLICAtlON

,gf MI[;,$ ^ thIf 4offgi[y[thr n

c tp TO AGING AND M AINil NANCE El F L CiliENE SS E, ALU ATIONS GINIHAL E t ECTHtC T YPE HF A hl LAYS IN USE IN CLASS 10 NUHEG/Cf4 %63 HELAP5 THERMAL HYDHAULIC ANALYSIS OF SAFITY SYbf EMS THE WNP1 PHE550RtlE D W ATER R[ ACTOR NunEGiCH L742 v01 F E AhiEilllT Y ASSL L5VE NT OF A F415K-NUREG/CR M70 M JLTILOOP INif GRAL $ Y $1[ M 1( $1 BASED APPhDACH 10 TECHNICAL f,PECiFICAtlONS t newtive (MIST)MtS1 F ACILITY FUNCTONAL SPCCIFICATON

$,mmay NUREG/CR %77. A UNIFIED INTE RPHET AllON OF ONE Fil TH TO NdHL G'CR 6142 V02 F E AssBILIT Y ASSESSMENT Or A $USK.

6

$ ULL SCALE THERMAL M;11NG E XPF.RIMENT$ R[ LATED TO B ASE D APPHOACH 10 T ECHN' CAL SPt Ct8 lCAflONS Mam N#PA.

PRESSURiff D THERMAL $ HOCK.

Div) SON U HADIATON PROTEC70N & E MERGENCY PHIPARED-NUREG/CR %82 $PECIFIC TOPICS IN 1EVERE ACCIDE NT MAN NFSS DOST B70411)

AGE ME Ny 546 i

GUM M W,M AL NURLG/CRkA91 (NSTF4UMENT ATON AVAILABILITY FOR A PRt $.

^"

SUR: LED WAllR RE ACTOR WITH A LAHGE DHY CONT AINVENT NUi G 92 RC U

iS FOR GENIRAL ELEC-DUR NG SEVERE ACCIDENTS TRIC BOILING W ATER RE AC10RS E

1 1

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

ARGONNE NATIONAL LADORATORY NunEG CR %11 ISSul S AND APPROACHE S F04 U$tNJ t QUt NURE G 'CR-4 5 t 3 E SilMATION OF FRACTURE TOUGHNESS Of Mf NT Rf tl ADIUT Y At t 41 t EVi t S CAST ST AINL ESS STE ELS DURING THE RMAL AGING IN L WH sis-NUht G/CR %12 DiGRADAliON MDDL LING WlTH AbOLICAtlON TO TEMS AG1NG AND MAINil NANCE E f f E CitVI N(;S (.vALUA160NS NUREG/CR-4f47 Vo9 E NVIROWENT ALLY ASSISTED CRACnNG IN NUHE GICA MA) LOWLEvil W ASTE SDU$O TEhM MDDIl DE LIGHT WATE R RE ACTORS Somamun! Rervi A nt SWIemtw im VE LOPME NT ANh 1F Sil4G J

NUNEGrCR 4M7 V10 ENVIHONMENT AL( v AS$51L D CHAC* lN3 IN NU4E G/CH %92 GE Nf h(, A9 IWGHT S 7 04 GI NE H AL elf C UGHT W ATE R RE AC10RS Se% annual Regort CXM,of 1989 Mnh ifoC 14DIUN3 W All H RE AC 7045 1990 NUni G/CR 447 VII ENVIRONMENT ALLY ASS;S1f D CHACMNO IN C AUF ORNI A UNIV. OF. EOS ANGE LES, C A LnHT W ATE R RE ACTORS Serma%ual Rept Ap**beNemt+r 190 NU4EG <CH 3%4 V02 TL CHNiOUF b F OR DE TE DMINING PHOBAf0L-NUHEG/CH-4744 v04 N1 L ONG 1ERM EMbH11TLt MLN1 Of CAST liiES OF E VE N f 5 AND proct SSE S Af f E CilNG THE PLHf ORM-DUPLE x ST AINLE SS STEELB IN LWR SYSTE MS Smann#

AmE Or GEOsc DE POSITORif S Sopitod Awoarhos Rept Octolet 19t38. March 1989 NUhr O'CH 4744 V04 N2 LONG-Tt RM EMBRITTLt MENT OF CAST C AUF ORNI A, UNIV. OF SANT A B AFIB AR A, C A DUPLEX ST AINLE SS STEELS IN LWH SYSTE MS Sermannual NUAWCH %77 A UN:FIED INTE RPHE T AllON Of ONE J iF 1H TO FUL L SCAll THI hM AL M!a:NG E kPE RIM [NTS DE LATE D 10 PDI 4 NF

/C 4

At L 5 OF FLOW STRA11FICAtlON IN THE bu"O U I"IhM^l b"U" SUHGE LINE OF THE COMANCHE PE AK HE AC1DR AR120N A. UNIV, OF, TUCSON, AZ CENTER FOR NUCLE AR WASTE REGULA10RY ANALYSES NUREG/CH %83 LABORA10HY TESTING OF CEMENT GROUTING NUREG/Ca 5440 GRlTICAL ASSE SSME NT Or SE LSMIC AND GI OMI.

OF F R ACTURI S IN WT LDED TUF F CHANtCS UTE RATURE RELA 1ED TO A H'GH L E VE L NUCL E AR NURE G/CH %B4 ANALYSES AND FIELD TESTS Or THE HYDRAUUC W ASTE UNDt hGROUND RL FOSITOH1 PE HFORMANCE OF CEMENT GROUT BOnEHot E SE ALS NURE G /CR MA6 E FFECfIVENLSS OF FRACTUht SE ALING W:1H CONTtST COLUMOUS TECHNOLOOiES Bt NTON!TE GROUTING NU4EG/CR 5%e iMM[RSiON STUDIE S ON CANDIDA1E CONT ArNI R NUREG'CR %B8 MECHANICAL CHARACTF Rif ATION OF DENSEl' ALLOYS FOR THF TUFr REPOSITORY WE LDE D APACHE LE AP TUF F NUHEG/CR 571t. MODE L VALIDATION AT THE LAS CRUCES E ogo ;D AHO, INC, (SUBS OF E G&Q, INC )

TRENCH SITE NU4E G/CH S330 V01 INTE GRAllD REtIATitTY AND Ribk ANAL Y.

sis SYSTE M ORH AS) VE HSiON 2 5 Retwerxe Manual BABCOCK & WILCOX CO' NUHL G/CH %43 A SYSTE MATIC PHOCESS FOH DEVE LOPING AND NUREG'CR 5395 V01 MULTit OOP INTEGRAL SYSTEM TE ST

^

(MIST) FIN AL REPORT Summar NUHEG/ER %01 E F FE CTS Or PH ON THE HE LE ASE OF HADIONU-NURE GICR 5670 MULTILOOP i TEGRAL SYSTEM TEST (M.STiMiST F ACIUTY FUNC1 TONAL SPECIFtCATiON CUDES AND CHELATING AGE NIS FROM CE MEN 1-SOLIDiflE D DE -

CONT AMINAllON lON E

• CHANGE HE SIN 5 COLLECTl D F FtOM OP-

\\

BATTELLE MEMORIAL INSTITUTE E R ATING MICLE AR POWE R St ATIONS NUREG/CR 4599 V01 N1 SHORT CRACKS IN PIPING AND pip NG NUREG/CH %63 RE LAP 5 THEkMAL HYDRAUUC ANALYSIS Of THE WELDS Semiannual Reptw1 March Septemter 1993 WNP1 PHE SSuni2ED WATE H RE AC10H NUREGICH 5128 EVALUAllON AND iblFINEMENT OF LE Ak RATE NUREG/CR 5ti91. INST 4UMENT A110N AVAIL ADIUTV F OR A PHI S-ESTIMATtON MODELS SURi2ED W ATE R RE ACTOH WITH A LARGE DHY CONT AINMLN1 DURING SE VERE ACCIDENTS BATTELLE ME MOFil AL INSTITUTE. P ACIFIC NORTHWE ST NUREG/CR 5702 ACCIDENT MANAGEME NT INIDHMAtlON NEEDS LABORATORY FOR A BWR WITH A MARK I CONT AINMENT NUREG/CR 5467. AtSK DASED INSPECTION GUIDE FOR CRYST AL NU4EG/CH 5717 PACKAGING SUPPUER INSPECTION GUIDE RIVE R UNIT 3 NUCLEAR POWER PLANT NURE G1CR 5713 A REVIF.W OF ENVmONMENT AL CONDITIONS AND GR A M, INC.

PERFORMANCE OF THE COMMERCIAL LOW LEVEL RADICACTIVE NUREG/CR-3E4 V02 TECHNiOVES FOR DETERMINtNG PHOBAEW W ASTE DISPOSAL F ACIUTY NE AR SHEFFLE L D.ILUNO45 111ES OF EVENTS AND PROCESSES AFFECTING 1HE PERFORM-NUREG/CR-5714 HYDROGEOLOGIC PERFORMANCE ASSESSMENT ANCE Or GEOLOGIC RE POSITORIE S Supstod APProachen ANALYSIS OF THE LOW-LEVEL RADOACTivE W AS1C DISPOSAL NUHEGICH %37, APPROACHES FOR THL VAUDATION OF MODELS

^

NUR

/R 37 HYDR E6 E C ERFORMANCE ASSESSMENT

^

0 b

b ANALYSIS OF THE COMME RC1 AL LOW LEVEL R ADIOACTIVE W ASTE DISPOSAL F ACluTY NEAR WEST VALLEY.NEW YORK iT ASCA CONSULTING GROUP. INC, BROOKHAVEN NATIONAL LABORATORY NUREG/CR E440 CRlTICAL ASSESSMENT OF SEISMIC AND GEOME NUREG/CP.0114 V01: PROCEED!NGS OF THE EIGHTEENTH W ATER CHANICS LITE RATUHE RELATED YO A HIGH LEVEL NUCLE AR RE ACTOR SAFETY INFORMATION MEETING W AST E UNDERGROUND REPOS! TORY NUREG/CP-0114 V02 PROCEEDtNGS OF THE EIGHTEENTH W ATER RE ACTOR SAFETY INFORMATION MEETING LOUISIANA STATE UNIV. BATON ROUGE. LA NUHEGICP-0114 V03 PROCE EDiNGS OF 1HE EIGHTEENTH W ATE R N' 'RE G rCR-%48 TRANSPORT CALCUL ATIONS OF NEUThDN REACTOR SAFETY INFORMATION MEETING TRANSM!SSION THROUGH STEEL USING ENDF /D V. REVISED NURE GICR $526 ANALYSIS OF R!SK REDUCTION MEASURES AP.

F MDF /D V.AND ENDF /8-Vi lRON EVALU ATIONS PUED TO SHARED ESSENTIAL SERVICE W ATER MSTEMS AT MULTI-UNIT SITES MODELING & COMPUTER SERYlCES NUREG/CR M85 THE H6GH LEVEL vBRATON TEST PROGRAM Fitw NURE G/CH 5129 MULTiv ARIABLE MODE UNG OF PRESSURE Report VESSE L AND PIPING JR DAT A 35

36 Contractor index NATONAL INSTITUTE OF tT ANDARDS & TICHNOLOGY (FORMERLY NURE G/CR 4551 V2 RIP 2 ( V ALU ATION OF SEVERE ACCID ( NT NATIONAL DURE AU OF RinS QUANTIF(CAllON OF MAJOR INPUT PARAMETER $ 8iPerts' NUREG/GR 5727 CHLOfCDE ON DlFFUSON IN LOW W Ait f4 TO Detenmnebon Of Ccotatoment Loads And Matten Ocve Containment

$0 LID EEMENT PASTES interacton iu x.s NURL G/CR %37 APPROACHf S F OR THE VAllOA10N OF MOD (LS Ntw MEllCO ST ATE UNIV., LAS CRUCt &, NM USED 5 04 PE RFORMANCE ASSESSME NT Of tUGH LtVll NUCLL-NURfGdCRt716 MODE L % ALIDA10N AT THE LAS CRUCES AR W Asit At POSITORIE S TRENCH $1TE NUtit G/CR M46 AN INVE S11 GALLON OF THE til ECTS Of' THE R MAL AGING ON THE FIRE DAMAGF ABILITY Or iLtCTRIC CABLE S OAK RIDGE NAtlONAL LABORATORT NURE G/CH M30 PAR DRY CONT AINutNT P AfoM2180C STUD!LS NU54t G/CR 2WJ V10 N2 LtCE NSE E [ VL N1 RLPORT (LI R)

NURI G/CR %M SUt1MI RGI NCE AND HIGH 1(MPERATURE hf E AM COMPIL ATION For Month Of f etsum 1991 1[ STING OF Cl ASS 1[ EtiCTRICAL CAEP N NUREG/CH 2000 VfD N3 L6CE NJ E IVENT REPORT (L E R)

COMPit ATlON For M-anth Of Mserh 1991

$CitNCE & ENOINTERING A$$0ClATt8,INC.

NURE G/CR ?000 V10 N4 LICE NSE L LV(NT REPORT (L(R)

NUREG/CR f4% SUBMLAGENCE AND HGH TEMPERATURE Sil AM M bitNG OF CLASS it ELLCTRICAL CABLE S 9 h0 N

il Vf CTON ST((L TECHNOLOGY NU [G/

4 PROGRAM Semiannual Prvress Hepart For Octoter 1969. Ma'ch

$CitNCE APPLIC ATIONS INTE RN ATION AL CORP. (f OR4 ERLY g

gp y

y ' EVALUATON Of SLVERi ACCIDE NT NF GrCR 4302 V02 AGING AND SE84VICE WE AR OF CHECK VALVES USED IN [NGINEERED SAf ETYJEATURE SYSTEMS O!

RISAS OUANilFIC AllON Or MAJOR INPUT PARAML "f RS taPerts NUCL L AR POWER PLANTS Agng Atwssments And Monitonng Determmaton Of Containment Loa 1s And Mahon Cut Contamment Method I t aloatons NunEG/C84106 THE RESPONSE OF BWR MARA 11 CONT AINMLNTS g[gy'h 1[ISSUF S AND APPROACHES 5 0R USING EQUIP-TO ST ATION BLACAOUT SEVE RE AOCIDEN1 SEQUE N'T S NUREG/CR %92 ANALYIlCAL STUDilS Of TRANSVERSL STRAIN N[,

L 01 I 1 L TY SSESSML NT OF A FilSK DASED FFE IS O FRACTURE TOUGHNE $5 IOR CIRCUMFLRENTIALLY Af'PROACH TO Tt CHNIC AL SP( Cif ICATOf3 [sec uttve Sunmary NUREG/CR 6142 V02 F E AS Bittit AS$4 SSMENT Or A RISK BASLD NURE G/CR %47 FISSION PRODUCT PLAf f 0VT AND UrtOFF IN APPROACH 10 f t.CHNICAL bPE CIF ICAllONS Mam Report THE MHTGR PRIMARY SYSit M A REVIFW NUALG/CR 5648 TRANSPORT CALCULAT ONS OF NEU1RDN SC C.

T R ANSMISSON THROUGH STEEL USING ENDF /D V,RE7 SED F

3 TE CHNfCAL f lNDINGS R[ PORT FOR GENlRIC

( NDF /B-V.AND E NDF /B.Vi IRON F %;ALUAllONS ISSUE 1% Str.am Gef eator And Steam Une Overidt lasues NUREG/CR 6736 POTENHAL SAF LTY AlLATl D PUMP LOSS AN AS NUREG/CR 6161. COST /BE NI F iT ANALYSIS F OR GE NE RIC ISSUE SESSMENT OF INDUSiliv DATA NRC Bulletin t18 04 23 fiE ACTOR COOLANT PUMP SE Al F ALLURE NUREC/CR %82 SPEClHC TOPICS IN SEVERE ACCIDEN1 MANAGL-PAR AM E TE R, INC, NUREG/GR 4p6 CLOSLOUT OF IE DULLETIN 84 02 F AILURES Or MLNT NERAL T LECIFitC 1YPE HFA fiELAYS IN USE IN CLASS 1E TECHNADYNL ENGINitRINO CONSUL 1 ANTS. INC.

NUREG/CR 4%) V2R1PJ I V ALUATON OF SE VE RE ACCIDE NT PENNSYLVANIA STATL UNIV UNIVERSITY PARK, PA RISAS QUANTlf ICATION OF MAJOR INPUT PARAML1E RS t sports' NURLG/CR SE2B PENNSYLVANIA SEISMiG MON 110HING NE.TWORA Determenahon Of Containnvent Loads And Mo: ton Core Contsenent AND RELATED TECTONIC $TUDtlS f nel Report intov erbon issues RAFAEL BRAS CONSLMING ENQlNEERS TEXAS A&M UNIV COLLE0t ST ATION, TK NUREG/CR 3964 V02 TECHNOUE S F OR DETERMIN'NG PROB ABit.

NUREG/CfL3%4 V02 TECHNIOUE S FOR DE TE RMINING PROD ABIL.

ITitS OF LVENTS AND PROCESSES AFFEC11NG THE Pf RF ORM.

ITIES Or EVENTS AND PROCESSES AFF LCTING 1HE Pt F4 FORM-ANCE OF GEOLOGIC nEPOsiTORIES Suggested Approaches ANCE OF GEOLOGIC REPOSITORiLS Suggested Approactwa SANDIA N ATION AL LABORATORitS WISCONSIN UNIV. OF M ADISON, WI NUREG/CR 3964 V02 TECHNIQUES FOR DETERMINING PROBABIL-NUREG'CR 344 V02 TECHNtQUES FOR 0011 RMINING PROBABIL-fTIES OF f VE NTS AND PROCESSES AFf LCTING THE PCRF ORM-ITIE S OF EVENTS AND PROCESSES A8 FEC11NG THE PERF ORM.

ANCE OF GEOLOGtC RE POSITORIES Suggested Approaches ANCE or GEOLOGIC REPOSITORilS Suggestwt Appros:hes

International Organization Index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forrning 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.

w.. u,. no Nuntca A, cwt n., n au.mu.

9 37

l l

I

I 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 prsceded by their Docket number and followed by tha report number. If further information is n'aeded, refer to the main citation by the NUREG nun ber.

54445 ComaNt* Fee Steam Emctre Stator. Urv 1.

NJREG'CH{456

$U3 (Mdo Canyon Now Pows Plat Urw 2.

N'JAEGW5 $34 Tees Utstes Eat I c4 Gas & Ewtre Co -

f E446 (unathe Pean Steam EWh Staten, Um 2.

NUREG'CR 54%

D601 Rf AAR SP% he$'#foae Ektic Corp NURfG 1413 Texas Uwes Elect W4@

MPSS New PrW Urm t. nasWon NUREGICA 5603 l

M307 Cr sts her Nda Plat Umt 3, Fknie Pows NVREG/CR 546?

k 8

6'S 8*

.m gggy,,,,,_

ggg,~g. w t.

~uG,5 $34 Va'wy Authtv4y i

1 4

39

U.S. NUCLEAR REQULATORY COMMSSiON

1. AEf* ORT NUMOER to 04>4 336

( AssigW by NRC. AM Vol..

(2-89)

Supp, Hev., and Addendum Ne NROM 102, b* * - " *ar 3 320'. W BIBLIOGRAPHIC DATA SHEET NUREG41304 (se. rstructions m tr. r.

..)

Vol.16, No. 2

a. u n t Are sue m Le

3. DATL HLPORT PVOUSHI O Regulatory and Technical Reports (Abstract Index Journal)

MONTH YEAR November 1991 Compilation for Second Quarter 1991

4. rtN OR GRANT NUMDER April-June

6. TYH OF HLPOHT

6. AUT HOR 6) t Refe ence

7. PLRIOO COVERED onclusive Dates) o April-June 1991

e. twoaMno OsawzioON - NAMe ANo AcosEss o, rec. provice oimon. Ome. or neo w. U s Nuasar seguistory coness on, ana rnailing a11ress; If contractor, provide narne and malteng sor$ess )

Division of Freedom of Information and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 SPONSORen OHGAN32ATION - NAME AND ADORESS Of NHC. type

• Same as above* ; it contractor, provice NRC Division. Qtfice or Region.

9. U.S, Nuclear Re4Watory Corwmssen. and mailing address.)

Same as 8, above.

10. SUPPLEMENT ARY NOTES

11. ABSTRACT (200 words or less)

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

13. AV AILABILITY ST ATEMENT

12. KEY WORDS/OESCRIPTORS (ust words or phr ases that will assist researchers in kx:stmg the report.)

Unlimited 14, SECURITY CLASSIFIC ATION Compilat}on (This l' age) abstract mdex Unclassified g

(This Report) 4 Unclassified Ib. NUMBLH OF PAGES

16. PH4GE NRC FORM 335 (2-60)

L 1

THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER

,,. n -,

1,.

UNITED 8TA900

~

'mccomm ceso cava PostAose setsPMD NUCLEAR REGULATO*,.Y COMMIT $lO.J

" "C WASHWGTON O.C. 20666 7

ennuit we c e?

C mafsNOi Mi..=

E fc

.f<

Main Citations I I#Ul# CIA 519'l E'

and Abstracts US d!1$hd1

?

DIV FOIA

?. PURLICATIONS SVCS TPS-PDR-NUREG Z

P-223

?"

W A S 11NG T ON OC 2055",

Secondary Report Number index Personal Author index E

S ca Subject Index

$c 5E mn F=

NRC Originating Organization i3 Index (Staff Reports)

E9 z t-m m

$@C NRC Originating Organization E

Index (International Agreements) 9=

=

kH NRC Contractor 5z SponsorIndex Contractor Index 2

International Organization 9

Index rd::

Em I

~

Licensed Facility index

_ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ - -