ML20093A631
| ML20093A631 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1984 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V09-N01, NUREG-304, NUREG-304-V9-N1, NUDOCS 8407110023 | |
| Download: ML20093A631 (146) | |
Text
._.
l NUREG-0304 l
Vol. 9, No.1 I
j I
Regulatory and Technical Reports Compilation for First Quarter 1984 January - March U.S. Nuclear Regulatory Commission Office of Administration I
f a a ' %,,
r j ',,.gf k
/
+,
l 8407110023 840531 PDR NUREG 0304 PDR J
=
h Available from NRC/GPO Sales Program Superintendent of Documents Government Printing Office Washington, D. C. 20402 A year's subscription consists of 4 issues for this publication.
Single copies of this publication are available from National Technical information Service, Springfield, VA 22161 Microfiche of single copies are available from NRC/GPO Sales Program Washington, D. C. 20555 i
2
..-______.__m..-.____
_______,__m_
NUREG-0304 Vol. 9, No.1 Regulatory and Technical Reports Compilation for First Quarter 1984 January - March i
DIte Published: May 1984 Division of Technical Information and Document Control Office of Administration U.S. Nuclear Regulatory Commission Wcshington, D.C. 20555
- f....,,
i.
1 a
\\,...../
)
b
i a
C 4
1 CONTENTS Preface........
v index Tab a
Main Citation and Abstracts.......................................................1 Staff Reports..........
Conference Proceedings.................................................
Contractor Reports.............
Contractor Report Number Index......................
.2 Personal Author index......
3 Subject index................................................................... 4 NRC Originating Organization index (Staff Reports)......
5 NRC Contract Sponsor index (Contractor Reports)..............
.6 Cont ractor index.................................................................... 7 i
Licensed Facility index....................................................... 8 4
I I
1 I
d 4
4
\\
6
-lit -
w
PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be ap-preciated. Please send them to:
Division of Technicalinformation and Document Control Policy and Publications Management Branch Publishing and Translations Section Woodmont 501 U.S. Nuclear Regulatory Commission Washington, D.C. 20566 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. These precede the following indexes:
Contractor Report Number index Personal Author index Subject index NRC Originating Organization index (Staff Reports)
NRC Contract Sponsor Index (Contractor Reports)
Contractor 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-0508: 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) report autnor, (4) organization that compiled the proceedings,'(5) date report was published, (6) number of pages in the report, (7) the NRC Docu-ment Control System accession numbei, (8) the report number of the originating organization, (9) the microfiche address (for NRC internal use).
Contractor Report NUREG/CR 1566: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R.
4 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.
I authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC '
i Document Control System accession number, (8) the report number of the originating organization (if given). and (9) the microfiche address (for NRC intemal use).'
v
l
-s
'g _
The following abbreviations are used to identify the document status of a report:
ADD - addendum APP - appendix DRFT - draft ERR
- errata N - number revision R
S
- supplement V
- volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the NRC-GPO Sales Office or from the National Technical Information Service, Springfield, Virginia 22161. To purchase documents from the NRC GPO Sales Office send a check or money order, payable to the Superintendent of Documents, to the following address:
U.S. Nuclear Regulatory Commission ATTN: Sales Manager Washington, D.C. 20555 You may charge any purchase to your GPO Deposit Account, Master Charge card, or VIS A charge card by calling the NRC-GPO Sales Office on (301) 492-9530. Non-U.S. customers must make payment in advance either by international Postal Money Order, payable to the Superintendent of Documents, or by draft on a U7ited States er Canadian bank, payable to the Superintendent of Documents.
NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identification replaces contractor established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship of the work being reported.
in addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings.
All these report codes are controlled and assigned by the NRC Division of Technical Information and Document Control.
I l
l vi l
1 Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is an NRC staff originated report, NUREG/CP-XXXX is an NRC sponsored conference report, and NUREG/CR-XXXX is an NRC contractor-prepared report. The bibliographic information (see Preface for details) is followed by a brief abstract of the report.
NUREG-0020 V07 N11: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data.As Of October 31,1983.(Greg Book)
- Management Information Branch.
January 1984.
408pp.
8402060291.
22105:267.
The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible.
This information is collected by the Office of Resource Management from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities.
The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported datas a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilitiess and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the U.S.
It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the U. S.
energy situation as a whole.
NUREG-0020 V07 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Greg Book)
- Management Information Branch.
February 1984.
379pp.
8402210078.
22320:313.
See NUREG-0020,V07,N11 abstract.
l I
NUREG-0020 VO8 N01: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Grey Book)
- Management l
Infarmation Branch.
February 1984.
396pp.
8403150058.
22647:001.
See NUREG-0020 V07,N11 abstract.
I j
l NUREG-0020 V08 NO2: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of January 31,1984.(Qvey Book)
- Management Information Branch.
March 1984.
22pp.
8404160205.
24063:341.
See NUREG-0020,V07,N11 abstract.
NUREG-0040 V07 NO4: LICENSEE CONTRACTOR AND VENDOR INSPECTION STATUS REPORT. Guarterly Report,0ctober 1983 - December 1983.(White Book)
- Region 4.
Office of Director.
January 1984.
190pp.
8402170320.
1
i 22303:001.
This periodical covers the results of inspections performed by the NRC 's Vendor Program Branch that have been distributed to the inspected organizations during the period from October 1983 through I
December 1983.
Also included in this issue are the results of certain inspections performed prior to October 1983 that were not included in previous issues of NUREG-0040.
NUREC-0304 V08 N04: REGULATORY AND TECliNICAL REPORT. Annual Compilation For 1983.
- Division of Technical Information & Document Control.
February 1984.
569pp.
8403070401.
22554: 217.
This compilation lists all NRC regulatory and technical reports published under the NUREC series during 1983.
NUREG-0325 R06:
U. S.
NUCLEAR REGULATORY COMMISSION FUNCTIONAL ORGANIZATION CHARTS. BARRY,L.W.
Office of Resource Management, Director.
January 1984.
63pp.
8401310461.
22042:349.
Functional orgar.1:stion charts for the NRC Commission Offices, Divisions. Staffs, and Branches are presented.
NUREG-0430 VO4 NO1: LICENSED FUEL FACILITY STATUS REPORT. Inventory Difference Data. January 1983 - June 1983.(Greg Book)
- Director's Office, Office of Inspection and Enforcement.
March 1984.
14pp.
8403220189.
22721:097.
(
NRC is committed to the periodic publication for licensed fuel facilities inventory difference data, following agency review of the l
information and completion of any related NRC investigations.
Information in this report includes inventory difference data for active fuel fabrication facilities possessing more than one effective kilogram of high enriched uranium, plutonium, or Uranium-235.
NVREG-0485 VOS N11: SYSTEMATIC EVALUATION PROGRAM, STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Buff Book)
- Office of Resource Management, Director.
January 1984.
75pp.
8401200362.
21872:003.
The Systematic Evaluation Program is intended to examine many safety-related aspects of 11 of the older light water reactors.
This document provides the existing status of the review process including individual topic and overall completion status, i
i i
NUSEO-0519 SOO: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF LA SALLE COUNTY STATION, UNITS 1 AND 2. Doc ket Nos. 50-373 And 50-374.(Commonwealth Edison Company)
- Division of Licensing.
March 1984.
30pp.
8404090036.
22947:282.
Supplement No. 8 to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located in Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the U.S.
Nuclear Regulatory Commission.
This supplement is to update our evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the full power operating license for Unit 2.
NUREO-0525 ROG: SAFEQUARDS
SUMMARY
EVENT LIST (SSEL).
- Division of Safeguards.
March 1984.
72pp.
8404050493.
22915:177.
2
The Safoguardo Summary Evont List (SSEL) providos briof summarion of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S.
Nuclear Regulatory i
Ccmmission (NRC).
Events are described under the categories of bomb-related, intrusion, missing / allegedly stolen, transportation, tcapering/ vandalism, arson, firearms-related, radiological sabotage cnd miscellaneous.
The information contained in the event descriptions is derived primarily from official NRC reporting channels.
NUREC-0540 V05 N11: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. November 1-30,1983.
- Division of Technical Information &
Document Control.
January 1984.
587pp.
8402210016.
22324:001.
This document is a monthly publication cantaining descriptions of information received and generated by the U.S.
NRC.
This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed mnterial received and generated by NRC pertinent to its role as a rogulatory agency.
The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Roference to Principal Documents Index.
i NUREG-0540 V05 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. December 1-31,1983.
- Division of Technical Information &
Document Control.
March 1984.
530pp.
8403260289.
22762:001.
See NUREG-0540,V05,N11 abstract.
NUREG-0500 V12 N12: REGULATORY LICENSING STATUS
SUMMARY
REPORT. Data As i
Of December 31,1983.(Blue Book)
- Management Information Branch.
i J:nuary 1984.
60pp.
8402100442.
22213:049.
Provides a review of the status of the progress of the licensing roviews for all construction permits, operating licenses, special projects and non-power reactor renewals under review, as reported to Congress.
NUREG-0606 V06 NO1: UNRESOLVED SAFETY ISSUES
SUMMARY
. Data As Of Fobruary 17,1984.(Aqua Book)
- Management Information Branch.
February 1984.
55pp.
8403230212.
22743:294.
Provides an overview of the status of the generic tasks cddressing " Unresolved Safety Issues" as reported to Congress.
i 4
i NUREG-0647: SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT,THREE MILE l
ISLAND NUCLEAR STATION, UNIT NO.
- 2. Docket No. 50-320. (Metropolitan i
Edison Company, Jersey Central Power And Light Company And Pcnnsylvania Electric Company)
- Office of Nuclear Reactor Rogulation, Director.
February 1980.
24pp.
8401270427.
22002:246.
This report contains an order for the Three Mile Island Nuclear Station, Unit 2, issued by the NRC. The order requires that effective immediately, the facility be maintained in accordance with the roquirements of the attached proposed Technical Specifications and (2) proposes to formally amend the Facility Operating License to include the proposed Technical Specifications, taking into account the present cccount of the plant' systems, so as to ensure that the unit will rcmain in a safe posture during the Recovery Mode.
3
NUREG-0675 S17: SAFETV EVALUATION REPORT RELATED TO THE OPERATION OF DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-275 Division of And 50-323.(Pacific Gas And Electric Company)
Licensing.
February 1984.
22pp.
8403070104.
22561:214.
Supplement No.
17 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate the Diablo Canyon Nuclear Power Plant (Docket Nos. 50-275 and 50-323) located in San Luis Obispo County, California has been prepared by the Office of Nuclear Reactor Regulation of the U.S.
Nuclear Regulatory Commission.
This supplement updates the Safety Evaluation Report ny providing additional informaticn on the breakwater issue.
NUREC-0675 S22: SAFETY EVALUATION REPORT RELATED TO THE OPERATION QF DIADLO CANYON NUCLEAR POWER PLANT, Units 1 AND 2. Docket Nos. 50-275 And 50-323. (Pacific Cas and Electric Company)
- Division of Licensing.
March 1984 400pp.
8403300300.
22843:001.
Supplement No. 22 to the Safety Evaluation Report for Pacific Gas and Electric Company 's application for licenses to operate the Diablo Canyon Nuclear Power Plant (Docket Nos. 50-275 and 50-323), located in San Luis Obispo County, California, has been prepared by the Office of t
Nuclear Reactor Regulation of the U.S.
Nuclear Regulatory Commission.
This supplement provides information on the Commission's review of allegations and concerns about the design, construction and operation of Diablo Canyon identified to the NRC as of March 9, 1984.
It includes the criteria that were used by the NRC to determine which o t*
the allegations that have been evaluated thus far must be resolved prior to Unit 1 achieving criticality and operating at power levels up to 5 percent of rated power ( i. e., low power operation).
NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
MASNIK,M.T.i SNYDER D.J.
TMI Program Office.
March 1984.
40pp.
8404100141.
22995:027.
This report updates a plan that defines NRC's role in cleanup l
operations at Three Mile Island Unit 2 (TMI-2) and outlines NRC's regulatory responsibilities in fulfilling this role.
Since the initial issuance of this NRC Plan in July 1980, this office has issued the Final NRC Programmatic Evironmental Impact Statement (PEIS) related to the entire TMI-2 cleanup and a draft Supplement to the PEIS related to occupational radiation exposure.
Additionally, a number of developments have occurred which will have an impact on the course of cleanup operations.
This revision provides a discussion of these developments, specifically in the areas of the functional role of the NRC in cleanup operations, the cleanup schedule, and the current status of the cleanup.
The plan also discusses NRC's perceived role in future cleanup activities.
Because of major uncertainties in the funding of the cleanup, portions of this plan, including the estimated schedule, are likely to require further changes as availability of funding and other factors affect the pace of the cleanup.
NUREG-0732 RO1: ANSWERS TO FREGUENTLY ASKED GUESTIONS ABOUT CLEANUP ACTIVITIES AT THREE MILE ISLAND, UNIT 2.
TMI Program Office.
March 1984.
55pp.
8404130056.
24049:001.
This question-and-answer report provides answers in nontechnical language to frequent 1u asked questions about the status of cleanup activities at Three Mile Island, Unit 2.
This revision updates 4
cnswars first prepared in 1981, chcrtly oftor the clocnup got under way.
NUREG-0748 VO3 N11: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of November 30,1983.(Orange Book)
- Division of Data Automation &
Management Information.
January 1984.
336pp.
8401260119.
21968:312.
The Operating Rametors Licensing Actions Summary a monthly publication designed to provide the Management of the Nuclear l
Regulatory Commission (NRC) with an overview of licensing actions f
i dealing with operating power and nonpower reactors.
I NUREG-0748 VO3 N12: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of December 31,1983.(Orange Book)
- Division of Data Automation &
Management In f or.na t i on.
January 1984.
335pp.
8402060497.
22108:039.
See NUREG-0748,VO3,N11 abstract.
NUREG-0748 VO4 NO1: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of January 31,1984.(Orange Book)
- Division of Data Automation &
I Management Information.
March 1984.
332pp.
8403270269.
22788:001.
See NUREG-0748,VO3,N11 abstract.
NUREG-0750 V16 B01: NUCLEAR REGULATORY COMMISSION ISSUANCES. July -
i September 1982.Pages 1-1,218.
- Division of Technical Information &
Document Control.
September 1982.
1220.
8402170121.
22306:001.
Legal issuances of the Atomic Safety and Licensing Board and Appeal Panels, the Commission, the Administrative Law Judge, and NRC Program Offices.
I NUREG-0750 V16 802: NUCLEAR REGULATDRY COMMISSION ISSUANCES.
October-December 1982.Pages 1,219-2,140.
- Division of Technical Information & Document Control.
December 1982.
960pp.
8402170060.
22309:264.
See NUREG-0750,V16,901 abstract.
)
NUREG-0750 V18 101: INDEXES TO NUCLEAR REQULATORY COMMISSION ISBUANCES.
1 July-September 1983.
- Division of Technical Information & Document Control.
September 1983.
85pp.
8404110317, 24007:101.
See NUREG-0750,V16,B01 abstract.
I i
NUREG-0750 V18 NO3: NUCLEAR REGULATORY COMMISSIDN ISSUANCES. September j
1983. Pages 299-742.
- Division of Technical Information & Document Control.
September 1983.
451pp.
8402280257.
22503:301.
See NUREG-0750,V16,B01 abstract.
NUREG-0750 V10 NO4: NUCLEAR REGULATORY COMMISSION ISSUANCES. October Division of Technical Information & Documentt 1983.Pages 743-1,137.
- Control.
October 1983.
400pp.
8403230183.
22813:040.
See NUREG-0750,V16,501 abstract.
l 5
- - _ - =.-.
NUREG-0750 V10 N05: NUCLEAR RECULATORY COMMIS3 ION ISSUANCES.Navcmber j
1983.Pages 1,139-1,301.
- Division of Technical Information &
Document Control.
November 1983.
167pp.
8404130221.
24036:175.
l See NUREG-0750,V16,901 abstract.
l I
NOREG-0775: FINAL ENVIRONMENTAL STATEMENT RELATED TO THE OPERATION OF COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NOS. 1 AND 2.
Docket Nos.
50-445 And 50-444.(Texas Utilities Generating Company)
Office of Nuclear Reactor Regulation, Director.
September 1981.
160pp.
C401270428.
22001:143.
The information in this Final Environmental Statement is the second assessment of the environmental impact associated with the j
construction and operation of the Comanche Peak Steam Electric Station, Units 1 and 2, located at a site on Squaw Creek Reservoir in
{
Comerve11 County, Texas. The Station will be operated by the Texas j
Utilities Generating Company. The Draft Environmental Statement j
related to the operation of the station was issued May 14,1981. The j
first assessment was the Final Environmental Statement related to the proposed station and was issued in June 1974, prior to issuance of the construction permits in December 1974. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the station, and includes the staff response to comments on the Draft Environmental Statement.
j NUREG-0776 SO6: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2. Docket Nos. 50-387=
l And 50-388.(Pennsylvania Power And Light Company A11egheng Electric Cooperative, Incorporated)
- Division of Licensing.
March 1984.
t j
100pp.
8404110036.
24002:123.
1 In April 1981, the staff of the Nuclear Regulatory Commission i
issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and Light Company (applicant or licensee) and the Allegheny Electric Cooperative. Inc.
(co-applicant) for licenses to operate the Susquehanna Steam Electric Station, Units J
1 and 2, located on a site in Luzerne County, Pennsylvania.
Supplements 1 and 2 were issued in June 1991 and September 1981, respectively and addressed several outstanding issues.
Supplement No.
2 also contains NRC staff responses to the comments made by the j
Advisory Committee on Reactor Safeguards in its report, dated August 11, 1981.
Supplement 3 was issued in July 1982 and addressed five j
items that remained open and closed them out.
On July 17, 1982.
Operating License NPF-14 was issued to allow Unit 1 operation at power l
1evels not to exceed 5% of rated power.
Supplement 4 was issued November 1982 and discusses the resolution of several license conditions.
On November 12, 1982, Operating License NPF-14 was cmended to remove the 5X power restriction, thereby permitting full power operation'of Unit 1.
Supplement 5 and this Supplement, No.
6 addresses several isssues that require resolution before licensing cperation of Unit 2.
1 I
NOREG-0800 07.1 R03: STANDARD REVIEW PLAN FOR THE REVIEW DF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To Section 7.1, Revision 1 To Appendix A.
Office of Nuclear Reactor Regulation. Director.
March 1984.
24pp.
8404180395.
24109:060.
Revision No. 3 to Section 7.1 of the Standard Review Plan incorporates changes that have been developed since the original issuance in July 1981.
This revision incorporates the resolution of j
I 6
Concric Iocuoo 45, "Inoporchility of Inctrumontotion Duo to Extrema Cold Weather."
NUREG-0000 07,5 R03: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To Section 7.5.
Office of Nuclear Reactor Regulation, Director.
March 1984.
Opp.
8404180397.
24109:052.
Revision 3 to Section 7.5 of the Standard Review Plan incorporates changes that have been developed since the original issuance in July 1981.
This revision incorporates the resolution of 0:neric Issue 45, "Inoperability of Instrumentation Due to Extreme Cold Weather."
NUREG-0800 07. 7 R03: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To-Section 7.7.
Office of Nuclear Reactor Regulation, Director.
March 1984.
7pp.
8404180399.
24109:045.
Revision No. 3 to Section 7.7 of the Standard Review Plan incorporates changes that have been developed since the original issuance in July 1981.
This revision incorporates the resolution of Coneric Issue 45, "Inoperability of Instrumentation Due to Extreme Cold Weather."
NUREO-0837 V03 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report, July-September 1983. COSTELLO, F. s THOMPSON,T.s COHEN.L.s et al.
Region 1, Office of Director.
March 1984.
138pp.
8404020212.
22877:245.
This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Natwork.
It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the third quarter of 1983.
NUREG-0847 SO2: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391.
Division of Licensing.
January 1984.
(Tennessee Valley Authority) 39pp.
8402100502.
22213:109.
This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982) and Supplement No. 1 (September 1982), issued by the Office of Nuclear Reactor Regulation of the U.S.
Nuclear Regulatory Ccmmission with respect to the application filed by the Tennessee Volley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391).
The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River.
This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation l
- Rcport, i
NUREG-0885 103: US NUCLEAR REQULATORY COMMISSION POLICY AND PLANNING OUIDANCE 1984.
- Commissioners.
~ January 1984.
23pp.
8403150211, 22662:139.
[
The purpose of the Policy and Planning Guidance document are to l
state, clearly and succinctly, the major policies and planning cbjectives of the Commission so that all employees will know where the 7
=
Agoney 10 hocdods to provido o comm2n basic within NRC for the development of programs, the establishment of priorities, and the allocation of resourcess to furnish guidance that can be used to develop-Agency budget voguestss and to help fulfill the requirement that NRC's annual report to the President for submission to Congress i'
contain a clear statement of the short-range and long-range goals, priorities, and plans of the Commission as they relate to the j
benefits, costs, and risks of commercial nuclear power.
NUREG-0887 SO4: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF l
PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2.Dochet Nos. 50-440 And 50-441.(Cleveland Electric Illuminating Company)
Division of Licensing.
February 1984.
142pp.
8402240381.
22381:118.
Supplement No. 4 to the Safety Evaluation Report on the
)
application filed by the Cleveland Electric Illuminating Company on j
behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant. Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been l
prepared by the Office of Nuclear Reactor Regulation of the U.S.
i Nuclear Regulatory Commission.
The facility is located in Lake County, Ohio.
This supplement, No. 4 further updates the SER and j
Supplements 1 through 3 by providing the results of the staff's review i
of information submitted by the applicant by letter addressing some of 1
the issues listed in Sections 1. 9.
1.10, and 1.11 of the SER that were 4
unresolved at the time Supplement 3 was issued.
I i
l NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER j
PLANTS. Technical Findings Relevant To USI A-1.
SERKIZ,A.W.
Division of Safety Technology.
March 1984.
79pp.
8404090032.
22947:198.
3 This report, which includes responses to public comments, summarines key technical' findings relevant to the Unresolved Safety Issue A-1, Water Hammer.
These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer 1
occurrences.
It should also be noted that this report door not represent a substitute for current rules and regulations.
I l
NUREG-0936 VO2 NO4: NRC REGULATORY AGENDA.Guarterly i
Report,0ctober-December 1983.
- Division of Rules and Records.
i February 1984.
180pp.
8403020165.
22482:212.
The NRC Regulatory Agenda is a compilation of all rules on which i
the NRC has proposed or is considering action and all petitions for l
rulemaking which have been received by the Commission and are pending l
disposition by the Commission.
The Regulatory Agenda is updated and l
issued each guarter.
The Agendas for April and October are published in their entirety in the Federal Register while a notice of l
cvailability is published in the Federal Register for the January and July Agendas.
NUREG-0940 VO2 NO4: ENFORCEMENT ACTIONS:SIGNIFICANT ACTIONS RESOLVED.Guarterlg Progress Report,0ctober-December 1983.
Director's Of fice, Office of Inspection and Enforcement.
January-1984.'
437pp.
840221C028.
22341:296.
This compilation summarises significant enforcement actions that 8
hevo boon rocc1vod during ono quartorly poriod (Octobor - Docochor 1903) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these cnforcement actions and the licensees' responses.
It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC,
.in the interest of promoting public health and safety as well as common defense and security.
NUREG-0975 VO2: COMPILATION OF CONTRACT RESEARCH FOR THE MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING TECHNOLOGY. Annual Report Division of Engineering Technology.
March 1984.
For FY 1983.
- 312pp.
8404170012.
24092:183.
This report presents summaries of the rewearch work performed during Fiscal Year 1983 by laboratories and organizations under contracts administered by the NRC's Materials Engineering Branch, Office of Nuclear Regulatory Research.
Each contractor has written a moro complete and detailed annual report of their work which can be obtained by writing to NRCs however, we believe it is useful to have a nuncary of each contractor's efforts for the year combined into one volume.
NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity B-10.
- Division of Systems Intogration (post 811005).
February 1984.
75pp.
8403220326.
22721:112.
This report, prepared by the staff cf the Office of Nuclear Rocctor Regulation and its consultants at the Brookhaven National Lchoratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design.
Its issuance completes NRC Generic Technical Activity B-10,'" Behavior of BWR Mark III Containment."
On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric-Company developed LOCA-related hydrodynamic definitions for use in the design of the standard Mark III containment.
The staff and its consultants have reviewed these load definitions and their bases and conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions.
The staff approved acceptance criteria for LOCA-related hydrodynamic loads are provided in Appendia C of this report.
NUREG-0993 RO1: REQULATORY ANALYSIS FOR USI A-1,
" WATER HAMMER."
SERKIZ,A.W.
Division of Safety Technology.
March 1994.
30pp.
C404090143, 22947:309.
NUREG-0993, Revision 1 is the staff's regulatory analysis dealing with the resolution of the Unresolved Safety Issue A-1, Water Hammer.
This report contains the value-impact analysis for this issue, public ccmments received, and staff' response, or action taken, in response to those comments.
The staff's technical findings regarding water hammer in nuclear power plants are contained in NUREG-0927.
NUREG-1007 S01: SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL AND POWER INCREASE FOR THE NATIONAL BUREAU DF STANDARDS i
REACTOR.' Docket No.
50-184.-
- Division of Licensing.
March 1984.
1Cp p. -
8404120323.
24035:133.
9
f Cupplocont 1 to tho Sofoty Evoluotion Roport (SER) reintod to tho renewal of the operating license and for a power increase (10 MWt to 20 MWt) for the research reactor at the National Bureau of Standards (NBS) facility has been prepared by the Office of Nuclear Reactor Regulation of the U.S.
Nuclear Regulatory Commission.
The reactor facility is located in Montgomery County, Maryland.
This supplement reports on the review of the licensee's emergency plan, which had not been reviewed at the time the Safety Evaluation Report (NUREG-1007) eas published, and the review of the NBS application by the Advisory 1
Committee on Reactor Safeguards, which was completed subsequent to the publication of the SER.
i NUREO-1015: STATE SURVEILLANCE OF RADI0 ACTIVE MATERIAL TRANSPORTATION.
Final Report. SALOMON S.N.
Office of State Programs, Director.
I February 1984.
72pp.
8403230190.
22759:048.
]
The main ob ective of this final report on the State surveillance J
of the transportation of radioactive material (RAM) is to suggest the j
most cost-effective inspection areas where enforcement actions might i
bo taken by States during their participation in the State Hazardous i
Materials Enforcement Development (SHMED) Program of the U.S.
D2partment of Transportation (DOT).
On the basis of the lessons i
learned from the surveillance program, these actions ars enforcement i
at low-level radioactive burial sites by means of civil penalties and ofte use suspensions enforcement at airports and at terminals that forward freights and enforcement of courier companies.
More effective 1
and efficient enforcement can be achieved through instrumented police patrol cars and remote surveillance because they require the least cmount of time of enforcement personnel.
Also, there is a strong relationship between effective emergency response and enforcement because the appropriate shipping papers, placarding and knowledge of i
cppropriate emergency response procedures lead to improved emergency
{
rosponse.
These lessons originate from a ten-State surveillance i
progra.n from 1977 through 1981 Jointly sponsored by the U.S.
Nuclear Rogulatory Commission (NRC) and DOT.
States give recommendations in i
the categories of education, training expanded surveillance, coordination and enforcement.
Topics of special interest covered include low-level radioactive waste disposal sites, airports, cargo i
j terminals, highways, ports, and accidents and incidents.
The relationship to other studies, the status of the SHMED Program, a cynopsis of State RAM surveillance reports, and NRC/ DOT expenditures i
are given.
Also, relevant laws and regulations and a selected bibliography are included.
NUREG-1022 801: LICENSEE EVENT REPORT SYSTEM.Deacription Of System And i
Ouidelines For Reporting. HEBDON,F.J.
Director's Office.
February l
1994.
58pp.
8403070121, 22561:308.
On July 26, 1983, the Commission published in the Federal Rogister a final rule (10 CFR 50.73) that modified and codified the Licensee Event Report (LER) system.
The rule became ef fective on J:nuary 1, 1984.
In September 1983, the NRC published NUREO-1022 which provides supporting information and guidance that is of interest to persons responsible for the preparation and review of LERs.
The information contained in NUREG-1022 includes:
(1) a brief description of how LERs are analyzed by the NRC, (2) a restatement of the guidance centained in the Statement of Consideration that accompanied publication of the LER rule,' (3) a set of examples of potentially reportable events with staff comments on the actual reportability of occh event, (4) guidance on how to prepare an LER, including the LER 10
~ -
..h forms, and (5) guidanco on submittel of LERs.
Subsequently, during h.
the period from October 25, 1983 to November 16, 1983, the NRC staff
",b.s held five regional meetings to discuss the scope and content of the ijy LER rule with utility and NRC regional representatives.
During these 24r4 neetings, numerous questions arose and were answered.
This supplement
.jifl to NUREC-1022 contains a summary of the questions asked and the
,; c.
answers given.
NUREG-1039: REVIEW AND EVALUATION OF THE NUCLEAR RECULATORY COMMISSION bC SAFETY RESEARCH PROGRAM FOR FISCAL YEAR 1985.
- ACRS - Advisory
[d Committee on Reactor Safeguards.
February 1984.
74pp.
8403070385.
g,j 22561:234.
w.i p[j 6 l'i Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on r
the safety research program of the Nuclear Regulatory Commission.
p{-
3; This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1985.
The report c
contains a number of comments and recommendations, lY NUREG-1040: FY 1985 BUDGET ESTIMATES.
- Division of Budget & Analysis.
~;"
January 1984.
68pp.
8402210188.
22346:072.
iCJ This report contains the fiscal year budget justifications to Congress.
The budget estimates for salaries and expenses for fiscal year 1985 provide for obligations of $468,200,000 to be funded in total by a new appropriation,
,. (
% l.:
NUREG-1042: TECHNICAL SPECIFICATIONS FOR SUSGUEHANNA STEAM ELECTRIC i/
STATION UNIT NO.2. Docket No. 50-388.(Pennsylvania Power And Light t'
Company) HOFFMAN,D.R.
Division of Licensing.
March 1984.
519pp.
_s-8404100519.
22978:001.
M' Susquehanna Steam Electric Station, Unit 2 Technical Ji Specifications were prepared by the U.
S.
Nuclear Regulatory Commission to set forth the limits, operating conditions, and other 4,,
requirements applicable to a nuclear reactor facility as set forth in
?.
b5" Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public.
- p.g. i y
NUREG-1043: SAFETY EVALUATION REPORT RELATED TO THE RENEWAL OF THE
~
OPERATING LICENSE FOR THE TRAINING AND RESEARCH REACTOR AT THE 1
UNIVERSITY OF MARYLAND. Docket No. 50-166.
- Division of Licensing.
l93 March 1984.
73pp.
8404160225.
24065:294.
?g This Safety Evaluation Report for the application filed by the
~ ^'
University of Maryland, (UMD) for a renewal of operating license R-70 c/"
to continue to operate a training and research reactor facility has
("
been prepared by the Office of Nuclear Reactor Regulation of the U.S.
31,
Nuclear Regulatory Commission.
The facility is owned and operated by
'? ?
the University of Maryland and is located at a site in College Park,
_ 1; Prince Georges County, Maryland.
The staff concludes that this
+,
training teactor facility can continue to be operated by UMD without
- q endangering the health and safety of the public.
y i
L.
NUREG-1045: CUIDANCE ON THE APPLICATION OF COMPENSATORY SAFEGUARDS
'i.
MEASURES FOR POWER REACTOR LICENSEES. BLUMENTHAL H.S.
Division of i o Safeguards.
January 1984.
10pp.
8402170517.
22320:024.
j' This NUREO provides criteria and examples to be used by power 4-4 ll
.- c
- - - ~
i rocctor licensos and the NRC staff in datormining the ecceptability of f
compensatory safeguards measures.
i 1
NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Report For Comment OSTRDWSKI N.4 NICHOLSON,T.J.; ALEXANDER,D.H.s et al.
Division of j
Health, Siting & Waste Management.
Fabruary 1984.
43pp.
8402240373.
22380:264.
The Nuclear Regulatory Commission (NRC) recently published final regulations related to the disposal of high-level radioactive wastes in geologic repositories (46 FR 13971 and 48 FR 28194).
These j
regulations were limited to geologic repositories in the saturated 1
zone since earlier Department af Energy program plans emphasized fully saturated geologic media.
However, the Department of Energy recently j
has initiated preliminary studies in unsaturated geologic media, and
}
requested that NRC reexamine and modify 10 CFR Part 60 so that it will apply to all geologic media.
This request also was made by several j
commenters on the proposed 10 CFR Part 60 technical criteria.
NRC has j
considered this request and has proposed amendments to ensure that the l
provisions of 10 CFR Part 60 are equally applicable to waste disposal l
in either the saturated or unsaturated zone.
In reaching this i
decision. NRC conducted a detailed study of the arguments presented by
{
the public commenters, the issues involved in disposal within the unsaturated zone, and the relative attributes and concerns associated with disposal in the unsaturated zone.
These points are discussed.in this document.
The NRC staff has concluded that disposal within the unsaturated zone is possible, provided that the site and the design of l
the geologic repository are capable of meeting the performance objectives of 10 CFR Part 60.
t f
NUREG-1049: ENVIRONMENTAL IMPACT APPRAISAL FOR RENEWAL OF SPECIAL 4
NUCLEAR MATERIAL LICENSE NO. SNM-42. Docket No. 70-27. (Babcock &
Wilcox Company, Naval Nuclear Fuel Division).
- Division of Fuel j
Cycle & Material Safety.
March 1984.
87pp.
8403270267.
22787:235.
This Environmental Impact Appraisal is issued by the U.S.
Nuclear i
Regulatory Commission in response to an application submitted by Babcock & Wilcox Company, Naval Nuclear Fuel Division, for renewal of l
Special Nuclear Material License No. SNM-42.
l I
NUREG-1050 DRFT: PROBABILISTIC RISK ASSESSMENT (PRA): STATUS REPORT AND, GUIDANCE FOR REGULATORY APPLICATION. Draf t Report For Comment.
Division of' Risk Analysis & Operations (post 840429).
February 1984.
337pp.
8402130612.
22215:001.
The Commission's Safety Goal Policy Statement in NUREG-OBBO, Rev 1,
directs the staff "...to collect available information on PRA studies and prepare a reference document that describes the current status of knowledge concerning the risk of plants licensed in the US."
The document discusses.the purpose and content of a PRA and identifies the PRAs and other probabilistic studies performed to date.
It then discusses the level of maturity and uncertainties associated with the various elements of PRA methodology es well.as those generic insights-derived from studies performed.
Finally, potential uses of PRA in l
regulation are evaluated.
l NURE0/CP-OO48 VO1: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY'
.INFORMATION MEETING. SZAWLEWICZ,S.A.
Srawlewicr, S. A.
. January 1984.
12
721pp.
D401310150.
22030:001.
The papers published in this report were presented at the Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers describe the results and program plans in nuclear roactor safety research conducted in this country and abroad.
l International participation in the exchange of nuclear safety research information is consistently encouraged by the Nuclear Regulatory Ccemission and was exemplified at this meeting by the relatively large number of papers (23) given by representatives of seven different European countries. Japan and Taiwan.
Volume 1 reports information presented at the a.
Plenary Session, b.
Integral Systems Experiments, c.
Separate Effects, d.
Foreign Programs in Thermal Hydraulics, and e.
The EPRI Safety Research Cossion.
i l
NUREG/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING. SZAWLEWICZ,S.A.
Szawlewicz, S. A.
J nuary 1984.
370pp.
8401260097.
21988:001.
The papers published in this report were presented at t!e Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers describe the results and program plans in nuclear roactor safety research conducted in this country and abroad.
International participation in the exchange of nuclear safety research information is consistently encouraged by the Nuclear Regulatory Ccamission and was exemplified at this meeting by the relatively large number of papers (23) given by representatives of seven different European countries, Japan and Taiwan.
Volume 2 reports information presented on a.
Pressurized Thermal Chocks b.
Code Assessment and Improvements c.
2D/3D Research Program 4
cnd d.
Nuclear Plant Analyzer Program.
NUREG/CP-OO48 V03: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING. SZAWLEWICZ,S.A.
Szawlewicz, S. A.
January 1984.
705pp.
8401260096.
21986:001.
The papers published in this report were presented at the i
Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers describe the results and program plans in nuclear roactor safety research conducted in this country and abroad.
International participation in the exchange of nuclear safety research i
information is consistently encouraged by the Nuclear Regulatory i
Ccomission and was exemplified at this meeting by'the relatively large i
number of papers (23)~given by representatives of seven different European countries, Japan and Taiwan.
Volume 3 reports information presented on a.
Containment Systems Rosearchs b.
Status of Source Term Reassessments c.
Fuel Systems Rosearch Program, and d.
Risk Analysis.
NURE0/CP-0048 VO4: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING. SZAWLEWICZ,S.A.
Szawlewiez, S. A.
January 1984.
470pp.
8401260108.
21969:327.
The papers published in this report were presented at the Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers de1cribe the results and program plans in nuclear 13
l reactor safety research conducted in this country and abroad.
International participation in the exchange of nuclear safety research inf orma tion is consistently encouraged by the Nuclear Regulatory Commission and was exemplified at this meeting by the relatively large number of papers (23) given by representatives of seven different European countries, Japan and Taiwan.
Volume 4 covers the sessions on Materials Engineering Research.
NUREG/CP-OO48 VOS: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING. SZAWLEWICZ,S.A.
Szawlewicz, S. A January 1984.
353pp.
8401250162 21950:254.
The papers published in this report were presented at the Eleventh Water, Reactor Safety Research Information Meeting held at the National Dureau of Standards, Gaithersburg,' Maryland, October 24-28, 1983.
The papers describe the results and program plans in nuclear reactor safety research conducted in this country and abroad.
International participation in the exchange of nuclear safety research information is consistently encouraged by the Nuclear Regulatory Commission and was exemplified at this meeting by the relatively large number of papers (23) given be representatives of seven different European countries, Japan and Taiwan.
Volume 5 reports information presented on a.
Mechanical Engineerings b.
Struc tural Engineerings c.
Seismic Research Programs d.
Instrumentation and Control Program, and e.
Research on Equipment Survival in Accidents.
NUREG/CP-0048 V06: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING. SZAWLEWICZ,S.A.
Szawlewicz, S. A.
January 1984.
206pp.
8401250125.
21950:046.
The papers published in this report were presented at the Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers describe the results and program plans in nuclear reactor safety research conducted in this country and abroad.
International participation in the exchange of nuclear safety research information is consistently encouraged by the Nuclear Regulatory Commission and was exemplified at this meeting by the relatively large number of papers (23) given by representatives of seven different European countries, Japan and Taiwan.
Volume 6 reports information presented on a.
Human Factors Researchs b.
Safeguards Researchs c.
Emergency Preparednesss d Process Control, and e.
Occupational Radiation Protection.
NUREG/CP-0049: PROCEEDINGS OF THE WCRKSHOP ON SPENT FUEL / CLADDING REACTION DURING DRY STORAGE. REISENWEAVER,D.
Division of Engineering Technology.
March 1984.
499pp.
8404130225.
24047:069.
This document presents the papers that were presented at the workshop on spent fuel dry storage research which was held in Gaithersburg, MD on August 17-18, 1983.
NUREG/CP-0050: PROCEEDINGS OF THE INTERNATIONAL BETA DOSIMETRY SYMPOSIUM. Held at Washington,DC February 15-18,1983.
- Office of Nuclear Regulatory Research, Director.
Energy, Dept. of.
Health Physics Society.
January 1984.
670pp.
8402100499.
22209:001.
At the International Deta Dosimetry Symposium, 1982, invited 14
=
1ecturoro proconted introductory oummarion for conigned topico and chaired both technical sessions and related workshops.
These proceedings contain the technical papers that were presented, summaries of each of the workshop discussion sessions, and the final oummary.
1.
Review the current state-of-the-art in beta dosimetry and the caplied problems throughout the nuclear indust?gs 2.
Review ongoing research and development and new technology.
3.
Stimulate vigorous interchange on an international basis to oncourage new ideas and technology transfers 4.
Review biological effects and explore the need for better-defined protection standards.
5.
Provide 2 public record of the above inf orma tions and 6.
Charge the industry and advisory bodies to provide improved technology and applied techniques as well as more clear guidance for worker protection.
NVRE0/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONINO NUCLEAR r
REACTORS AT MULTIPLE-REACTOR STATIONS. WITTENBROCK,N.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1982.
339pp.
8401230677.
21901:083.
j Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) cnd large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations.
Three decommissioning alternatives are studied:
DECON (immediate decontamination), SAFSTOR (safe storage followed by l
deferred decontamination), and ENTOMB (entombment).
Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to
{
be unavailable at a single-reactor station, and applying these ostimated impacts to the decommissioning costs and radiation doses ostimated in previous PWR and BWR decommissioning studies.
The j
multiple-reactor-station features analyzed are:
the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services.
i NURE0/CR-2000 V02N12: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of December 1983.
- Dak Ridge National Laboratory.
January 1984.
l 169pp.
8402060529.
ORNL/NSIC-200.
22092:143.
1 This monthly report contains Licensee Event Report (LER) operational information that was processed into the LER data file of the Nuclear Safety Information Center (NSIC) during the one month portod identified on the cover of this document.
The LERs, from which this information is derived, are submitted to the Nuclear Regulaturg Commission (NRC) by nuclear power plant licensees in accordance with foderal regulations.
Procedures for LER reporting are described in dotail in NRC Regulatory Guide 1.16 and NUREG-0161, Instructions for Preparation of Data Entry Sheets for Licensee Event Reports.
The LER i
oummaries in this report are arranged alphabetically by facility name cnd then chronologically by' event date for each facility.
Component, system,' keywords, and component vendor indexes follow the summaries.
The components, systems, and vendors are those identified by the i
utility when the LER is initiateds the keywords are assigned by the ccmputer using correlation tables from the Sequence Coding and Search i
System.
i 15
.m-, _,
__m..,, _,,.
,y
-y.
-_..,y..
__.___Z
=
NUREG/CR-2OOO VO3 N1: LICENSEE EVENT REPORT (LER) COMPILATIOM.For Month
--J Of January 1984.
- Oak Ridge National Laboratory.
February 1984.
ll 123pp.
8403070392.
ORNL/NSIC-2OO.
22554:092.
=E See NUREG/CR-2OOO.VO2,N12 abstract.
4f at NUREC/CR-2OOO VO3 N2: LICENSEE EVENT REPORT (LER) COMPILATION.For Month 2E Of February 1984.
- Oak Ridge National Laboratory.
March 1984.
zu 167pp.
8404020225.
ORNL/NSIC-2OO.
22876:160.
See NUREG/CR-2OOO,VO2,N12 abstract.
2; imm NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS. LUDWICK,J.D.:
-g MOORE,E.D.
Battelle Memorial Institute, Pacific Northwest
- =
Laboratories.
January 1984.
7pp.
8402060341.
22105:001.
q Safety and Cost information is developed for the conceptual i
decommissioning of five representative independent spent fuel storage
=-
installations.
This information is presented by analyzing major z;
facility components and then developing safety and cost information for the reference installations made up of these components.
Three
-[
decommissioning alternatives are studied to obtain comparisons between "E
costs (in 1981 dollars), occupational radiation doses, potential
,e radiation dose to the public, and other safety impacts.
The
-4 alternatives considered are:
DECON (immediate decontamination),
SAFSTOR (safe storage followed by deferred decontamination), and d{
ENTOMD (entombmont).
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE
=
OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983. DARI,R.A.s CERDONE,R.J.; GINSDERG,T.; et al.
Drookhaven National Laboratory.
March 1984.
159pp.
8404020011.
_f DNL-NUREG-51454, 22876:001.
The Advanced and Water Reactor Safety Research Programs Guarterly Progress Reports have been combined and are included in this report entitled, " Safety Research Programs Sponsored by the Office of Nuclear Regulatory Research - Quarterly Progress Report."
The projects reported are the following: HTCR Safety Evaluation, SSC Development, Validation and Application, CRDR Dalance of Plant Modeling, Thermal-Hydraulic Reactor Safety Experiments. LWR Plant Analyzer Development, LWR Code Assessment and Application, Thermal Reactor Code Develorment (RAMONA-3D)s Stress Corrosion Cracking of PWR Steam
=
Oener, tor Tubing, Bolting Failure Analysis, Probability BaseJ Load Combinations for Design of Category I Structures. Mechanica? Piping Denchmark Problems: Human Error Data 8or Nuclear Power Plant Safety Related Events. Criteria for Human Engineering Regulatory Guides and Human Factors in Nuclear Power Plant Safeguards.
Y
=
NUREQ/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS. LOOMIS,0.0.s SODA.K.
EG&G, Inc.
October 1982.
74pp.
8307210265.
EGG-22OO.
19688:093.
y A series of experiments was conducted in a scaled model of a pressurized water reactor (Semiscale Mod-2A) to investigate natural a
circulation heat rejection under normal and abnormal operating
=g conditions.
The effects on natural circulation of diminished primary and secondary coolant inventory, as well as the presence of non-condensible gas in the primary, were determined.
Three distinct nodes of natural circulation were found to occur as a function of A
16 L
L
l primcry coolant inventory:
single phase, two phase (liquid continuous), and reflux condensation.
The primary coolant inventory limit for adequate heat rejection was found to be the amount of coolant necessary to keep the core covered.
The presence of nitrogen gas in plausible quantities altered natural circulation behavior, but did not preclude adequate heat rejection.
NOREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY. RYMAN,J.C.a HERMANN, 0. W. s WEBSTER,C.C.; et al.
Oak Ridge National Laboratory.
October 1982.
144pp.
8307250159.
ORNL/CSD-90.
19738:280.
The SAS2 control module and ORIGEN-2 code of the SCALE code system have been used with the standard ORIGEN-S data libraries and the SCALE 27-group ENDF/B-V cross-section library to predict afterheat power and fuel inventories in uranium-fueled pressurized water reactor (PWR) fuel assemblies. Dased on present comparisons with measured data cnd on previous experience, it is concluded that this combination of codes and data bases is properly qualified for the calculation of efterheat power in uranium-fueled PWR fuel assemblies. The prediction of fission product fuel inventory data for fuel samples from three PWR fuel assemblies appears to be adequate, but the prediction of actinide inventory data is seen to be quite conservative with respect to measured data. Additional investigation of the differences between calculated and measured inventory parameters, improvements in the SAS2 cross section treatment, and acquisition of additional experimental data appear to be needed to qualify the SAS2, ORIGEN-2, and data base combination for uranium-fueled PWR fuel inventory calculations. It was determined, howevere that predicted values of af terheat power for three uranium-fueled PWR fuel assemblies were in good agreement (about 5% conservative) with measured values.
NUREO/CR-2679 VO3: ADVANCED REACTOR SAFETY RESEARCH GUARTERLY REPORT. JULY-SEPTEMBER 1982.
- Sandia Laboratories.
March 1984.
244pp.
8404020211.
SANDB2-0904.
22077:001.
Sandia National Laboratories is conducting, under USNRC's sponsorship, phenomenological research related to the safety of commercial nuclear power reactors.
The overall objective of this work is to provide NRC a comprehensive data base essential to (1) defining key safety issues, (2) enderstanding risk-significant accident sequences, (3) developing and verifying models used in safety assessments, and (4) assuring the public that power reactor systems will not be licensed and p1 meed in commercial service in the United States without appropriate consideration being given to their effects on health and safety.
Together with other programs. the Sandia effort is directed at assuring the soundness of the technology base upon which licensing decisions are made.
This report describes progress in a number of activities dealing with current safety issues relevant to both light water and breeder reactors.
The work includes a broad range of experiments to simulate cecidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development cnd verification of the complex computer simulation models and codes usod in accident analysis and licensing reviews.
Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance 17
undor o brocd varioty of cbnormal conditions.
Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with sever LWR accidents, and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.
NUREG/CR-2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE CONTAINING CHELATING CECONTAMINATION CHEMICALS. PREMUZIC,E.T.s MANAKTOLA,H.K.
Brookhaven National Laboratory.
February 1984.
56pp.
8402240378.
DNL-NUREG-51593.
22380:309.
Selected trench waters from several low-level waste disposal sites have been analyzed for the presence of chelating decontamination chemicals.
Several methods for decomposition of chelating agents used in decontamination processes are discussed.
Specifically, nitriloacetic acid (NTA), ethylenediamine tetra acetic acid (EDTA),
and diethylene triamine pentaacetic acid (DTPA) decomposition properties under thermal, biological, oxidative, and photochemical conditions are reviewed and discussed in the light of currently available information.
Based on the analysis of the information, it is concluded that combustion and oxyphotolysis may be worth further exploration as possible methodologies for the degradation of chelating decontamination chemicals.
NUREG/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS. LONGEST A.W.s CROWLEY,J.L.s CHAPMAN,R.H.
Oak Ridge National Laboratory.
October 1982.
54pp.
8307210260.
ORNL/TM-8413.
19688:167.
Five single-rod, heated-shroud replicate burst tests were conducted to study statistical variations in Zircalog cladding deformation under simulated loss-of-coolant accident conditions. The test conditions used (low steam coolant flow and a heating rate of *10 K/s to tube failure at '775 C) were conducive to large deformation and matched those used in two of the Multirod Burst Test Program bundle tests so that the results could be used to aid in interpretation of differences observed for individual rods in bundle tests.
The results established estimates of variations that can be expected for freely deforming tubes under these test conditions. The data also indicated a potential for rod-to-rod mechanical interactions in a large bundle.
NUREG/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE,PH AND BORIC ACID CONCENTPATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL CORROSION LOYOLA.V.M.s WOMELSDUFF J.E.
Sandia Laboratories.
January 1984.
31pp.
8402230378.
SAND 82-1179.
22376:177.
The corrosion of galvanized steel, to produce hydrogen gas, will occur if sprays operate during a Loss-of-Coolant Accident in a Light Hater Reactor.
The ratos of hydrogen generation, however, are variable and dependent on accident and post-accident conditions.
This report describes a study designed to identify the important parameters (temperature, p H, and boric acid concentration) in determining the rates of hydrogen generation from Light Water Reactor containment building spray solutions.
The data are gathered over a wide range of temperature, p H, and boric acid concentration, and are used in a j
two-level, three-factor factorial experiment to determine the relative importance of the three parameters to the hydrogen' generation process.
A statistical treatment of the data gives an indicatinn of the relative importance of the parameters (temperature, p H, boric acid 18
concontration) and of their intorections.
It ettempts to fit the data to o relatively simple equation to model the interactions of the various parameters.
NUREC/CR-2815: PRODADILISTIC SAFETY ANALYSIS PROCEDURES CUIDE.
BARI,R.A.s PAPAZOCLOU,I.A.s BUSLIK.A.J.s et al.
Brookhaven National Laboratory.
January 1984.
234pp.
04G2060484.
BNL-NUREG-51559.
22109:014.
A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs.
It will be revised as comments are received, and es experience is gained from its use.
The probabilistic safety essessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues effecting reactor safety.
This guide addresses the determination of the probability (per year) of core damage resultir.g from accident initiators internal to the plant, and from loss of offsite electric power.
The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage occident sequences, and an explicit treatment and display of uncertainties for the key accident sequences.
Ultimately, the guide vill be augmented to include the plant-specific analysis of in-plant processes (i.e.,
containment performance) and the risk associated with outornal accident initiators, as consensus is developed regarding suitable methodologies in these areas.
This guide provides the otructure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making.
Methodology is treated in the guide only to the outont necessary to indicate the range of methods which is acc ep tab les emple reference is given to alternative methodologies which may be utilized in the performance of the study.
NUREO/CR-2824 V01: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUDING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
DODD,C.V.s DEEDS,W.E s MCCLUNG,R.W.
Oak Ridge National Laboratory.
October 1982.
9pp.
8307210268.
ORNL/TM-8418/V1.
19672:304.
Eddy-current methods provide the best in-service inspection of steem generator tubing, and these techniques can produce ambiguity because of the many independent variables that affect the signals.
This development program has used mathematical models and has developed or modified computer programs to design op timum probes, instrumentation, and techniques for multifrequency multiproperty onominations.
Interactive calculations and experimental measurtments have been made with modular eddy-current instrumentation and a minicomputer.
These establish the coefficients for the complex oquations that define the values of the desired properties (and the otteinable accuracy) despite changes in other significant variables.
Tho computer programs for calculating the accuracy with which various properties can be measured indicate that the tubing wall thickness and the defect size can be measured much more accurately than is required, ovon when other calculations show that an array of small pancake coils prossed against the inner wall of the tubing can detect and locate sno11 flaws on the outer wall of the tubing with much greator accuracy cnd reliability than can the usual larDe circumforential coils.
We cro continuing to investigate such arrays.
I 19
}
'NURES/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES. WHITE W.S.
Argonne National Laboratory.
March 1984.
115pp.
8404130132.
ANL/ES-128 R01.
24048:221.
The DIRECTORY AND PROFILE OF LICENCED URANIUM-RECOVERY FACILITIES presents facts, data, and information about conventional mills, i
in-situ mining facilities, heap leach o p e r s '. l o n s, and other operations l
which process and produce marketable quantities of yellowcake.
In the l
United States, such facilities are found in Agreement States (Arizona, i
Colorado, Florida, Louisiana, New Mexico, Texas, and Washington) and in Non-Agreement States (South Dakota, Utah and Wyoming).
Each facility is described on a case-by-case basis.
Reporting of i
information on the conventional uranium mills begins with a brief j
narrative description that outlines general and specific characteristics about the site.
Data sheets summarize the principal operating characteristics of the facility by listing the following i
in f orma ti on:
location / ownership, licensing data, processing of t
uranium, characteristics of effluent releases and/or tailings, and f
radiological parameters.
For in-situ and heap leach facilities, only j
data sheets are included.
1 1
NUREG/CR-2896 VO1: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT l
8 INGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User 's Manual.
l DOMANUS,H.M.s SCHMITT R.C.s SHA,W.T.4 et al.
Argonne National Laboratory.
March 1984.
327pp.
8403300261.
ANL-82-25 VO1.
22839:217.
i The COMMIX-1A computer program, the improved version of COMMIX-1, l
1s designed to analyze steady-state / transient, single phase, three-dimensional fluid flow with heat transfer in reactor components i
and multicomponent systems.
The concepts of volume porosity,
{
directional surface permeability, distributed resistance, and j
distributed heat source or sink is used to model a flow domain with stationary structures.
The new porous-media formulation permits simulation of either a single component or a multicomponent system.
]
The conservation equations of mass, momentum, and energy based on the j
new porous-media formulation are solved as a boundary-value problem in 4
space and an initial-value problem in time, j
This report (Volume I )' describes in detail the basic equations, i
formulations,-solution procedures, flow charts, rebalancing scheme for t j
faster convergency, options available to users, models to describe the auxiliary phenomena, input instructions, and two sample problems.
The i
}
. Volume II assembles and summarizes the results of many simulations l
l that have been performed with COMMIX-1A computer program.
t i
l NUREG/CR-2996 VO2: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF' SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Verification. DOMANUS.H.M.s SCHNITT,R.C.: SHA.W.T.
Argonne National l
Laboratory.
February 1994.
95pp.
8403300285.
ANL-82-25 VO2.
+
i 22840:192.
This report assembles and summarises the results of many simulations that have been performed with COMMIX-1A computer prcgram since the beginning of its development in 1976.
The COMMIX-1A is a
.three-dimensional, time-dependent, single-phase computer program for thermal-hydraulic analysis of component / multicomponent systems'under i
normal /off-normal operating conditions.
This report compiles most simulations for which comparisons with experimental measurements or-analytical solutions have been made.
20 4-
-.m------a-4
NOREQ/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE EODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED HCDA. ZANOTELLI,W.A.; MILiER,0.D.s CRAVEN,S.M.
Mound Facility /Monsanto Research Corp.
October 1982.
18pp.
8307210255.
MLM-2983.
19688:297.
During the main thrust of the HCDA studies, it was found that sodium uranates, especially (3)NaU(4)O. were formed when the Na-U-O system was subjected to high temperatures approximating those of the HCDA.
Mechanisms through which these rather complicated compounds are formed remain unknown.
The purpose of these SIMS and ESCA studies was to detect the formation of any precursor ion species to the sodium uranates.
The main species detected from the Ar+ excited positive SIMS analyses of oxides in salts of uranium were (2)UO+,
JO+,
and U+.
The main ion detected from the Ar+ excited SIMS analyses of a (2)Na(2)U(7)O or of a uranium dioxide - disodium oxide pellet or from o sodium film deposited on a uranium metal foil.
ESC analyses show peak shapes and binding energies for the (2)Na(2)U(7)O pellet that are different from those for the U-Na foil samples and the uranium dioxide
- disodium oxidee pressed pellet. The ESCA results agree with theory and support the presence of (2)U(7)O = in (2)Na(2)U(7)O however, SIMS cnalyses show no evidence of possible uranate precucsor formation in on Ar+ sputtered ion beam.
NOREG/CR-2932 V02: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CADLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
MINOR,E.E.s FURGAL,D.T.
Santia Laboratories.
November 1902.
65pp.
8307210257.
SAND 81-2027.
19688:222.
Electric cables with fire-retardant chemically crosslinked polyolefin extruded insulation containing factory-made conter-conductor splices and insulation repairs manufar,tured by Ooneral Electric Company were used in a methodology test of the IEEE Standard 383-2974.
This standard is concerned with tha ability of cables to function during and following erposure to aging and LOCA/MSLB environments.
Cable specimers were radiation aged at a low-dose rate and then thermally aged to simulate a 40-year containment exposure.
After aging, the specimens werr subjected to LOCA radiation and a 33-day steam and chemical spray exposure.
The cables were electrically loaded and functioned without failure during cnd after LOCA steam and chemical spray exposure.
Insulation rosistance measurements were taken during the exposure sequence.
Subsequent to the exposures, hipot and mandrel bend tests w6re conducted.
Test results indicate that the methods given,ix IEEE 383-1974 are adequate to show that cables can function-and support control operations during and after a LOCA/MSLB o# the severity simulated by the test.
Further, the presence of center-conductor oplices and insulation repairs did not appear to degrade cable' performance.
NUREG/CR-2970 V04: MATERIALS SCIENCE AND TECHNOLG0Y DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS h
EEPORT OCTOBER-DECEMBER 1982. SHACK,W.J.s RECT,J.s"MASSNER,T.F.s et at.
Argonne National Laboratory.
January 1984.
.1RSpp.
8401160443.
ANL-82-41.
21824:001.
This progress report summarizes the Argonne National Laboratory
.vek performed during October, November, and December 1983 on water roactor safety problems.
The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors.
Transient Fuel Response and Fission Product Release, Clad Properties 21
b for Codo Verification and Long-Term Embrittismont of Cost Duplex i
Stainless Steels in LWR Systems.
u NURCG/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT
- ( "
SITING. DURFEE.R.C.1 COLEMAN.P.R.
Oak Ridge National Laboratory.
December 1983.
104pp.
8402170439.
ORNL/CSD/TM-197.
22302:166.
The Nuclear Regulatory Commission is in the process of reviewing guidelines and regulations associated with population distribution criteria around nuclear power plant sites, the purpose of this paper is to describe the methodology for calculating population distribution in the U S.
and then evaluating specific population criteria and their effect upon the selection of future nuclear power plant sites.
t Through the use of computer systems, different alternatives may be evaluated for individual sites or For major regions of the country to determine their restrictiveness on siting nuclear plants.
Two types of criteria were used.
They involved the analysis of population distributions radially out frcm each possible site and the study of I
angular distributions around each site.
Results are presented in both i
tabular and graphic form using national, regional, and site-level computer maps.
NUREG/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA. KELLY,M.J.s RUSH,R.M.s OTT,W.R.s et al.
Oak Ridge National Laboratory.
January 1984.
i 44pp.
8402170417.
ORNL-5936.
22320:041.
This study evaluates the effect of various alternative population f
i criteria on the availability of suitable sites for new nuclear power plants.
The population criteria investigated include population I
density limits of 500 and 750 persons per square mile within 30 miles of the site and three different limits on the total population in adjacent sectors.
The site availability in the states with higher population density was investigated--using power pools, regional aggregations, and specific sites as appropriate.
The resuIts of this study indicate that the application of any of the alternative population criteria studied will not rule out the use of the nuclear option in the northeast quadrant of the United States The analysis demonstrates that viable sites exist even in the states and service areas with the largest population densities.
These results, together with a cursory examination of the rest of-the United States indicating that both real and potential viable sites are available, confirm that the application of any of the alternative population criteria studies will not preclude the identification of suitable nuclear sites in any region.
NUREC/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BNL AIR SAMPLER. HUCHTON,R.L.s BIRD,S.K.s TKACHYK,J.W.s et al.
Exxon Nuclear Co.,
Inc. (subs. of Exxon Corp.).
February 1984.
52pp.
8403060533.
ENICD-1125.
22522:064.
Three calibration sources.were designed, developed, and-fabricated for a CDV-700 ratemeter equipped with a specially-shielded 6306 G-M detector.
The CDV-700/6306 has been proposed for use with the BNL Air Sampler. designed for radiciodine monitoring upon a nuclear reactor accident.
I Specifically, the three sources were constructed in a geometry l
identical to the BNL air sampler radiciodine absorption canister, l
which is a silver silica gel filled 2.75-inch diameter right circular-
-cylinder with a 1.0-inch diameter annulus, into which the 6306 G-M.
l 22.
l dotoctor to insertod.
As fabricated, occh sourco consisted of an
-cuter stainless steel housing, an inner (133)Ba impregnated polyester i
liner, 4-weight percent silver silica gel media, and a laser welded l
l hormetically-sealed stainless steel lid.
Respectively, the levels of I
(133)Ba, an (131)I simulant, were varied in the three sources to yield nominal CDV-700/6306 instrument responses of 200 cpm, 2,000 cpm and 20,000 cpm.
NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527. CUNNINGHAM,M.E.; LANNING,D.D.
Battelle Msmorial Institute, Pacific Northwest Laboratories.
January 1984.
36pp.
8401310449.
PNL-4542.
22036:234.
Preitradiation characterization data and irradiation data are summarized and postirradiation examination (PIE) data are presented for the six-rod instrumented fuel assembly IFA-527.
This assembly was irradiated in the Halden Boiling Water Reactor, Halden, Norway, as part of the U.S.
Nuclear Regulatory Commission-sponsored Experimental Support and Verification of Single-Rod Fuel Codes Program.
The i
ensembly was irradiated from July 1, 1980, to April 8.
1981, during
)
uhich time rod-average burnups of approximately 1.0 mwd /kgM were obtained.
All six rods had pressure boundary failures prior to removal from the reactor.
The PIE was conducted at the Harwell
'leboratory of the United Kingdom's Atomic Energy Research Establishment.
Examinations were oriented toward discovering the site and cause of rod failure (visual, neutron radiography, leak checking) cnd the effects of operating an assembly with failed rods-(micrography of fuel and cladding).
It was concluded that rod failures occurred in the end fittings and not in the cladding.
No significant fuel or i
cladding microstructural changes were observed.
NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432. LANNING,D.D.s BRADLEY,E.R.
Battelle Memorial Institute, Pacific Northwest Laboratories.
March 1984.
189pp.
8404160201.
PNL-4543.
24065:042.
Preirradiation characterization data and measured in-reactor data cro summarized for the six-rod instrumented Halden fuel essembly i
IFA-432.
Postirradiation data are presented on three of the rods--Rods 1, 6,
and 8--from this assembly.
Rods 1 and 6 operated from December 1975 to June 1981 and accumulated peak burnups of 34 mwd /kgM.
Fuel temperatures, gas pressures, and rod alongation were measured throughout the life of these rods, together with the corresponding power histories.
Posfirradiation observations on the
)
rods are correlated with their design features and operating history.
End-of-life fission gas release data demonstrate the influence of both on-fabricated grain size and the operating history, i
~
1 and:6 experienced classic thermal feedback between fuel Rods temperatures and gas release but had different rates of response, such-that they attained lifetime peak temperatures at different burnups.
D3 tailed measurements of the distribution of retained gas were-i.
.porformed on these two rods, - and the-results are compared with macsured and calculated temperatures and with computer code prodictions.
NUREC/CR-3091 V03: REVIEW OF-WASTE PACKA0E VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
BOO, P.
Brookhaven: National Laboratory.
February 1984.
164pp.
C403070115.
BNL-NUREG-51630.
22562:176.
23
This report is part of an ongoing task to specify tasks that may be used to verify that engineered waste package / repository systems meet the containment and controlled release performance objectives of 10 CFR Part 60.
This report analyzes verification tests form carbon steel container corrosion and the testing methodologies that are cppropriate for evaluating interaction effects between adjacent components in waste packages.
NUREC/CR-3104: AGUIFER RESTORATION TECHNIQUES FOR IN-SITU LEACH URANIUM MINES. DEUTSCH,W.J.s BELL,N.E.
MERCER.B.W.
Battelle Memorial Institute, Pacific Northwest Laboratories.
February 1984.
58pp.
C403230177.
PNL-4583.
22759:121.
In-situ leach uranium mines and pilot-scale test facilities are currently operating in the states of Wyoming, Texas, New Mexico and Colorado.
This report summarizes the technical considerations j
involved in restoring a leached ore zone and its aquifer to t i..
l required level.
Background information is provided on the geology and geochemistry of mineralized roll-front deposits and on the leaching techniques used to extract the uranium.
NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
CREIMANN,L.s FANOUS,F.; KETELAAR,D.s et al.
Iowa State Univ., Ames, I A.
January 1984.
132pp.
8402270207.
22397:225.
A probabilistic description of the seismic resistance of six containment vessels was developed.
A random vibration approach and an advanced first order.second moment reliability method were combined to predict the cumulative distribution of the resistance.
Strain ductility was used as the failure criteria.
BOSOR4 was used to determine linear vibration modes.
Extreme Value Type I distributions were used to characterize the maximum responses (stress resultants).
BOSOR5 was implemented to predict the proportional increase of these maximums'which would cause buckling.
Imperfections were included in the shell models.
Only shell failure modes were considered.
NUREG/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
POLLACK,H.N.s CHRISTENSEN.D.
Michigan, Univ. of. Ann Arbor, MI.
March 30, 1984.
64pp.
8403230131.
22739:232.
Earthquake activity in the Western Ohio-Indiana region is monitored with a precision seismograph network which consists of none l
stations located in-west central Ohio and four stations sited in Indiana.
Five local and near regional earthquakes have been recorded during this report period.
Three events were located outside the otray, near the cities of Kalamazoo, Michigan, Cleveland, Ohio and Cincinnati, Ohio.
Two events occurred in the center of the Ohio array.
A focal mechanism was calculated for the larger of these two events.
This focal mechanism shows mainly strike slip motion on l
cteeply dipping nodal planes, striking at N35 degrees-45 degrees E and l
N50 degrees-70 degrees W.
Both of these planes correspond to local otructures.
NUREG/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC. PARK,J.E.s CROSS K.E.
Oak Ridge National Laboratory.
December _1983.
130pp.
8403260286.
DRNL/TM-8650.
22761:176.
As the world demand for electricity is met by large coal-or 24
. - - ~
,--------------e---
nucloer-fuolod contral generating stations, the effluent streams from j
these plants will have an increasingly important impact on the local onvironment.
The Nuclear Regulatory Commission has a responsibility to assess the impact of proposed and operating nuclear power plants.
l Tc support this NRC mission, a numerical algorithm and associated computer program have been developed to predict the temperatures occurring in the immediate vicinity (the near field) of a hot water discharge from a power plant.
The algorithm is a natural extension of the classic Marker-and-Cell (MAC) technique developed by F.H.
Harlow at the Los Alamos Scientific Laboratory.
ORSMAC (Dak Ridge Simplified Marker and Cell), adds the logic for simple turbulence modeling, onergy conservation and buoyancy effects to the MAC model.
Modern numerical techniques have been used wherever practical.
In this report, the MAC and SMAC (Simplified MAC) algorithms are reviewed, and.the ORSMAC algorithm is described.
The finite difference analogs are given and discussed.
Solutions for several sample problems are presented which illustrate the features of the ORSMAC algorithm.
A complete FORTRAN listing is included with input and sample output.
j NUREG/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2. OSBORNE,M.F.s.LORENZ,R.A.; TRAVIS,J.R.s et al.
Oak Ridge National Laboratory.
March 1984.
60pp.
8404020277.
22873:223.
4 The second in a series of high-temperature fission product release tests was conducted for 20 min at about 1700 degrees C in flowing steam.
The test specimen, a 20-cm-long section of a H.B.
Robinson fuel rod that had been irradiated to a burnup of 28,000 mwd /t, was heated in an induction furnace mounted in a hot cell.
Posttest analyses of the furnace, the thermal gradient tube, l
filters, and other components of the experimental apparatus showed that about 50% of the (85)Kr, (137)Cs, and (129)I were released from the specimen during the test.
In addition, approximately 2% of the (110m)Ag and (125)Sb along with smaller fractions of several other radionuclides were measured by gamma spectrometry.
Spark-source mass spectrometric data from a limited number of samples showed significant j
releases of fission product tellurium and molybdenum, as well as j
structural (zirconium and tin) and furnace (primarily tungsten) i materials.
Metallographic examination of the fuel specimen revealed extensive fractures in the cladding, essentially complete oxidation to ZrO(2), and evidence of fuel-cladding interaction.
i NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR FIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS. ESTUARIES AND. -
COASTAL REGIONS. ERASLAN,A.: LIN, W. s SHARP.R.D.
Oak Ridge National Laboratory.
December 1983.
381pp.
8404030564.
ORNL/TM-8401.
22878:176.
FLOWER is a three-dimensional computer code for simulating fast-transient, free-surface flow, temperature, and salinity J
conditions in rivers, estuaries, and coastal regions.
The model also includes rotational effects (Coriolis force) and is capable of cccomodating wind-stress. coupling.- a capability which enables the model to be applied to large water bodies with significant wind-driven currents, such as the Great-Lakes.
The mathematical formulation
= utilizes the integral form of the governing equations of the discrete-element method.
In this method, interior flow regions are l-
-ropresented as rectangular elements of variable size, while
-impermeable boundary elements are constructed from truncated 25
rectangles, thus allowing accurate representations of complex shorelines.
]
NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE l
PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE. WICHNER,R.P.s SPENCE,R.D.
Oak Ridge National Laboratory.
March 1984.
43pp.
8404020263.
ORNL/TM-8683.
22873:181.
The degree of vaporization of LWR core materials was estimated using a highly idealized procedure involving (1) specification of the phases that are present for both structural and fuel materials (2) estimetion of the vapor pressures exerted by the individual components of each phases and (3) assuming a degree of vaporization of each phase constituent, to allow equilibration between gaseous and condensed species within the assumed pressure vessel volume.
Obviously, the l
degree of vaporization of many core materials is limited by other complex factors such as local mass transport conditions and solid phase dif fusion ratess however, the results obtained in this study serve to illustrate the types of driving forces for vaporization that are present and to give some Indication of the composition of the vaporized material.
Some comparisu,s are provided with estimated degrees of core vaporization from other sources.
In addition to estimated degrees of vaporization, information is included regarding the projected chemical forms of the condensed material for the expected range of oxygen potentials in the reactor
- vessel, f
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUDING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983. DODD.C.V.s DEEDS,W.E.s SMITH,J.H.s et al.
Oak Ridge National i
Laboratory.
March 1984.
22pp.
8404090145.
ORNL/TM-8796/V3.
22971:262.
Eddy-current inspection is the most suitable method for rapid I
boreside evaluation of steam generator tubing.
However, small flaws can be masked by the effects of harmless variables such as. tube supports.
To identify the critical properties accurately and reliably in the presence of extraneous signals caused by variations of unimportant properties, sufficient information is needed to identify harmful variations and to reject harmless ones.
For this reason we have developed instrumentation capable of measuring both the amplitude and phase of the eddy-current signal at several different frequencies l
as well as computer equipment capable of processing the data quickly and reliably.
Our most recent computer-optimized probe design uses an array of small flat " pancake" coils pressed against the inside wall of the steam generator tubing.
Data have been taken with such coils on I
tubes with various combinations of abnormalities.
Data were alsa taken for machined defects in tubes and flat plates to verify our basic flaw theory and to check our inversicn theory for characterizing flaw properties from scans across the defect.
l l
NUREG/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS. THEOFANOUS,T.G.; BELL,C.R.
Los Alamos Scientific Laboratory.
March 1984.
436pp.
8403230216.
.LA-9716-MS.
22740:001.
The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document.
This assessment was performed for the Nuclear Regulatory Commission under the-direction of the CRBR Program Office 26 i-
f I
within the Office of Nuclear. Rocetor Roguiction.
It considored in dotail the accident behavior for three accident initiators that are representative of three different classes of eventss unprotected loss l
of flow, unprotected reactivity insertion, and protected loss of heat l
l oink.
The primary system's energetics accommodation capability was j
dotermined in terms of core events.
This accommodation capability was found to be equivalent to a ramp rate of about 200 $/s applied to a classical two phase disassembly.
This accommodation capability was contrasted to the potential for energetic behavior which was shown to crise only in the advanced core disruption states (gravity driven recriticalities).
The accident behavior was found to be dominated by noutronic activity that was bounded conservatively by 100 $/s events.
Based on a qualitative probabilistic approach, we concluded that nossive failure of the reactor head with associated early challenge to i
the containment building is physically unreasonable.
NUREG/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS. FENTON.D.L.s DALLMAN,D.J.; SMITH,P.R.s et al.
Los Alamos Scientific Laboratory.
January 1984.
13pp.
.8402010111.
LA-9929-MS.
22058:028.
A facility to test the plugging effects of combustion products on high-efficiency particulate air filters has been constructed.
This facility can supply experimental data to support pressure-drop models 1
of filter plugging under fire accident conditions, which are needed for use in an existing fire accident analysis computer code.
The test facility includes a specially designed null-balance filter-weighing system.
The resoluticn of this system is approximately 2 to 3 g out of 14 kg for a commercial O.6-by 0.6-m filter.
Using this system, commercial filters can be tested to provide data with which to correlate pressure drop and smoke aerosol mass accumulation and flow rate.
Some recently accomplished tests and future test plans are discussed.
NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERCENCIES AT NUCLEAR POWER PLANTS. CARDWELL,R.G.s MOUL,D.A.s MCBRIDE.J.A.s et cl.
Union Carbide Corp.
March 1984.
83pp.
8404170575.
Y/DS-178.
24093:272.
This report provides an analysis of the literature and on-site data gathering relating to the actions of security forces at licensed nuclear power plants during safety-related emergencies.
Literature search findings and results of on-site data gathering are furnished and sub Jected to analysis.
Taking into account the analysis provided, oppropriate recommendations are presented.
Recommendations are keyed l
as to how improvements can be made in the regulatory approach and licensee planning and procedures as they relate to the subject matter under examination.
In addition, certain technological problems and issues are examined within the context of the study.
Appendices provide.the results of the literature search, an annotated bibliography, the Data-Collection Guide used.-and additional details rogarding certain aspects of the study that are relevant for further explication of the body of the report.
(
. NUREG/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE HUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL. FEDERMAN,P.J.s l
BARTTER,W.D.; SIEGEL,A.I.s et al.
Applied Science Associates,-Inc.
i Fobruary 1984.
191pp.
8403300325.
ORNL/TM-8755.
22842:007.
27
Tho Job cnolysis of the cloctrician position is part of the work being done within a program that is developing and will evaluate a computer simulation model that will generate maintenance performance reliability data.
This report is the fourth and last in a series of Job analysis studies which characterize maintenance positions in i
nuclear power plants (NPPs).
This characterization takes the form of detailed inf ormation about:
(1) frequency of task performance, (2) time required-for task performance, (3) the training required for adequate task performance, and (4) the perceived consequences of inadequate performance.
Additionally, information is also presented about the mental and perceptual-motor loading imposed by various work functions.
A list of 199 tasks were compiled and verified through a number of visits to NPPs.
Two formal questionnaires concerning these tasks were distributed to 24 NPPs and resulted in a 61% return rate.
Results from the data received from the questionnairec formed the basis of this job analysis.
A statistically significant positive correlation was found between electrician training requirements and the perceived severity of adverse consequences following inadequate task performance.
This and other information from this Job analysis report will have direct influence on the development of the computer simulation model.
NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
EINSIGER,R.E.s COOK,J.A.
Hanford Engineering Development Laboratory.
March 1984.
82pp.
8404110020.
HEDL-TME 83-9.
24002:223.
Westinghouse Hanford Company (WHC) and EG&G-Idaho are jointly conducting a testing program to provide information that the Nuclear Regulatory Commission (NRC) can use to establish a licensing position relative to long-term, low-temperature performance of spent fuel rods in dry storage.
The tests investigate the performance of intact and defected light water reactor (LWR) spent fuel rods in inert gas and unlimited air environments.
The tests consist of placing four H.
B.
Robinson Unit 2 pressurized water reactor (PWR) and four Peach Bottom-II boiling water reactor (BWR) spent fuel rods in a furnace-at 230 degrees C for a maximum of 50 months.
Interim and final examinations are planned to assess behavior during the test.
To establish the initial condition of the test rods, visual examinations of the test rods and crud examinations of companion rods were conducted.
In addition, an open literature evaluation of crud characteristics was compiled.
NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS. BEARE.A.N.s DORRIS,R.E.s BOVELL,C.R.s et al.
General Physics Corp.
January 1984.
190pp.
8403300342.
SAND 83-7095.
22844:070.
The purposes of this study were to empirically establish error rates for control selection and operation during the performance of proceduralized tasks in nuclear power plant control rooms during simulated casualties, and to compare the observed error rates with the human error probabilities in the Handbook of Human Reliability Analysis With Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278 l
l l
NUREC/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGRAM GUARTERLY REPORT JULY-SEPTEMBER 1983. THOMPSON,S.L.
Sandia l
28
l l
Loboratorios.
February 1984.
84pp.
8402280123.
SAND 83-1171.
l 22430:123.
The RELAPS independent assessment project at Sandia National Lcboratories is part of a multi-faceted effort sponsored by the NRC to determine the ability of various system codes to predict the detailed thermal / hydraulic response of LWRs during accident and off-normal conditions.
The version used for the FY82 assessment project
{1,2,3,4) was RELAP5/ MOD 1/ CYCLE 14 {5}, the latest publicly released vorsion available at the time this project was begun.
Brief individual status reports on ongoing LOFT and Semiscale NC cnd UT_ calculation (all being done with RELAP5/ MOD 1), and the MOD 1.5 BCL analyses, are given in the main body of this quarterly, as is the current status of the new UHI plant analyses (with both TRAC-PF1 and RELAP5).
During this quarter, calculations were completed for T'miscale degraded heat transfer natural r.irculation tests S-NC-3 and S- !C-4, for Semiscale transient natural circulation test S-NC-8, and foe LOFT large break test L2-5.
NUREC/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1983. PUGH,C.E.
Oak Ridge National Laboratory.
January 1984.
68pp.
8401230066.
ORNL/TM-8787/V2.
21921:001.
The Heavy-Section Steel Technology (HSST) Program is an engineering research activity conducted by the Oak Ridge National Laboratory for the Nuclear Regulatory Commission.
The program comprises studies related to all areas of.the technology of materials fabricated into thick-section primary-coolant containment systems of light-water-cooled nuclear power reactors.
The investigation focuses on the behavior and structural integrity of steel pressure vessels containing cracklike flaws.
Current work is organized into seven tasks:
(1) program administration and procurement, (2) fracturemechanics analyses and investigations, (3) investigations of i
irradiated materials, (4) thermal-shock investigations, (5) pressure vessel investigations, (6) stainless steel cladding investigations, and (7) environmentally assisted crack growth studies.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 198?
RUGH,C.E.
Oak Ridge National Laboratory.
March 1984.
120pp.
8403300317.
ORNL/TM-8787/V3.-
22826:067.
See NUREG/CR-3334,VO2 abstract.
l 4
NUREG/CR-3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS-EQUIPMENT. ROUNTREE.S.L.
Sandia Laboratories.
January 1984.
44pp.
C402060336.
SANDB2-2933.
22107:272.
Security officer tactical training issues are discussed in relation to the possible implementation of the Tactical. Improvement Package (TIP), utilizing the Engagement Simulat'9n System (ESS) cquipment, by nuclear power plant licensees for security officer tactical training.
The ESS equipment provides the capability to simulate engagement conditions between adversaries armed with weapons which have harmless laser transmitters.
A brief discussion of the TIP-is presented, along with some concerns and consideratione in the use of the TIP.
29
NUREG/CR-3359 V03: PHYSICS OF REACTOR SAFETY.Guarterly Roport, July-Saptember 1983.
- Argonne National Lcboratory.
January 1984.
15pp.
8401230062.
ANL-83-11 V03.
21931:075.
This quarterly progress report summarizes work done during the msnths of July-September 1983 in Argonne National Laboratory's Applied Physics and Components Technology Divisions for the Division of Roactor Safety Research of the U.S.
Nuclear Regulatory Commission.
The work in the Applied Physics Division includes reports on reactor oefety modeling and assessment by members of the Reactor Safety Appraisals Section.
Work on reactor core thermal-hydraulics is performed in ANL's Components Technology Division, emphasizing 3-dimensional code development for LMFBR accidents under natural convection conditions.
An executive summary is provided including a statement of the findings and recommendations of the report.
NUREG/CR-3359 VO4: PHYSICS OF REACTOR SAFETY.Guarterly Report,0ctober-December 1983.
- Argonne National Laboratory.
Fobruary 1984.
22pp.
8404020217.
ANL-83-11 VO4.
22876:329.
See NUREG/CR-3359,VO3 abstract.
i NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND i
MINERALS. MEYER,R.E.; ARNOLD,W.D.; CASE,F.I.
Oak Ridge National Laboratory.
February 1984.
49pp.
840402O260.
ORNL-5978.
22845:284.
Estimation of the rates of migration of nuclides from nuclear waste repositories requires knowledge of the interaction of these nuclides with the components of the geological formations in the path of the migration.
These interactions will be dependent upon the valence state and speciation of the nuclide.
Experiments designed to asasure interaction of multivalent nuclides and minerals must therefore include some form of valence state control.
An olectrochemical method of valence state control was developed which makes use of a porous electrode in a flow system containing a column of the adsorbent.
By use of this method and solvent extraction cnalyses of the valence states, a number of reactions of interest to HLW rep ositories were investigated.
These include the reduction of Np(V) and Te(VII) by crushed basalt and other minerals.
For the reduction of Np(V)Hby basalt, the experiments indicate that the corption of basalt increases with pH and that most of the Np is reduced to Np(IV) which is very difficult to remove from the basalt oven if oxygenated tracer-free solution is added,to the solution.
For the experiments with Tc(VII), the results.are considerably more complicated.
The results of these experiments.are used to-assess some of the techniques and methods currently used in safety analyses of proposed HLW repositories.
NUREG/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNSAT2 - VARIABLY SATURATED FLOW MODEL.(Including 4 Example Problems). DAVIS,L.A.;
NEUMANN.S.P.
Water, Waste & Land. Inc.
December 1983.
218pp.
8403230197.
WWL/TM-1791-1. ~ 22742: 001.
i This report presents documentation and a user's guide for= program UNSAT2.
Mathematical equations and. physical principles utilized to develop the code are presented in Section 2.
The numerical approach-uced (Galerkin Finite Elements) is' presented in Section 3.
Section 4-presents an overview of how problems should be set _up to properly use the code while detailed input instructions are presented-in Section 5.
Output produced by the code is discussed'in Section 6.
Four 30
x oxcmplo prob 1cmo, including scaple input data sets and output data, cro prosonted in Section 7.
Program information and a complete listing of the program is provided in Section 8.
This report was
_propared as part of a project in which the NRC staff was presented a training course on how to properly use this computer program.
Program UNSAT2 can be utilized to analyze flow in unsaturated. partially unsaturated, or fully saturated flow regions.
It is anticipated that the NRC will use the model for checking information provided by a licensee, for evaluation alternative sites and designs for waste disposal, and for comparing their results with results from other methods of solution.
NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants. MELBER,B.D.s OLSON,J.;
SCHREIBER,R.E.s et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
March 1984.
61pp.
8404020220.
PNL-3786.
22875:276.
l The provisions of engineering expertise on shift at commercial nuclear power plants has mainly taken the form of the Shift Technical Advisor (STA).
This person, acting in a capacity that is part I
ongineer and part operator, is expected to advise the operations crew in the event of an emergency and review plant operating experience during normal circumstances.
The position was mandated by the Nuclear Regulatory Commission following the incident at Three Mile Island.
T..t report expands on a growing body of knowledge regarding the offectiveness of the STA.
The new data presented here come from interviews with plant personnel and utility officials from nine sites.
Researchers from the Pacific Northwest Laboratory (PNL)
I interviewed plant personnel, including the STA and immediate management, the shift supervisor and management, the training department, and ancillary staff, all of whom affect the intended performance of the STA.
The conclusions of the report are that the design of the STA position results in limited contribution during an omargencys more comprehensive ways should be sought to provide the variety and specificity of engineering expertise needed during such times.
NUREG/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983. BELJWAS.T.E.s HORSCHEL.D.S.s JUNO.J.; et al.
Sandia Laboratories.
February 1984.
44pp.
8402280014.
SAND 83-1482.
22429:308.
This report contains a description of work performed in the cocond quarter of FY83 on the Containment Integrity Program.
Plans for future work are presented.
The overall objective of the program is the qualification of methods for reliably predicting the capability of containment structures to function under loadings caused by severs cccidents and extreme environments.
Both analytical and experimental offerts are under way.
The experiments are tests of entire containment for qualifying the analytical methods.
NUREG/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM. Guarterly Progress Report For April-June 1983. ADAMS.R.E.s TOBIAS,M.L.
Oak l
Ridge National Laboratory.
February 1984.
52pp. '8403150219.
l ORNL/TM-8849/V2.
22662:087.
This report summarizes progress for the Aerosol Release and l
Trcnsport' Program sponsored by the Nuclear Regulatory' Commission's Office of-Nuclear Regulatory Research, Division of Accident l
31 1
Evaluation, for April-June, 1983.
Topics discussed includo (1) sovoral cepecitor discharge vaporization experiments in the CRI-III cnd Fuel Aerosol Simulant Test facilities, (2) descriptions of dry atmosphere test 511 and steam atmosphere 505 with iron oxide aerosols in the NSPP facility, (3) technical support work for the aerosol test program at Marviken, Sweden, (4) US-German exchange experiment proposals concerning aerosols containing simulant fission products, (5) a core melt test to observe metal-interaction effects in cladding degradation, (6) progress in construction of a 10 kg core-melt induction furnace, (7) analytical work in support of the FAST /CRI-III oxperiments, (8) aerosol code implementation, (9) NAUA code validation studies, and (10) steam-only experiments in the NSPP.
j NUREG/CR-3427 V03: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983. STAHL,D.s MILLER,N.E.
Battelle Memorial Institute, Columbus Laboratories.
March 1984.
90pp.
8403300294.
22826:203.
Data from the preliminary glass leaching experiments were analyzed, and methods for leachate analysis were developed.
Testing conditions were determined for the leaching pilot experiment, and a flow chart for devitrification calculations was developed.
Methods for evaluating spent fuel and radiation effects were reviewed.
Experiments in the internal corrosion task were essentially completed, and data analysis continues.
External corrosion studies indicated low j
general corrosion rates for the canisters however, some relatively deep pits were found on one specimen in the vapor phase.
Further experiments will be conducted.
Electrochemical studies indicate that steel can passivate and become susceptible to localized corrosion in basaltic groundwater.
Fracture toughness tests of cast and wrought low carbon steels in nitrogen and hydrogen were initiated.
Hydrogen reduced the tearing modulus of the steel.
Hydrogen absorption in cast and wrought steel in basaltic environments is being evaluated.
Results of computer simulations of groundwater radiolysis were compared with results from the general-corrosion correlation.
Gamma onergy deposition was calculated for commercial high-level waste.
Efforts in correlation development focused on pitting corrosion and water chemistry with emphasis on pit-growth kinetics.
A quality j
assurance program audit was initiated.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK.
AT THE ZION NUCLEAR POWER PLANT. BOHN,M.P.s SHIEH,L.C.s WELLS.J,E.:
ot al.
Lawrence Livermore Laboratory.
January ! ?O4.
324pp.
8402210021.
UCRL-53483.
22322:001.
The risk analysis included a detailed seismological evaluation of the reglen around Zion, Illinois which provided the earthquake hazard function and an appropriately randomized. set'of 180 time _ histories.
These time histories were used as input to dynamic structural response calculations for four separate Zion buildings.
Detailed finite olement models of the buildings were_used.
Calculated time histories at piping support points were then used to determine moments throughout critical piping systems.
Twenty-one separate piping systems were analyzed.
Finally, the responses of piping and safety cystem components within the buildings were combined with probabilistic failure-criteria and event tree / fault tree models of the plant safety systems to produce an estimate of the probability of core Eelt and radioactive release due to the occurrence of earthquakes.
The computed median probability of core melt was found to be 3E-5 per year.
The upper (90%) bound on the core melt probability was 32 -
ccaputed to bo 2E-S per y oct, and lowar ( 107. ) bound was computod to bo IE-7 per year.
NOREG/CR-3435: A NEW IMPLICIT NUMERICAL SOLUTION SCHEME IN THE COMMIX-1A COMPUTER PROGRAM. DOMANUS,H.M.; SCHMITT.R.C.s SHA.W.T.s et cl.
Argonne National Laboratory.
January 1984.
52pp.
8402060339.
ANL-83-64.
22107:348.
The report describes, in detail, the new fully-implicit numerical solution procedure implemented in the COMMIX-1A computer code.
This procedure, named SIMPLEST-ANL, is similar to the SIMPLE / SIMPLER procedure developed at Imperial College, London.
SIMPLEST-ANL has been implemented as an additional option to the previously implemented semi-implicit procedure.
The new procedure permits the use of larger time-step sizes without causing any instability in the solution of cystem equations.
It is advantageous specifically for steady-state enolysis of slowly varying long-transient problems.
SIMPLEST-ANL j
requires less computer storage than the SIMPLER procedure with comparable or better computing efficiency.
NOREG/CR-3439 V01: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
SMITH,C.M.
Oak Ridge National Laboratory.
January 1984.
73pp.
8401230039.
ORNL/TM-8862/V1.
21931:322.
1 This report documents the Power Spectral Density Recognition (PSDREC) Continuous On-Line Reactor Surveillance Program.
Volume 1 of this manual is a description of the major concepts and philosophy of the PSDREC surveillance system.
Volume 1 is of interest to readers who desire to understand how'the system operates.
Volume 2 is the oppendices which contain detailed information useful only to a reader involved with the computer implementation of this system.
Volume'1 has been given a general distribution.
Volume 2 is available from the author upon request.
NOREG/CR-3439 V02: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION)i VOLUME 2.
SMITH,C.M.
Oak Ridge National Laboratory.
January 1984.
139pp.
8401230690.
ORNL/TM-0062/V2.
21900:300.
See NUREG/CR-3439,V01 abstract.
NUREQ/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report. DAVIS M.S.
Brookhaven National Laboratory.
January 1984.
124pp.
8402170494.
BNL-NUREG-51699.
22304:202.
This report describes generic and specific aspects of.hard and soft chemical decontaminations and' considers the radiation and thermal l
otebility of the reagents involved.
Disposal options for LWR i
docontamination wastes are reviewed and advantages and disadvantages rolated to the options are discussed.
. Studies indicating the potential impact of these wastes on a shallow land burial ~ ability to rotein radionuclides are summarized.
Processes being considered for the management of spent ion-exchange resins are reviewed.
Problems osoociated with the state-of-the-art of incineration, and chemical digestion.are evaluated.
The solidification and disposal of i
dccontamination wastes are considered with respect to criteria given 33 l
l
in tho Licensing Rule for Land Disposal of Radioactive Waste, 10 CFR 61.
Thoce are ovelunted with respect to possible solidification in cement, bitumen, and plastics.
The various options in mixing i
decontamination wastes with normal LWR resin waste are discussed with respect to their impacts on occupational exposure.
A NUREC/CR-3448: URANIUM HOLDUP MODELING. PICARD.R.R.s MARSHALL,R.S.
Los Alamos Scientific Laboratory.
January 1984.
10pp.
8402170498.
LA-9853-MS.
22320:001.
Statistical modeling of nuclear materials holdup in processing facilities can play an important role in operation, variability of process conditions, quality of measurements, and measurement standards impact the value of model-based estimates.
Recognition of both the i
benefits and the limitations of model-based estimates and the periodic updating of such estimates are essential to maintaining a credible holdup estimation model.
I.
NUREG/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LIME NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report. OPITZ B.E.
DODSON,M.E.; SERNE,R.J.
Battelle Memorial Institute, Pacific Northwest Laboratories.
February 1984.
50pp.
8403070118.
22562:004.
Experiments were conducted to evaluate a two-step neutralization scheme for treatment of acidic uranium tailings solutions.
Tailings solutions from Lucky Mc and Exxon Highland Mills were neutralized with limestone, CACO (3), to an intermediate pH of 4.0 or 5.0, followed by lime, Ca(DH)(2), neutralization pH 7.2.
The combination limestone / lime treatment methods, CACO (3) neutralization of pH 4 followed by neutralization with Ca(DH)(2) to pH 7 resulted in the highest quality effluent solution with respect to EPA's water quality guidelines.
The combination method is the most cost effective treatment procedure tested in our studies.
Experiments to evaluate the optimum solution pH for contaminant removal were performed on tailings solutions utilizing only Ca(OH)(2) as the neutralizing agent.
The data indicates solution neutralization above pH 7.2 does not significantly increase removal of pH dependent contaminants from solution.
Column leaching experiments were performed on the neutralized sludge material (the precipitated material which forms as the acidic tailings solutions are neutralized).
The sludges were contacted with laboratory prepared ground water and several effluent pore volumes were collected.
Effluent solutions were analyred for macro ions, trace matals and radionuclides to evaluate the effectiveness of attenuating contaminants in sludges formed during neutralization.
NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL-INTELLIGENCE _IN PROCESS CONTROL ROOMS. BRAY,M.A.;
l NELSON, W. R. s BLACMMAN,H.S.; et al.. EG&G, Inc.
January 1984.
34pp.
l 8402030099.
EGO-2272.
22090:340.
l An experiment was performed during 1983 that measured performance of nuclear plant operators.with and without a computer-based operator l
aid.
This report discusses the results of that experiment and their implications for design and regulation of advanced computer aids in nuclear control rooms.
The aid tested is called a response tree and is intended to help operators properly. align a piping system despite component or support system failures.
In the experiment, 28 reactor operator _ subjects were required.to align a system to inject coolant 34
cnd stop a tcmporeturo excursion in a simulated roactor.
The oxperiment did not show an improvement in operator performance when
- the response tree aid was used.
More important, the experiment did j
produce several conclusions related to the design and evaluation of computer aids in nuclear control rooms.
NUREG/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF
-BLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
HARRISON,F.L.s LAM,J.R.
Lawrence Livermore Laboratory.
January 1984.
30pp.
8402060333.
UCRL-53487.
22107:317.
We conducted experiments to determine the cuncentrations of copper in effluents and the durations of chronic exposure to sublethal levels of copper that bluegills can tolerate without adverse effects.
I Groups of young bluegills were exposed to water regulated to pH 5.5 that contained either no additional copper or 20, 40, 80 or 160 mg/L 4
additional copper.
In one tank, water was regulated to pH 7 and the j
copper to 80 mg/L.
Liver metalloproteins from the bluegills were separated into a j
low molecular-weight (LMW) protein fraction, which contains
)
notallothioneins (MTs), and into intermediate molecular-weight (IMW) i and high molecular-weight (HMW) fractions, which contain matalloenzymes (MEs), using high performance liquid chromatography.
q Large differences in quantities of copper associated with nota 11oproteins were found.
Copper concentrations in the LMW, IMW, i
i and HMW protein fractions and in the pellet (insoluble fraction) increased with increased exposure concentration and time.
Bluegills i
naintained in 80 mg Cu/L water at pH 5.5 accumulated higher concentrations of copper in the HMW and IMW protein fractions and lower concentrations in the LMW protein fraction and pellet than those naintained in 80 mg Cu/L water at pH 7.
Mortality was dependent on j
exposure concentration and duration and appeared to be related to the onceeding of the MT-detoxification capability.
j 4
NOREG/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIR0f lS. HARRISON,F.L.
Lawrence Livermore Laboratory.
January 1984.
98pp.
8402130117.
UCRL-53488.
22213:198.
The concentrations of copper in the abiotic and biotic 3
compartments of freshwater ecosystems, and the effects on biota of increased amounts of copper in the water and sediments are reviewed.
Data compiled and discussed include the quantities and physicochemical forms of copper in the water column, the concentrations of copper in 4
the bed-load sediments and interstitial waters, and the concentrations of copper in primary producers, annelid worms, molluscs, crustacea, equatic_ insects, minor invertebrates, and fishes.
In addition, the l
ecute and sublethal effects of copper on the same groups of biota are presented, as well as data on copper concentration factors.
This information can be used to:
(1) determine for different types of ocosystems the ranges of copper concentrations that occur in nature, (2) identify ecosystems that are or may be impacted by copper released from industrial and urban sources, and (3) assess the effects on biota l
of the use of copper alloys in nuclear power station cooling systems.
i
, NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL l
PIPE WELDS. HEBBLE, T. L. s CANONICO.D.A.: EDMONDS.D.P.s et al.
Oak Ridge National Laboratory. -January 1984.
16pp.
8402010115.
DRNL-6024.
22058:007.
i An American Society of Mechanical Engineers task group on' I
35
Otcinloos stool weld materials was organized to determine the need for ferrite measurements of production welds required by the U.S.
Nuclear.
Regulatory Commission Regulatory Guide 1.31 (Rev.
1).
The task group studied paired ferrite measurements C i. e., calculated and measured j
ferrite numbers (FNs) for the material qualifications versu" measured i
ferrite numbers for corresponding production welds (PWs)].
Our purpose was to compare delta-ferrite content as measured in the filler i
metal weld. qualification pad with_that in the resultant PW.
Welds made predominantly by three common processes (submerged arc. shielded i
metal arc, and gas tungsten arc) were included in the study.
Weld I
metals investigated i*ecluded types 308, 308L, 316, and 316L stainless steel.
An initial evaluation of the paired ferrite measurements was made by the task group, and specific conclusions and recommendations l
were made.
We describe the analysis of the data and the conclusions drawn.
The data base consisted of a heterogeneous collection of 1449 l
paired ferrite measurements for several forms and combinations of types 304 and 316 stainless steel pipe qualification pad and j
production welds.
Qualification pad values ranged from 5 to 15 FN, 1
and corresponding values for the PWs ranged from 2.3 to 17.5 FN.
Only l
two PW ferrite numbers were less than 3.
For qualification weld j
ferrite numbers less than 14, the median PW ferrite number was in reasonable agreement.
However, the results show a wide seatter.
As a result of this analysis and the task group evaluation, we i
concluded that the requirements of Regulatory Guide 1.31 on the measurement of ferrite in PWs are not necessary and that a ferrite
}
number of 5 in the qualification welds will, in most cases, result.in l
PW ferrite contents greater than 3 FN.
f i
NOREQ/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERIA. WOO,H.H.
Lawrence Livermore Laboratory.
January 1984.
44pp.
8402210019.
UCRL-53490.
22323:115.
This report presents the results of studies on the current j
regulatory position on postulated pipe rupture location criteria and recommends future licensing regulations.
The report contains five parts.
The first part highlights the current regulatory positions on criteria for postulated pipe rupture locations.
The second part reviews data on nuclear piping failures related to the failure locations in the piping systems.
The third i
part presents a probabilistic assessment of three nuclear piping lines under fatigue loadings.
The fourth part recommends modifying the 1
criteria and scopes future work, the fifth part, Appendix A, provides
{
the validation results for the stress corrosion cracking model.
The failure case chosen for comparison with the. analytical result is a recirculation line safe-end cracking incident in a boiling water reactor.
NOREG/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL. MCARTHUR.D.A.;
MAST,P.M.
Sandia Laboratories.
January 1984.
32pp.
8402210024.
SAND 83-1916.
22343:281.
The TRAN B-Series experiments are being conducted at Sandia National Laboratories to investigate the characteristics of fuel removal / freezing through the upper axial blankets of a liquid-metal fast-breeder reactor during the transition phase of a hypothetical _
core-disruptive accident.
The first experiment in this s er i e s,'
TRAN 3-1, was performed in February 1983 and the.results are reported.
herein.
This experiment involved the injection of molten UO(2) into l
l 36 L
~. -. - -
i I
I en annular flow chennel.
Previous experiments had shown crusts to be stable on the inside of a cylindrical flow channel.
This experiment man intended to investigate whether the conclusion of crust stability could be extended to freezing on the outside of cylindrical rods (the more prototypic geometry of the upper axial blankets).
The results of the TRAN B-1 experiment, consisting of data from enline instrumentation and postirradiaton examination, indicate that the crusts on both inner and outer surfaces of the annular channel wore stable during the duration of the fuel flow.
Thus, a conduction-limiting model could be used to describe the fuol-flow / freezing process.
However, the experiment data also indicated that the crusts were less stable on the outside of a rod then on the inside of a cylinder late in time.
NUREQ/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF GEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
O 'KELLEY,0. D. s MEYER, R. E.
Oak Ridge. National Laboratory.
March 1984.
38pp.
8404100524.
ORNL-5988.
22981:001.
Analyses of the performance of a high-level nuclear waste ropository will require a detailed study of the chemical factors involved in the interaction of water-mobilized nuclides with the geologic formations of the host repository, including sorption phenomena, redox processes, hydrolysis, complexation, solubility, and formation of polymeric and colloidal forms of the nuclides.
A discussion and review of these factors is given along with their pertinence to the migration of the nuclides and the development of j
ccmputer codes for the prediction of this migration.
Much of the chcmistry of the nuclides of interest is very sensitive to pH and redox conditions and, in general, increase of acidity and oxidizing pcNet of the groundwater could have serious consequences, additional i
concerns are the formation of negatively charged species, which tend to exhibit very low adsorption, and the formation of insoluble products through redox processes.
Because of the great complexity of the chemistry involved, it will probably be necessary to develop techniques of prediction which do not take into account all reactions but only those which are thought to limit system performance.
l NUREG/CR-3491: OCA-II,A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPERATURE AND PRESSURE TRANSIENTS. BALL. D. G. s CHEVERTON, R D. s DRAKE J.B.s et al.
l Onk Ridge National Laboratory.
February 1984.
110pp.
8402210073.
ORNL-5934.
22323:189.
The OCA-II computer code, like its' predecessor OCA-I, performs tho thermal, stress, and linear elastic fracture-mechanics analysis for long flaws on the surface of a cylinder that is subjected to thormal and pressure transients.
OCA-I. represents a revised and onpanded version of OCA-I and includes as new features'(1) cladding as a discrete region, (2) a finite-element subroutine for calculating the stresses, and (3) the ability to calculate stress intensity factors-for certain three-dimensional flaws,.for two-dimensional' circumferential flaws on the inner surface, and for both axial and circumferential flaws on the outer surface.
OCA-I considered.only.
inner-surface flaws.
An option is included in OCA-II that permits a coorch for critical values of fluence or nil-ductility reference-to:perature corresponding to a specified failure criterion.
These and other features of OCA-II are described in the report, which also includes user instructions for the code.
l 37 l
l-
I NUREQ/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION QUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983. BALL,S.J.s CLEVELAND,J.C.; HARRINGTON,R.M.s et l
41.
Oak Ridge National Laboratory.
January 1984.
13pp.
8402060457.
22115:008.
Work on postulated severe accident sequence code development and application continued both for the Fort St. Vrain and 2240-MW(t) lead plant designs.
Initial experiments on high-temperature gas-cooled reactor (HTGR) fission product release and transport were run in an existing high-temperature (>2000 degree C) graphite-resistance furnace.
Initial work was done on a cooperative study of HTGR safety i
research needs.
NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, JULY - SEPTEMBER 1983. BALL,S.J.s CLEVELAND,J.C.s HARRINGTON,R.M.s et al.
Oak Ridge National Laboratory.
March 1984.
26pp.
8404100531.
ORNL/TM-8921/V3.
22979:315.
Work continued on code development aimed at establishing capabilities for licensing and source-term calculations for design.
Refinements were made in liner cooling system (LCS) models.
Three runs were completed in the fission product release and transport studies, indicating rapid diffusion of rare earths through graphite at high temperatures (2700 K).
Benchmarking work continued for the BLAST steam generator code.
Initial plans were developed for large-scale i
thermal-hydraulic tests for verifying LCS and core bypass flow models.
NUREG/CR-3496: REVIEW OF A TEST PROGRAM FOR QUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT. BARLETTA.R.E.s j
DAVIS,R.E.
Brookhaven National Laboratory.
January 1904.
32pp.
8402210026.
BNL-NUREG-51712.
E7323: 001.
The results and recommendations of the resin solidification test program conducted by Metropolitan Edison Company are reviewed.
The 1
l original purpose of this program was to recommend a formulation or i
range of formulations suitable for the cement solidification of first-stage Epicor-II liners generated during cleanup activities at t
Three Mile Island.
This was to be accomplished through a systemmatic-laboratory and full-scale testing program using ionexchange materials supplied by Epicor, Incorporated.
Events, however, caused the truncation of the full-scale testing.
Hence, a formulation was recommended based upon the results of laboratory scale testing.
l Failure to achieve satisfactory solidification in a single full-scale test using this formulation was observed.
The unqualified conclusion that these tests demonstrate that the Epicor-II spent ion exchange media can be successfully solidified in cement appears to be unwarranted.
Through a full-scale testing program, some of the deficiencies of the full-scale waste form may be resolved by simple technical modification or implementation of a process control program Met-Ed/GPU had recognized the need for additional full-scale. testing.
Further, conflicting results of the screening and primary phases of the Met-Ed/GPU test program and the general conclusion af the Met-Ed/GPU study are noted in this report.
NOREG/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT. HILL,L.J.s RAINEY,J.A.s TEPEL.R.C.s et al.
Oak Ridge National Laboratory.
January 1984.
47pp.
8403200358.
ORNL/TM-8684.
22709:010.
l
,38
i l
.The popor presents an analysis of en actual 24-month nuclear power plant licensing delay under alternate assumptions about regulatory practice sources of replacement power, and the cost of the plant.
The analysis focuses on both the delay period and periods subsequent to the delay.
The methodology utilized to simulate the impacts involved the recursive interaction of a generation costing program to estimate fuel replacement costs and a financial regulatory i
model to concomitantly determine the impact on the utility, its I
retepayers, and security issues.
The resulte indicate that a licensing delay has an adverse impact on the utility 's internal generation of funds and financial indicators used to evaluate financial soundness.
The direction of impact on electricity rates is contingent on the source of fuel used for replacement power.
NUREG/CR-3502: HIGH DRYOUT QUALITY FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD BUNDLE. YODER,G.L.; ANKLAN, T. M. ;
l MORRIS, D. C. s et al.
Oak Ridge National Laboratory.
January 1984.
i 84pp.
8401300018.
ORNL/TM-8794.
22027:334.
i A series of eight steady-state rod bundle tests has been performed at the Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility to gather data in both the low flow film
~
i boiling region and high flow steam cooling region.
This test series 4
includes experiments both with and without liquid entrainment above the dryout point.
I Bundle fluid conditions were calculated using steady-state energy and mass conservation equations.
The experimental heat transfer data j
have been compared to several film boiling heat transfer correlations and one vapor correlation.
Results of these comparisons support the conclusions reached in the analysis of prior ORNL transient and steady state tests (3.03.6AR, 3.06.68, 3.08.6C, series 3.07.9.
series l
3.02.10, and series 3.09.10).
Results indicate that the Dougall-Rohsenow correlation often overpredicts the heat transfer i
coefficient, while the Groeneveld 5.7 and Condie-Bengston IV correlations tend to underpredict, however they are in better egreement with the data.
The Groeneveld-Delorme correlation underpredicts heat fluxes.
The Dittus-Boelter correlation was a
j ovaluated only when equilibrium qualities were greater than one, and 1
j tends to overprodict the heat transfer coefficient.
NOREG/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO -
MANAGING PUBLIC HEALTH AND SAFETY RISKS. FISHCHOFF.B.
Decision Rosearch,Inc.
Oak Ridge National Laboratory.
February 1984.
l 66pp.
8403190444. -ORNL/SUB-7576/3.
22681:004.
Standards are an effective means of managing hazardous technologies.
This guide presents a general framework for the design dovelopment and implementation of safety standards.
Particular otrategies along with inherent strengths and. weaknesses are described.
NUREG/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION DF RADIOIODINE j
FROM MILK. SOLBRIO,R.M.; HUCHTON,R.L.; MOTES,B.G.
Exxon Nuclear Co.',
Inc. (subs. of Exxon Corp.).
February 1984.
24pp. =8402280010.
ENICD-1137, 22429:280.
The development and testing of a practical field method for the collection of radiciodine from milk is reported.
The technique is simple, rapid and relatively inexpensive to perform and yields 1a good
.icdine collection efficiency.
The-batch method involves adding a j
-250-m1 volume of Dower 1-x8 anion-exchange resin-to 3.5 liters of
-39
i oilk, mixing at a rate of 30 rotations per minute for threw minutes, separating the resin and milk by pouring the mixture through a wire-screened canister,-and rinsing the resin with 2OO-m1 of distilled water.
Advantages of the procedure include: minimal equipment and personnel trainings an inexpensive industrial grade resins a total of ten minutes to completts and an adaptability of the wire-screened canister to different geometries for direct counting.
Additionally, the total collection efficiency of 81 + or - 6% is relatively l
independent of temperature, iodide concentration, mixing rate and mixing time.
NUREG/CR-3522 VO1: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF l
SPECIAL NUCLEAR MATERIALS, VOL 1: U Oxide Plus Graphite Powder.
SPRINKLE. J. K. s LIKES,R.N.4 PARKER.J.L.s et al.
Los Alamos Scientific Laboratory.
January 1984.
41pp.
8402010368.
LA-9910-MS VO1.
l 22061:001.
This manual describes the fabrication of reference materials for use in gamma-ray-based nondestructive assay of low-densit, uranium-bearing samples.
The sample containers are 2 liter bottles.
The reference materials consist of small amotsnts of UO(2) spread l
throughout a graphite matrix.
The (235)U content ranges from 0 to 100 g.
The manual also describes the far-field procedure used uith low-resolution detectors.
i NUREG/CR-3522 VO2: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF 4
SPECIAL NUCLEAR MATERIAL. Volume 2: Th in Metal Foils Of Highly Enriched l
Uranium. SPRINKLE,J.K.s LIKES,R.N.s SMITH,H.A.
Los Alamos Scientific Laboratory.
January 1984.
15pp.
8402010313.
LA-9910-MS VO2.
22046:210.
This manual describes the fabrication of reference materials for i
in gamma-ray-based nondestructive assay of small high-density use uranium samples.
The sample containers are small Petri dishes.
Tha reference materials consist of thin circular discs of highly enriched i
uranium metal foil.
The 235U content ranges from O.2 to 10 g.
The i
manual also describes the assay procedure used with low-resolution detectors.
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTIAL NUCLEAR POWER PLANT MALFUNCTIONS.
SELBY,D.L.s HENSLEY,W.T.
Oak Ridge National Laboratory.
February 1984.
121pp.
8403300306.
ORNL/TM-8950.
22842:190.
I The research summarized in this report was conducted as part of a program entitled " Nuclear Power Plant Entry Level Gualification and Training."
A process is developed to assist in the selection of plant j
malfunctions which should be specifically addressed'as part of the j
training program, and further guidance is given for determining which of those malfunctions should be included in simulator training.
Consequences (C), difficulty (D), and frequency (F) rating forms are developed to determine the relative importance for training of any system malfunction.
Plant malfunctions were' categorized for 46 plant systems.
Thirteen of these malfunction categories were then used to demonstrate the C-D-F rating forms.
NOREG/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING-FOR BWR. APPLICATIONS. PADOWSKI,M.Z.s TALEVARKHAN, R. s ' LAHEY, R. T.
Oak Ridge National Laboratory.
January 1984.
75pp.
8401260101.
40
ORNL/SUB/81-908.
21971:005.
This report summarizes the results of developmental work at l
Ronsselaer Polytechnic Institute (RPI) of methods of core modeling for l
use in the analyses of the progression of accidents that involve core l
dcmage in BWRs.
Accomplishments include the development of an cnalytical model for channel box and control rod heatup, oxidation, l
i and melting, and a mechanistic core-wide meltdown and relocation model.
These are provided in the form of a FORTRAN subroutine denoted MELRPI that can be exercised with an existing version of the MARCH code.
The modeling concept and the modular structure employed.in MELRPI have been designed so that new models subsequently developed for specific phenomena can be rapidly incorporated when they become i
evailable.
NUREG/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK j
BROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS. CHUANG,T.Y.
LU,S.C.; BENDA,B.J.a et al.
Lawrence Livermore Laboratory.
March 1984.
72pp.
8404120384.
UCRL-53491.
24035:062.
The Technical Committee on Piping Systems of the Pressure Vessel Rosearch Committee has proposed two modifications that affect seismic analysis of piping systems to regulatory guides.
One modification would change damping values for piping systems specified in Regulatory Guide 1.122.
In this study we quantified the reduction in piping responses of three piping systems in the Zion nuclear power plant resulting from these two modifications, separately and in combination.
We concluded that:
The proposed damping values reduce piping response substantia 11gi and the proposed alternative to peak broadening reduces piping response only marginally.
We calculate the seismic response of the three piping systems by two methods:
Response spectrum analysis and multi-support time history analysis.
We used the proposed modifications in the response spectrum analysis.
The results of the response spectrum analysis were calibrated against those of time history analysis.
We found that conservatism remains under the proposed modifications.
One of the three piping systems was used to show the potential benefit of the proposed modifications.
We found that both snubbers cnd 7 of the 10 horizontal restraints could be removed without causing strssses in the piping system to exceed code allowables.
Hence, the potential benefit of the proposals is very promising.
NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
YOUNGBLOOD.R.W.s PAPAZOGLOU,I.A.
Brookhaven National Laboratory.
3 l
. February 1984.
102pp.
8403230133.
BNL-NUREG-51721.
22739:130.
The purposes of - this report are: (1) to review the Emergency Foedwater System Upgrade Reliability Analysis for the Arkansas-Nuclear One Nuclear Generating Station Unit No.
1, and (2) to estimate the l
probability that the Emergency.Feedwater System will not perform its j
pission for each of three different initiators: (1) loss of main feedwater with offsite power available. (2) loss of offsite power, (3) loss of all 4160 VAC power.
The scope, methodology, and failure data cre prescribed by.NUREG-0611, Appendix III.
t NUREG/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO. 1 AUXILIARY FEEDWATER CYSTEM RELIABILITY ANALYSIS. YOUNGBLOOD R.W.s PAPAZOGLOU,I.A.
Brookhaven National Laboratory.
February 1984.
17pp.
8402170430.
41
l BNL-NUREG-51722.
22318:319.
The pursose of this report'is to review the "Davi's-Besse Unit No.
1 Auxiliary Feedwater System Reliability Analysis Final Report," and l
to provide an independent estimate of the Auxiliary Feedwater System l
Reliability.
This report presents estimates of the probability that the Auxiliary Feedwater' System will not' perform its mission for each of three different initiators: (1) loss of main feedwater with offsite power available, (2) loss of offsite power, (3) loss of all 4160 VAC power.
The scope, methodology, and failure data are prescribed by NUREG-0611, Appendix III.
+
NUREG/CR-3531: REVIEW OF SEABROOK UNITS 1 AND 2 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS. FRESCO,A.; YOUNGBLOOD,R.W.s PAPAZOGLOU,I.A.
Brookhaven National Laboratory.
February 1984.
i 194pp.
8402170503.
BNL-NUREG-51723.
22304:320.
This report presents the results of a review of the Emergency Feedwater' System Reliability Analysis for Seabrook Nuclear Station Units 1 and 2.
The ob Jective of this report is to estimate the probability that the Emergency Feedwater System will fail to perform its mission for each of three different initiators: (1) loss of main feedwater with offsite power available, (2) loss of offsite power, (3) loss of all AC power except vital instrumentation and control 125 VDC/120 VAC power.
The scope, methodology, and failure data are prescribed by-NUREG-0611, Appendix III.
The results are compared with l
those obtained in NUREG-0611 for other Westinghouse plants.
i NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONDENERGETIC ELECTRON IRRADIATIONS. BUCKALEW,W.H.; WYANT,F.J.s LOCKWOOD,G.J.
Sandia Laboratories. -January 1984.
60pp.
8401130105.
SAND 83-2098.
j 21821:040.
The papers published in this report were presented at the i
Eleventh Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, October 24-28, 1983.
The papers describe the results and program plans in nurlear reactor safety research conducted in this country and abroad.
l International participation in the exchange of nuclear safety research information is consistently encouraged by the Nuclear Regulatory Commission and was exemplified at this meeting by the relatively large number of papers (23) given by representatives of seven different European countries, Japan and Taiwan.
i NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983. MAXFIELD, B. W. s WOO,H.H.
Lawrence Livermore Laboratory.
January 1984.
19pp.
8402060452.
UCRL-53492.
22107:167.
On January 11, 1983, a United Airlines ~DC-8F cargo aircraft crashed shortly after. takeoff from Detroit Metro Airport.
A lower rear cargo pit had a type A package containing 10,000 Americium-241 (241(Am) solid-form sources, each of 1.5-microcurie (mci) strength, used in smoke detectors.
Although burned and somewhat. battered, the 1 gal metal can holding all these sources was recovered completely intact with no release of radioactive material to the environment or loss of any sources.
This report describes Lawrence Livermore National Laboratory 's attemp t to reconstruct, as closely as practical.
l the mechanical and thermal environments experienced-by this can during l
cnd immediately after the accident.
Mechanical loading of the metal 42
~
con in shipping cotton was simuleted by impacts from a 16-lb pondulum mass falling through vertical displacements to demolish internal' plastic jars and to produce major deformation of the metal can.
The thermal environment was best reproduced by the simple burning of the outer shipping carton.
l NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report September 1983. MURPHY,0.A.
CASADA,M.L.
HOY,H.C.
Oak Ridge National Laboratory.
January 1984.
44pp.
8402060478.
ORNL/NSIC-216.
22110:230.
The results of a study utilizing the Oak Ridge National Laboratory (ORNL) Nuclear Operations Analysis Center (NOAC) computer files of operating experience reports Clicensee event reports (LERs),
obnormal occurrences, etc.3 are summarized.
In this study, specific 1
time-related degradation mechanisms are identified as possible causes of a reportable occurrence.
Data collected on domestic commercial nuclear power plants covering 1969 to 1982 yielded over 5000 events attributable to age-related failures.
Of these events, 2795 were attributable to instrument drift, which are addressed separately in the report.
The remaining events (3098) were reviewed, and data were collected for each event, identifying the specific system, component, and subparts the information included age-related failure mechanism, severity of failure, and method of detection of the failure.
About two-thirds of the failures were judged to be degraded, with one-third listed as catastrophic failures.
No events were found to be incipient failures because an LER is prepared only on degraded or catastrophic failure conditions that place plant operation outside the Technical i
Specifications.
The study found that information desired for ovaluation of aging effects (equipment, age, service life, and onvironment) was seldom available from LERs.
This reflects the' intent of the LER system as a regulatory instrument, rather than an ongineering data collection system.
The study is a part of the overall Nuclear Regulatory Commission research on nuclear power plant i
aging effects.
J h
NUREG/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEQUENCE ANALYSIS.
STACK,D.W.
Sandia Laboratories.
January 1984.
165pp.
8404020272.
SANDB3-2238.
22875:109.
This manual describes the use of the Set Equation Transformation System (SETS) to perform the accident sequence analysis portion of a probabilistic risk assessment (PRA) for a nuclear power plant.
Other tasks in a PRA provide the input to the accident sequence analysis task.
The SETS computer program-is used to process these inputs to identify the dominant failure modes and to compute an approximate
)
frequency of occurrence for an accident sequence.
The use of SETS for i
cach step in an accident sequence analysis is described and an example SETS user program is provided for each step.
NUREG/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERIA.
DOUGAN J.R.
Oak Ridge National Laboratory.
March 1984.
56pp.
.C403300318.
- DRNL/TM-8909.:
22B26: 3C3.
Revision of Appendix J, to reflect technological advances and testing experience, has-been under consideration for years and has culminated in the issuance of a draft version of a proposed revision to Appendix J.
To assist in the revision process, a review of 49 Type A test reports and 46 Type B and C test reports was accomplished.
Exemption requests found in 25 reports and 100. License Event Reports 43
.v
.-e
+ - - - -
w
,e r
+
w
1 i
uoro cico reviewad.
Two major findings of the dato analysis were that Type A test duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are practical and that almost all Type A test failures and delays were caused by excessive r
leakage through Type B and C tested components.
Excessive valve leakage represented 38% of the LERs and highlighted the need for improved maintenance, repair and testing of these components.
Excessive airlock leakage was generally the result of worn, damaged, misaligned, or dirty door seals.
The proposed revision to Appendix J
{
appears to be very responsive to the results of test experience and technological changes.
The introduction of a regulatory guide provides a vehicle for the NRC to specify any exceptions to the relevant industry standards and to resolve areas of conflict.
NUREG/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONINO PROJECTS.
Annual Summary Report - Fiscal Year 1983. MILLER,R.L.s BAUMANN B.L.
United Nuclear Corp.
January 1984.
173pp.
8402170304.
22304:029.
This document summarizes work performed during the 1983 fiscal year for the Nuclear Regulatory Commission 's Evaluation of Nuclear Facility Decommissioning Projects program.
This report describes actual work performed during the reporting period and work planned for the future.
Included as an appendix to this report is a draft of the Decommissioning Code Table / Indexes for BWR, PWR, Research and Test Reactors included in this study.
Other appendices list current data from the TMI-2 recovery efforts and Shippingport Atomic Power Station decommissioning.
NUREC/CR-3553: AN EFFICIENT SIMULATION APPROACH FOR EVALUATING THE 1
POTENTIAL EFFECTS OF NUCLEAR POWER PLANT SHUTDOWNS ON ELECTRICAL CENERATING SYSTEMS. VANKUIKEN,J.C.
Argonne National Laboratory.
{
January 1984.
37pp.
8402010274.
ANL/EES-TM-233.
22049:061.
Production-cost and reliability studies of electrical utility
{
systems have, in the past, been hindered by high computational costs l
and long lead times for preparing case studies.
Computational costs have been especially high for simulating large systems or lona periods j
and for conducting comprehensive sensitivity analyses.
This report describes modeling developments that help. alleviate previous constraints.
A new simulation approach preserves an acceptable level l
of accuracy and detail from previous production-cost and reliability nethods and, at the same time, significantly reduces the computational requirements.
An automated data assembly package facilitates the collection and preparation of simulation inputs used to characterize utility systems.
Several case studies are investigated to test and demonstrate the new procedures for reactor shutdown evaluations.
NUREG/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982. ROBERTSON D.E.;
TOSTE,A.P.; ABEL,K.H.s et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
82pp.
8402210013.
PNL-4773.
22323:031.
Research has continued at a low-level waste disposal facility to characterize the physiochemical species of radionuclides migrating in groundwater.
This facility consists of an unlined basin and connecting trench which receives effluent water containing low levels-of a wide variety of fission and activation products and trace amounts i
of_ transuranic radionuclides.
The effluent water percolates.through the soil and a small fraction of it emerges at seepage springs located some 260 meters from the trench.
The disposal basin and trench are very efficient in retaining most of the radionuclides, but trace 44 mv+' ' '
m-~
w
---a
cmounts of a number of radionuclides existing in mobile chemical forms l
migrate.in the groundwater from the trench to the springs.
This facility provides the opportunity for characterizing the rates and nachanisms of radionuclide migration.in groundwaters,- identifying roterdation processes, and validating geochemical models.
NUREG/CR-3556; NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS. BLACKMAN,H.S.s GERTMAN,D.I.s GILMORE W.E.s et al.
EG&G, Inc.
January 1984.
36pp.
8401130092.
EGG-2284.
21820:289.
The United States Nuclear Regulatory Commission (USNRC) is cponsoring an ongoing research program to develop methods of assessing various types of computer generated displays currently being i
implemented in nuclear power plant control rooms.
The purpose of this report is to prasent a noninteractive simulation technique for the ovaluation of computer generated displays.
Four safety parameter display formats were evaluated in two separate experiments.
Three formats were evaluated in Experiment I (STAR, BAR, METER).
Two formats were evaluated in Experiment II (BAR, P-T map).
All formats contained top-level safety parameters minimally necessary for the safe operation of a pressurized water reactor at the Loss-of-Fluid Test (LOFT) reactor.
Subjects for the experiments were current or former l-operators at the Loss-of-Fluid Test (LOFT) reactor.
The results of this experiment have indicated that the noninteractive technique can l
be used to evaluate the detection and recognition of transients in safety parameter display evaluation.
In addition, the data suggest that, given a reliable set of parameters and good human engineering, that graphical format of the display has negligible impact of l
performance.
The implications of these results are discussed in terms i
of future work and display design.
]
i NUREG/CR-3560: EVALUATION METHODS FOR THE CONSEGUENCES OF BELOW WATER 1
TABLE MINE DISPOSAL OF URANIUM MILL TAILINGS. MCKEON T.J.s NELSON,R.W.
Battelle Memorial Institute, Pacific Northwest 4
Laboratories.
January 1984.
90pp.
8403230173.
PNL-4904.
22742:217.
l A method has been developed at the Pacific Northwest Laboratory I
to ovaluate the environment consequences of below water table disposal of uranium mill tailings in mine stopes.
The method described uses cnolytical expressions for the velocity potentia 1'and examines the j
convection transport of tailings liquor and leachate through the equifer and into a water supply well located down gradient from the mine stope.
The arrival distribution of contaminant (mass flux versus tims) and the concentration pumped from the well-as a function of time cro the final results of the analysis.
i l
' NOREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENERATOR TUBES.
i BICKFORD, R. L. ; CLARK R.A.;
DOCTOR,P.G.s et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
130pp.
C402270213.
PNL-4695.
22395:263.
This report provides the results of an eddy current round robin tont conducted on Inconel 600 steam generator tubing specimens with l
l icberatory induced IGSCC.
This test was an attempt to establish the boot available. nondestructive testing method for characterizing IGSCC in Inconel steam generator tubing.
The participanks were permitted to
.use any available eddy current method and were not limitedito probes I
er cethods that are or could be used in commercial primary side 45
in-sorvico inspection.
Areas covered in this report include production of the specimens, defect characterizations by the participating teams, data from the subsequent destructive metallographic analysis of the specimens and a statistical evaluation of the results per team and between teams.
I NUREG/CR-3562: STEAM GENERATOR TUBE INTEGRITV PROGRAM LEAK RATE TESTS-PROGRESS REPORT. CLARK,R.A.s BICKFORD,R.L.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
69pp.
0402010373.
PNL-4629.
22061:090.
This interim report presents preliminary results on leak rate tests performed on through-wall defected Inconel 600 steam generator tubing.
Tube defects included an EDM (electro-discharge machine) notch and IGSCC (intergranular stress corrosion cracks) of various f
lengths.
Tests were conducted at PWR operating temperatures with leakage of hot water / steam into air.
A number of IGSCC cracks were unstable under the experiment conditions of these initial tests, continuing to grow until system capacity limitations resulted in decreased pressure differential.
However, initial testing also pointed to a need for reconfiguration of the test apparatus to sustain increased flow and, more importantly, alter the mode of control.
The initial test configuration is based on flow control, with pressure differential across the specimen an independent variable.
This often results in pressure increases too rapid to establish the initiation of crack instability.
A reconfigured system based on pressure control with flow as an independent parameter is being recommended for future tests.
NUREG/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
DIAN,S.H.; THURGOOD, M. J. ; KELLY,J.M.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
63pp.
8402060343.
PNL-4908, 22107:202.
The computer code COBRA / TRAC was used to simulate a Small-Break Loss-of-Coolant Accident (SBLOCA) test performed at the Semiscale MOD-2A Test Facility operated by the Idaho National Engineering Laboratory.
The results of the simulation were compared with the results of the actual test.
The comparison showed that the COBRA / TRAC calculation gave a reasonable match with the measured data and that I
the code has the capability to model the loop components in an integrated coolant system for a pressurized water reactor-(PWR).
l NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL' SOURCES (PERCS). The Theory,The Code And Examples. REECE,W.D.s HADLEY, R. T. s HARDTY,R.s et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
173pp.
8403190449.
PNL-4923.
22680:170.
A new interactive point kernel shielding code for gamma rays named PERCS (Personnel Exposure From Right Cylindrical Surfaces) is presented with theory, a listing and examples.-
PERCS calculates doses from more complicated geometries faster than other known shit 1 ding l
codes.
The code is graphics-oriented, interactive, menu-driven and easy to use.
PERCS is especially suited for calculation of dose l
arising from activated corrosion products plated on primary piping in commercial power plants.
46
- NUREG/CR-3577
- THE MEASUREMENT OF COUNTERCURRENT PHASE SEPARATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION, BUKHARI,M.;
l LAHEY, R. T.
Rensselaer Polytechnic Institute, Troy, NY.
January l
1984.
220pp.
8401250134.
21949:028.
The degree of phase separation that' occurs in the core of a proosurized water reactor (PWR) during various postulated acc,idents is en important consideration for studying the course of events during ouch accidents.
The dependence of countercurrent phase separation and distribution phenomena on flow quality, mass flux and system geometry uno studied experimentally in a two-dimentional (2-D) test section.
A two-phase (air / water) mixture flowed upwards and single-phase water flowod downward along one side of the test section.
This countercurrent flow configuration was intended to simulate the so-called " chimney effect" in the diabatic JAERI 2-D experiments in Jcpan.
A large air / water loop was used with a3' x 3' x
- 0. 5 " (91.44 cm x 1.27 cm) test section to study phace separation and distribution offects.
A traversing single beam gamma-densitometer cas used to m3asure the chordal average void fractions at several elevations along the test section.
Cross-plots between various low conditions and goomstries were made.
An error analysis giving the total error in the void fraction measurements was also performed.
High speed photographs were also made of the flow structure, to provide information on flow regimes.
The photographic records and the void fraction and hydraulic inflow / outflow data are presented in a form suitable for the assessment of advanced generation computer codes (eg: TRAC).
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-H2cIth Physics. REECE,W.D.s HOENES,0.R.s PARKHURST,M.A.; et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
33pp.
8401260105.
PNL-4711.
21969:288.
The gamma radiation fields in and around the retired Surry steam generator were measured extensively with thermoluminescent dosiodters (TLD's) and other standard radiation instruments.
The techniques of naesurement and the results are described for locations outside the.
i shell, inside the channel head, and inside the secondary. side of the steem generator.
The gamma fields ranged from more than 10 R/hr in the middle of the tube bundle on the secondary side to less than 5 nR/hr at the bottom of the outside cf the shell below the channel hood.
Co-60 was the only detected pamma amitter.
The results of the nocturements were used in an analytical model which predicted the Co-60 inventory to be between 70 and 87 curies.
! NUREG/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis. DOCTOR,P.G.s BUCHANAN,J.A.s MCINTYRE,J.M.s et al.
Battelle Memorial Institute, Pacific Northwest
,d u j Lsboratories.
January 1984.
38pp.
8402170311.
PNL-3955.
l 22318:181.
A major task of the Steam Generator Group Prcject (SGGP) is to x
ostchlish the reliability of the eddy current inservice inspectionz of PWR cteam generator tubing, by comparing the eddy current data to the cetuc1 physical condition of the tubes via destructive. analyses.
This report describes the plans for the-computer systems needed to acquire, otoro and analyze the diverse data to be collected during.the projoct.
The real-time acquisition of the baseline eddy current inopoction data will be handled using a specially designed data ccquisition computer system based on a Digital Equipment Corporation 47
4 (DEC) PDP-11/44.
The data will be crchived in digital form for une after the project is completed.
Data base management and statistical analyses will be done on a DEC VAX-11/780.
Color graphics will be heavily used to summarize the data and the results of the analyses.
The report describes the data that will be taken during the project and the statistical methods that will be used to analyze the data NUREG/CR-35BO: STEAM CENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982. CLARK,R.A.J LEWIS,M.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
34pp.
8402170300.
PNL-4692.
22318:223.
The Steam Oroup Project (SGGP) is an NRC program joined by additional sponsors.
The SGGP utilizes a steam generator removed from service at a nuclear plant as a vehicle for research on a variety of safety and reliability issues.
This report is a semi-annual summary of progress of the program.
Information is presented on positioning the generator into the Steam Generator Examination Facility, and examination of the secondary side to confirm pretransport generator condition.
The report then presents radiological field mapping results and personnel exposure monitoring data.
Radiation field reduction achieved in channel head decontamination efforts is reported.
The results of a profilometry examination to determine the extent of denting are summarized.
Plans for unplugging of selective explosively plugged tubes are discussed.
NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
CLARK R.A.4 LEWIS,M.; MJSCARA,J.
Battelle Memorial Institute, Pacific Northwest Laboratories.
February 1984.
Ip.
8404200016.
PNL-4693.
The Steam Generator Group Project (SGGP) is an NRC program Joined by additional sponsors.
The SGGP utilizes a steam generator removed from service at a nuclear plant as a vehicle for research on a variety of safety and reliability issues.
This report is an annual summary of progress of the program for 1982.
Information is presented on the i
Steam Generator Examination Facility (SGEF), especially designed and J
constructed for this research.
Loading of the generator into the SGEF is then discussed.
The report then presents radiological field mapping results and personnel exposure monitoring.
This is followed-l by information on field reduction achieved by channel head j
decontaminations.
The report then presents results of a secondary side examination through shell penetrations placed prior to transport, l
confirming no change in generator condition due to transport.
i Decontamination of the channel head is discussed followed by plans for eddy current testing and removal of tube plugs placed during service.
Results of a preliminary profilometry examination are then provided.
NUREG/CR-3504: COMMONLY USED NUCLEAR MATERIAL MEASUREMENTS AND THEIR SOURCES OF ERROR. ROBERTS. F. P. s BROUNS, R. J. s BYERS,K.R.s et al.
Battelle Memorial Institute, Pacific Northwest Laboratories.
January 1984.
116pp.
8402240233.
22381:001.
In a study commissioned by the Nuclear Regulatory Commission, Batte11e's Pacific Northwest Laboratories examined practices for calibrating and/or determining biases for the principal nuclear material measurement systems in use by the nuclear industry: uranium gravimetry, uranium determination by reduction-oxidation titrimetry, plutonium determination by amperometric titration, isotopic analysis by mass spectrometry, isotopic-dilution assay'of iron and plutonium, 48
_. _ _ _ _ _ ; _ : _ w, marer% m uranium fluorometry, iron spectrophote -'try, mass measurements, volume-neasurements, flow measurements, n'ondes;ructive assays, and holdup neasurements.
A number of frequently used methods are described in this report.
The principle, procedures, apparatus, applications, and calibration for each are disc;ssed.
The sources of measurement bias are identified, also the etrected magnitudes of errors associated with' the methods.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
OZTUNALI,0.I.
Dames & Moore.
ROLES,G.W.
NRC - No Detailed Affiliation Given.
February 1984.
531pp.
8402280006.
22415:001.
A calculational methodology is presented which can,be used.te
~
ostimate impacts from disposal of radioactive waste by,less 4
restrictive means ("de minimis" waste disposal).
The tethodology consists of two computer codes: one, which determires annual radiological impacts to individuals and to populth' ions from release of de minimis waste into less restrictiv'e. disposal pathways, and another which determines :imiting concentrations of radionuclides based upcn comparison with a set of individual d o s'e limitation criteria.
Operational impacts are calculated for d'e minimid waste
~
transportation, treatment by incineration,,and disposal.
Long-term impacts after disposal (e.g.,
groundwater higration) 'are also calculated as are possible impacts From rec $cle if metal or -g lars.
Alternatives for waste treatment / disposal include on-tj te, off-site as a municipal waste, and off-site as a h dz.; dous, waste /
_s NUREG/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT. URANIUM MILLS.
SWAJA, R. E. ; SIMS,C.S.
Oak Ridge National Laboratory.'
February,1984.
97pp.
8402280114.
ORNL-6023.
22416:199. -
This document provides guidance end procedures (or conducting /
s an occupational radiological monitor,ing ptogram at uranium mills.
Included are a review of the ob Jectives of an o'ccupatibTel monitoring is program and a description of nornal physicaland radiological onvironments at uranium mills.
Detaf1'sd magi,toring procedoras are presented for airborne particulates, radon and radon daughters, external radiation, and surface con,tagination.
Although specifically uritten for uranium mills, some of'tha procedures contained in this,
document may be applied to other trani;um recovery, Facilities with similar environments.
NUREG/CR-3601: MANAGEMENT AND ORGANI2ATJdNAL ASSESSMENTS: A PEVIEW OF
~
SELECTED ORGANIZATIONS. NADEL,M.V.:t KERWIN>C.M..Dattelle H'ama5
?
Battelle Memorial' Institute, >=iiFic Affairs Research Centers.
~
Northwest Laboratories.
February 1984.
'42p p.
6403070199.
PNL-4013.
22561:172.
s, m
This report reviews the processes and: criteria used by
^
organizations other then the NRC in' conducting managemenh,-and
~
organization audits and evaluations.
A~s part of a larger'pnoject assisting the NRC in establishing improved 4 Poc edurew'and go,idelines",i i
for assessing the management and or g an i z a t i on,o f ap p.(l'c an t s for nuclear power plant operating licenses
- this report pr on ceganizational assessment./,ovides a comparative perspective The organizations whose management audits are reviewed are state public utility commissions, the Comptroller of the Currency, the Department of Health and Human Services' Office of Health Maintenance Organizations, the Food and Drug Administration, the General Accounting Office, and a largo commercial insurance company.
This l
4S T l
l
report examines the purposes, areas of emphases, and processes used in these reviews.
These organizations conclude that management is the key performance of organizational functions.
NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1992. BAILEY,W.J.
Battelle Memorial Institute, Pacific Northwest Laboratories.
TOKAR,M.
NRC - No Detailed Affiliation Given.
March 1904.
99pp.
8404110312.
PNL-4817.
22997:135.
This annual report, the fifth in a series, provides a brief description of fuel performance during 1982 in commercial nuclear power-plants.
Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance ar e provided.
References to additional, more detailed information and related NRC evaluations are included.
NUREG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility. DOERGE,D.H.;
MILLER R.L.
United Nuclear Corp.
February 1984 54pp.
8403150214.
22649:052.
This document summarizes information concerning the decommissioning of the Plum Brook Reactor Facility, which was placed in a Nuclear Regulatory Commission (NRC) approved safe storage configuration.
The data were placed in a computerized information retrieval / manipulation system which permits future utilization of this information in decommissioning of similar facilities.
The information is presented both in computer output form and a manually assembled summarization.
Complete cost data were not readily available and decommissioning activities did not in all cases ccnform with-current criteria for the SAFSTOR decommissioning mode, thertfore no cost comparisons were made.
NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL SITES: 1982 Annual Report of Research Investigations On The Distribution, Migration And-Containment Of Radionuclides At Maxey Flats. Kentucky. KINBY,L.J.
Battelle Memorial Institute, Pacific Northwest Laberatories.
February 1984.
80pp.
8403070093.
22563:229.
Subsurface waters at Maxey Flats are anoxic, have a high alkaorganic carbon.
The trench leachates are extremely variable in composition.
Prominent radionuclides include (3)H, (60)Co. (90)Sr, (137)Cs, (238)(209)(240)Pu and (241)Am.
A wide spectrum of dissolved organic compounds is present in the-leachates, including EDTA, polar organics and decomposition products from the waste forms.
Cobalt-60 and plutonium are present as' EDTA complexes and (90)Sr and (137)Cs are associated with carboxylic acid type compounds.
The chemistry of these waters changes drastically as they become oxic and plutonium becomes less mobile under these new conditions.
Water enters the trenches by infiltration through the. trench caps, though subsidence areas, and through interfaces between new landfill and the original soil.
Lateral flow is very' complex and slow and apparently occurs nainly by fracture flow.
The plastic infiltration barrier installed in 1981-1982 has been effective in reducing soil' moisture if cracks and leaks are eliminated.
To date, no direct evidence of radionuclide transport to offsite locations by subsurface flow has been confirmed.
The offsite distribution of radionuclides, except for tritium,'is comparable to the ambient fallout-frem nuclear weapons testing.
50 i
Tritium concontrations in wotor offsito are ordors of magnitude below MPC levolo.
NUREG/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS.A Nultidimensional Stochastic Theory With Application To Fractured Rocks. WINTER,C.L.s NEUMAN,S.P.s NEWMAN,C.M.
Arizona, Univ. o f, Tucson, AZ.
March 1984.
66pp.
8404050505.
22912:091.
A multidimensional stochastic theory is presented for far-field dispersion due to the spatial variability of hydraulic conductivities.
We use a second-order perturbation approach to relate the far-field velocity vector, V,
and dispersion tensor, D,
to the mean and covariance of the local seepage velocity vector, v,
and the local dispersion tensor, d.
We find that, in general, V is not necessarily equal to the ensemble mean of v, micron, and that D is a second-rank symmetric tensor.
In the particular case where v x velocity vector = 0 (e.g.,
incompressible fluid in a rigid porous medium of uniform effective porosity), V becomes equal to micron, and our expressions for D simplify to those presented by Gelhar and Axness C19833.
We further extend a conclusion of these authors, that as the Peclet number, v,
increases, D becomes asymptotically linear in micron, by showing that it holds for arbitrary velocity covariance functions.
Finally, we derive expressions for D as a function of v for situations where the logarithm of hydraulic conductivity fits a j
spherical covariance or semivariogram function, as is.often the case.
~
These expressions are applied to log hydraulic conductivity data form packer tests conducted in seven boreholes penetrating fractured granites near Oracle, southern Arizona.
NURE0/CR-3614: CONSTANT EXTENSION RATE TESTING OF SA302 GRADE B MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS. CZAJKOWSKI,C.J.
Brookhaven National Laboratory.
Fobruary 1984.
48pp.
8402220099.
BNL-NUREG-51736.
22364:096.
A test program was conducted on welded specimens (both stress relieved and non stress relieved) of SA302 Grade B materials.
The specimens were tested in a constant extension rate apparatus in various environments in order to reproduce the transgranular cracking at Indian Point 3.
The report concludes that SA302 Grade B material is susceptible to transgranular stress corrosion cracking in constant extension rate testing with as little as 1 ppm chloride (as CuC1(2) in 268 degrees C H(2)O.
NUREG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS. CHU, W. ; LEE H. s DHIR,V.K.s et al.
California, Univ, o f, Los Angeles.. CA.
January 1984.
158pp.
l 8401250129, 21949:251.
An experimental investigation of two phase flow thriugh porous layers formed of non-heated glass particles (nominal di neter 1-6 mm) has been made.
Particulate bed depths of 30 cm and 70 cm were used.
i I
The effect of particle size distribution, bed porosity and bed stratification on void fraction and pressure drop through particulate beds' formed in cylindrical and rectangular test sections has been.
investigated.
The superficial velocity of liquid (water) is varied from 1.83-18.3. mm/s while the superficial velocity of gas (air) is varied from 0-68.4 mm/s.
These superficial velocities were chosen su that pressure drop and' void fraction measurement could be made for the porous layers in fixed and fluidized states.
A model based on drift 51
i flux epproach has boon developod for the void fraction in homogono,un beds.
Using the-two phase friction pressure drop data, the relative permeabilities of the two phases have been concluded with void fraction.
2 The void fraction and two phase friction pressure gradient in beds composed'of mixtures of spherical particles as well as shapes of I
different nominal sizes have also been examined.
It is found that the models for single size particles are also aoplicable to mixtures of particles if a mean particle diameter for
'.rs mixture is defined.
The observations in stratified beds i t, J i c a t e depletion or build l
up of voids at the interface between high and low permeability i
regions.
Blocking of the flow into one of the layers of laterally stratified beds caused the pressures at different horizontal locations at the same bed height to be different from each other.
NOREG/CR-3616: -TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS. BROCARD,D.N.
Alden i
Research Laboratory.
Sandia Laboratories.
Janeary 1984.
4Bpp.
8402010365.
ARL-124-83/M39F.
22061:040.
A loss-of-coolant-accident (LOCA) in a nuclear power plant could result in the formation of insulation debris which could transport to PWR sump screens (or BWR RHR suction intakes) and result in screen blockage.
This report presents the transport and screen blockage l
characteristics of reflective metallic insulation materials and I
supplements previously acquired information on fibrous in s ula ti o,n raterials (see NUREG/CR-2982).
These tests revealed that thin metallic fails (0.0025" and 0.004") could transport a low flow velocities, 0.2-0.5 ft/sec.
Thicker foils (0.008") transported at higher velocities, 0.4-0.8 ft/sec, and "as fabricated" half cylinder insulation units required l
velocities in excess of 1.0 ft/sec for transport.
These tests also l
provided information on screen blockage patterns that showed blockage could occur at the lower portion of the screen as fails readily flipped on the screen when reaching i t.
p.,
tests also revealed that, although transport of foils occurred in a fu! ding and tumbling mode, the fails did not become " water borne" and did not block the screen above their largest dimension.
A maximum 80% blacLace was observed in these tests.
NUREC/CR-3619: SURVEY OF COMMERCIAL NON-NUCLEAR SECURITY PROGRAMS.
ISHIMOTO,W.Y.
March 1984.
49pp.
8404120389.
24035: 152.
This study provides a limited, but current, review of security techniques and practices used in analogous non-nuclear commercial industries to defend against external threats.
Nine non-nuclear
(
commercial industries which engage in high-value or high-risk operations were interviewed.
Current security periodicals and books were also reviewed to determine whether there are any unique security practices, techniques, or procedures in use by non-nuclear commercial.
industries that may benefit the security posture of the NRC and its licensees.
The study briefly reviews ten specific types of threat posed by the external adversarys basic reasons for adversarial success; and detection and prevention strategies.
The " average" level of security,-as evidenced in practice, and the most stringent level of
]
security-used by the interviewees are also examined.
52 l-
l NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING. LEWIS,J.R.s MORGENSTERN,M.; RIDEOUT,T.B.i et al.
.Battello Mamorial Instituta, Pacific Northwest Laboratories.
March 1984.
129pp.
8403230200.
PNL-4832.
22741:077.
The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants.
The goals of the study were to assess for the NRC the offectiveness of current monitoring systems and procedures, to develop cceeptance criteria by which the adequacy of safety status monitoring systems can be evaluated, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue.
A review of safety i
system status monitoring practices indicated that current systems and i
procedures do not adequately aid control room operators in monitoring l
safety system status.
This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47).
In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status.
Also suggested are near-term guidelines that could reduce the likelihood of human orrors in specific, high-priority status monitoring tasks.
It is our recommendation that 1) Regulatory Guide 1.47 he revised to address these acceptance criteria, and 2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.
)
NUREG/CR-3622: A PROBABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN BY CYLINCRICAL GEOMETRY IMPEDANCE PROBES.
ALLGOOD,G.O.; ROBERTS.M.J.
Oak Ridge National Laboratory.
February 1984.
65pp.
8403230057.
ORNL/TM-8841.
22742:300.
A probabilistic model of annular-dispersed flow in a reactor sub-channel as seen by cylindrical geometry impedance probes.is developed from a finite element model of these electrodes in an inhomogeneous, isotropic medium of water and steam.
The model is based on a derived finite difference equation for the potential at the conter of a cube in terms of the potentials of the adjacent cubes and their material properties (Ampere's circuital law, ?ow-frequency case).
The probabilistic model returns admittance (or capacitance) l signals for two sets of probes based on specified film and two-phase void fractures.
These signals will have temporal variations based on the flow velocities, the probe separation distance, and'the frequenc'y content of signals.
The model assumes one-dimensional flow.
NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC l
APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING (SAFT-UT).
l BUSSEL,L.J.s COLLINS H.D.s DOCTOR,S.R.
Battelle Memorial Institute, I
Pacific Northwest Laboratories.
March 1984.
112pp.
8404110296.
PNL-4957, 22997:233.
The' development and capabilities of synthetic aperture focusing techniques for ultrasonic testing (SAFT-UT) are presented.
The purpose of SAFT-UT is to. produce high-resolution images of the-(
interior'of opaque objects.
The goal of this work is to develop and
(
1mplement methods.which can be used to' detect and to quantify the ostent of defects and cracks-in critical components of nuclear roactors (pressure vessels, primary piping systems, and nozzles).
This report places particular emphasis upon the practical experimental rosults'that-have been obtained using SAFT-UT as.well as the-i b
thoorotical background that underlies synthetic oporture focusing.
A discussion regarding high-speed and "real-tima" impismsntations of two-and three-dimensional synthetic aperture focusing is also presented.
NUREG/CR-3631: RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS. NELSON,W.R.
EG&G, Inc.
March 1984.
26pp.
8404170031.
EGG-2293.
24091:314.
The United States Nuclear Regulatory Commission is sponsoring a Project performed by EG&G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) to evaluate different display concepts for ust in nuclear reactor control rooms.
Included in this project is the evaluation of the response tree computer based decision aid and its associated displays.
This report serves as an overview of the response tree methodology and how it has been implemented as a computer based decision aid utilizing color graphic displays.
A qualitative assessment of the applicability of the response tree aid is generalized to address a larger category of computer aids, those known as knowledge based expert systems.
General characteristics of expert systems are discussed, as well as examples of their application in other domains.
A survey of ongoing work on expert systems in the nuclear industry is presented, and an assessment of their potential applicability is made.
Finally, recommendations for the design and evaluation of computer based decision aids are presented.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
WART, R. J. s SKIBA.E.L.s CURTIS,R.H.; et al.
Acres American, Inc.
February 1984.
191pp.
8402220358.
22364:145.
This report describes benchmark problems to test computer codes used in design of nuclear waste repositories.
Problems with analytical solutions, hypothetical repository design problems, and problems simulating field experiments are used.
Types of problems include: thermal conduction, geomechanical stress and coupled stress, ground water flow, and temperature problems.
Specific phenomena addressed are thermal conduction, propagation, thermal expansion, and consolidation, i
l l
NUREG/CR-3642: A COBRA / TRAC,BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION. GUIDOTTI.T.E.3 THURGOOD,M.J.
Battelle Memorial Institute, Pacific Northwest Laboratories.
March 1984.
243pp.
8404100521.
PNL-4971.
22977:039.
This report documents the simulation of a double-ended (200 percent), cold leg break, loss-of-coolant accident in a PWR equipped with an upper head injection system.
The simulation was performed i
using the COBRA / TRAC thermal-hydraulic computer program developed at the Pacific Northwest Laboratories for the Nuclear Regulatory Commission to analy ze PWR 's with the upper head injection system.
This analysis used best-estimate assumptions and a 556 cell cultidimensional mesh in the vessel.
Each of the four primary loops uere modeled.
Four cooling periods were predicted prior to the beginning of bottom reflood.
The first cooling period was caused by the flashing of liquid in the lower plenum while the other three cooling periods were related to the hydrodynamic behavior in the upper head and the delivery of upper head cooling watsr to the core.
The entire core was quenched during the first period of upper head water l
delivery to the core.
The peak clad temperature during the transient 54
ucs 1,155 degroco fahronhoit end occurrod 8 soc ofter the initiation of blawdown.
Tho pook temporoturo romainod below 600 degrees fchrenheit for the remainder of the transient.
The transient behavior of the reactor coolant system is presented in the form of plots of the koy thermal hydraulic variables as a function of time.
Major phenomena calculated during the transient (e.g.,
multidimensional offects, counter-current flow limiting, ECC bypass, etc.) are discussed in detail.
These results are compared with a Westinghouse SATAN calculation.
NUREG/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE ORGANIZATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS. SOMMERS,P.
Battelle Human Affairs Research Centers.
Battelle Memorial Institute, Pacific Northwest Laboratories.
February 1984.
656pp.
8403190055.
PNL-4906.
22678:001.
The purpose of this report is to assist applicants for a nuclear power plant operating license through a structured review of the organization and administration literature.
The Nuclear Regulatory Commission reviews an applicant's proposed organization and administration as part of the operating license review.
NRC is developing draft Guidelines for a Utility Organization Plan and a proposed Workbook for Assessment of Organization and Administration for reviewing responses to the guidelines.
It is the intention of the NRC to incorporate these documents when completed into Chapter 13 of the Standard Review Plan NUREG-0800.
This report assists users of the Guidelines and Workbook by providing a guide to the academic literatures relevant to the concepts used in these two regulatory documents.
Persons preparing responses to the Guidelines or reviewing these responses can locate literature relevant to a particular topic discussed in the Guidelines or Workbook through use of this report.
This report is organized as follows.
The Introduction describes the purpose and scope of the review.
Details of the search processes used to identify relevant literature are also covered.
The next section documents government concern with nuclear plant organization end administration issues through a review of major reports and Congressional hearings.
The third and fourth sections contain obstracts of selected items and a lengthy bibliography of the relevant items identified in nur literature searches.
The final section of the report is a keyword index which allows readers to identify relevant items in the abstract and bibliography sections through use of kogwords.
The keywords include the major concepts used in the Guidelines and Workbook to facilitate location of relevant items in the literature.
NUREG/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION. SRINIVASAN,M.G.s KOT,C.A.s HSIEH,B.J.
Argonne National Laboratory.
January 1984.
117pp.
8403070114.
ANL-83-20.
22562:055.
The experience with dynamic. testing of as-built large civil engineering structures other than nuclear power plant buildings is ovaluated.
A review of literature on the dynamic testing of a large number of structures formed the basis for this evaluation.
Methods of oxcitation and data analysis for determining dynamic parameters from maasured response are evaluated.
Tests of as-built structures have enabled a partial verification of linear models, have revealed the inadequacies of some assumptions made in conventional analytical mothods and have been the major source of data on damping.
Tests 55
boforo cnd aftor have boon usod to cbtain a mmosuro of the chcnge in i
tho intogrity of a structure sub Jected to strong oxcitation.
Tests on some structures at various excitation levels coupled with the development of analytical methods for determining nonlinear models from such tests is needed before testing can be used as a means of predicting response to strong excitation.
However, recent improvements in experimental and analytical techniques associated with low-level testing of as-built structures enhance its utility for model verification and improvement and for the investigation of phenomena such as damping associated with soil-structure interaction.
NUREG/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report. YOUNG,M.s TAKEUCHI,K.s MENDLER.J.s et al.
Westinghouse Electric Corp.
March 1984.
19Bpp.
8403230208.
EPRI NP-3494.
22743:096.
This report describes the Westinghouse MB-2 model boiler test facility and the test program currently planned (with Westinghouse /EPHI/NRC funding) to investigate various types of possible accidents which might occur in a PWR steam generator.
The planned tests will simulate loss of feedwater (LOF) transients, various steam generator tube rupture (SGTR) scenarios, and steamline breaks (SLB).
The facility will be extensively modified to allow measurement of local wall and fluid temperatures, and to measure possible moisture carryover during the SLB and SGTR tests.
This report is divided into six sections.
The first three sections describe the facility and the new components and instrumentation to be installed.
The next section is a detailed scaling analysis,of MB-2.
Section S describes the analysis of the data which is planned.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL. HARRIS,D.R.s BURN,R.R.s CLARK,L.s et al.
Rensselaer Polytechnic Institute, Troy, NY.
February 1984.
16Spp.
8403190437.
22680:001.
The impacts of a proposed rule requiring conversion of source cr all NRC-Licensed training and research reactors to low enrichment uranium fuel were determined.
Consideration focused on: technical feasibility, functional impacts, licensing, and schedule.
It was determined that the cost of conversion would range from $1,000,000 to
$12,000,000, depending on rule criteria.
NUREG/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
PEERENBOOM,J.P.s BUEHRING,F.A.
Argonne National Laboratory.
March 1984.
66pp.
8404050473.
ANL/EES-TM-241.
22912:023.
Shutdowns of nuclear power plants typically result in significant increases in operating costs (production costs) for the affected utilities.
This report presents a framework that will help users evaluate the reasonableness of estimated production-cost changes resulting from reactor shutdowns.
The framework consists of three basic steps: (1) preliminary evaluation and classification of the I
outage. (2) evaluation of the input data and assumptions, and (3) evaluation of production-cost results.
Several simplified procedures for estimating changes in production costs are presented.
l
NUREG/CR-3674: DESIGNING VEGETATION COVERS FOR LONC-TERM STABILIZATION OF URANIUM MILL TAILINGS. BEEDLOW,P.A.
Battello Memorial Institute, Pacific Northwest Laboratories.
March 1984.
103pp.
8403230207.
PNL-4986.
22741:207.
The use of vegetation and vegetation-rock combinations for long-term stabilization of uranium mill tailings is discussed.
Interactions between surface covers and the tailings containment are identified and used as the basis for designing protective covers.
The role of vegetation in erosional processes is reviewed and the offectiveness of vegetation for controlling erosion in the western U. S.
is d i s c u s r.e d.
Principles of revegetation are presented.
Environmental influences on vegetation are reviewed.
The effects of surface covers on water dynamics within the containment system are presented.
A systematic approach is given for designing protective covers using vegetation.
NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT. SULLIVAN,P.J.s SWARTZMAN,G.L.
Washington, Univ. o f, Seattle, WA.
March 1984.
29pp.
8404120390.
24034:306.
The dynamics of the Hudson River striped bass (Morone Saxatilis) stock were analyzed using a stochastic age structured model.
The offect of river flow on recruitment was combined with the mortality due to fishing and power plant water uptake to obtain an overall offect of these variables on the fishery.
Model equations and parameters were documented and their underlying assumptions presented.
Preliminary model runs resulted in yields well below those 4
ectually observed.
Calibration of model parameters brought these values closer to the observed yields, but stock values proved inexact.
The influence of power plant mortality on fishery yield was ovident, but the simulation results remain inconclusive.
NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT. COFFMAN,W.s VOGT,D.; MILLS,M.
CorSTAR Research, Inc.
March 1984.
314pp.
8404020158.
22848:012.
This is the fourth in a series of five reports that will provide critical reviews and summaries of computer programs that can be used to analyze the potential performance of a high-level radioactive waste repository.
The computer programs identified in this report address the performance of a waste package, including the areas of thermal analysis, structural analys;s, and special purpose programs.
The report provides a summary description of 19 computer programs.
Fourteen of these computer programs are being used by the U.S.
Dopartment of Energy or the U. S.
Nuclear Regulatory Commission to analyze various aspects of waste package performance.
The remaining five codes can be used to analyze phenomena that may be important in umste package performance.
4 NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Anclysis Program. LIN.C.C.s ECONOMAS C.4 LEHNER J.R.s et al.
Brookhaven National Laboratory.'
March 1984.
281pp.
8404110024.
BNL-NUREG-51754.
24003:001.
CONTEMP4/ MOD 4 is a digital computer program that describes the response of multicompartment containment systems sub Jected to postulated loss-of-coolant accident (LOCA) conditions.
The program is-written in FORTRAN IV and can accommodate both pressurized water roactor (PWR) and boiling water reactor (BWR) containment systems.
57
Also, both donign besio eccidsnt (DBA) cnd dogrcdod coro type: LOCA conditions can be analyzed.
The progrcm calculaton the tima variation of compartment pressures, temperatures and mass and energy inventories due to intercompartment mass and energy exchange, LOCA source terms,
}
containment fans and pumps, cooling sprays, heat conducting structures, sump drains, PWR ice condensers, BWR pressure suppression systems hydrogen combustion within compartments and energy transfer due to gas radiation.
Dynamic storage allocation (DBA) is used to limit the amount of ccmputer core used for each problem and to provide the multicompartment capability of up to 999 individual compartments.
The program employs an implicit algorithm to compute junction flow uhen numerically induced flow oscillations are encountered.
This capability provides significant reduction of computer run time i
relative to previous codes in the CONTEMPT series.
i NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR j
POWER PLANTS. WHITE,J.R.i EVERSOLE,R.E.s FARNSTROM,K.A.s et al.
Remote Technology Corp.
March 1984.
100pp.
8404020268.
22875:001.
This report presents and demonstrates a cost-effective approach for robotics application (CARA) to surveillance and inspection and work in existing nuclear power plants.
The CARA was developed by the Remote Technology Corporation to systematically determine the specific surveillance / inspection tasks, worker hazards, and access or equipment placement restraints in each I
of the many individual rooms or areas at a power plant.
Solutions for each area are based upon the modular arrangement of commercially-available sensors and other robotic components.
l Techniques for maximizing the cost effectiveness of robotics are l
emphasized in the report including: selection of low-cost robotic I
components, minimal installatior work in plant areas, portable systems for common use in different areas, and standardized robotic modules.
l Factors considered as benefits are reduced radiation exposure.
man-hours, power outage, waste material, and worker safety concerns.
A partial demonstration of the CARA approach to a large BWR plant is provided in the report along with specific examples of robotic l
installations.
Full utilization will require in-depth application at specific plants.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE ~ REPOSITORY SITE PROJECTS.
KELMERS,A.D.s CLARK,R.J.s CUTSHALL,N.H.s et al.
Oak Ridge National Laboratory.
March 1984.
59pp.
8404160218.
ORNL/TM-9109.
24065:234.
This report summarizes the results of the activities of the first year in a Nuclear Regulatory Commission (NRC) supported, experimentally oriented project to evaluate geochemical information (primarily radionuclide sorption and apparent concentration limit values).
The geochemical information is being developed by the Department of Energy (DOE)'in their high-level waste repository site projects for use in site performance assessment calculations.
During this period, work was focused on the candidate site in basalt being.
characterized by the Basalt Waste Isolation Project (BWIP).
Activities involved measuring sorption values for technetium and neptunium under geochemical parameters expected to be relevant.to the site.
Oxic (air saturated), reducing (hydrazine added), and anoxic i
l (air excluded) redox conditions were employed in batch contact tests.
Geochemical modeling calculations using.available thermodynamic dcta and codes also were carried out to evaluate site groundwaters.
The 58 l
roculto cro ccmparod with valuos publinhod by BWIP es "concorvativa best estimate" numbers in their Site Characterization Report and to i
other values and information in other available BWIP reports.
i e
i d
1 J
e 1
i l
4
l i
1 l
l Contractor Report Number index This index lists, in alphabetical order, the contractor-issued report codes for ths NRC contractor reports in this compilation. Each contractor code is cross-referenced to the NUREGICR for the report and to the 10-digit NRC Document Control System accession number.
SECONDARY SECONDARY REPORT REPORT REPORT REPORT NUMBER NUMBER NUMBER NUMBER ANL-82-25 VO1 NUREG/CR-2896 VO1 EPRI NP-3494 NUREG/CR-3661 ANL-82-25 VO2 NUREG/CR-2896 VO2 HEDL-TME 83-9 NUREC/CR-3285 ANL-82-41 NUREG/CR-2970 VO4 LA-9716-MS NUREG/CR-3224 ANL-83-11 VO3 NUREG/CR-3359 VO3 LA-9853-MS NUREQ/CR-3448 ANL-83-11 VO4 NUREG/CR-3359 VO4 LA-9910-MS VO1 NUREG/CR-3522 VOt ANL-83-20 NUREG/CR-3649 LA-9910-MS VO2 NUREG/CR-3522 VO2 ANL-83-64 NUREC/CR-3435 LA-9929-MS NUREG/CR-3242 ANL/EES-TM-233 NUREG/CR-3553 MLM-2o83 NUREG/CR-2926 ANL/EES-TM-241 NUREG/CR-3667 ORNL-5934 NUREG/CR-3491 ANL/ES-128 RO1 NUREG/CR-2869 RO1 ORNL-5936 NUREG/CR-3057 ARL-124-93/M39F NUREC/CR-3616 ORFL-5978 NUREG/CR-3389 BHARC-3OO/83-03 NUREG/CR-3645 ORNL-5988 NUREG/CR-3490 BHARC-400/83-01 NUREG/CR-3601 ORNL-6023 NUREQ/CR-3598 CNL-NUREG-51454 NUREQ/CR-2331 VO3 N2 ORit-6024 NUREG/CR-3482 BNL-NUREG-51559 NUREG/CR-2815 ORNL/CSD-90 NUREQ/CR-2397 BNL-NUREG-51593 NUREG/CR-2721 ORNL/CSD/TM-197 NUREQ/CR-3056 BNL-NUREG-51630 NUREG/CR-3091 VO3 ORNL/NSIC-2OO NUREG/CR-2OOO VO2N12 BNL-NUREG-51699 NUREQ/CR-3444 VO1 ORNL/NSIC-2OO NUREG/CR-2OOO VO3 N1 BNL-NUREG-51712 NUREG/CR-3496 ORNL/NSIC-2OO NUREG/CR-2OOO VO3 N2 BNL-NUREG-51721 NUREG/CR-3529 ORNL/NSIC-216 NUREG/CR-3543 l
BNL-NUREG-51722 NUREQ/CR-3530 ORE /SUB-7576/3 NUREG/CR-3508 BNL-NUREG-51723 NUREQ/CR-3531 ORft/SUB/81-908 NUREG/CR-3525 BNL-NUREG-51736 NUREG/CR-3614 ORNL/TM-8401 NUREC/CR-3172
)
t BNL-NUREG-51754 NUREQ/CR-3716 ORit/TM-8413 NUREQ/CR-2810
)
EQQ-22OO NUREG/CR-2335 ORit/TM-8418/V1 NUREQ/CR-2824 VO1 EGO-2272 NUREG/CR-3461 ORPL/TM-8653 NUREQ/CR-3153 l
E Q-2284 NUREQ/CR-3556 ORNL/TM-8683 NUREQ/CR-3181 EGG-2293 NUREC/CR-3631 ORR/TM-8604 NUREC/CR-3501 ENICO-1125 NUREQ/CR-3067 ORM./TM-8755 NUREC/CR-3275 j
ENICO-1137 NUREG/CR-3512 ORNL/TM-8787/V2 NUREG/CR-3334 VO2 l
61
SECONDARY SECONDARY REPORT REPORT REPORT R EPORT NUMBER NUMBER NUMBER NUMDER ORNL/TM-8787/V3 NUREQ/CR-3334 VO3 PNL-4971 NUREQ/CR-3642 ORNL/TM-8794 NUREQ/CR-3502 PNL-4986 NUREQ/CR-3674 Or'NL/TM-8796/V3 NUREQ/CR-32OO VO3 SAND 81-2027 NUREG/CR-2932 VO2 ORNL/TM-8841 NUREQ/CR-3622 SAND 82-0904 NUREC/CR-2679 VO3 ORNL/TM-8849/V2 NUREQ/CR-3422 VO2 SANDB2-1179 NUREQ/CR-2812 ORNL/TM-8862/V1 NUREQ/CR-3439 VO1 SANDB2-2933 NUREQ/CR-3351 ORNL/TM-8862/V2 NUREC/CR-3439 VO2 SAND 83-1171 NUREC/CR-3329 VO3 2
ORNL/TM-8909 NUREQ/CR-3549 SAND 83-1482 NUREQ/CR-3412 ORNL/TM-8921/V3 NUREQ/CR-3492 VO3 SANDB3-1916 NUREQ/CR-3484 ORNL/TM-8950 NUREQ/CR-3523 SAND 83-2098 NUREQ/CR-3532 ORNL/TM-9109 NUREQ/CR-3730 SANDB3-2238 NUREQ/CR-3547 PNL-3786 NUREQ/CR-3396 SANDB3-7095 NUREQ/CR-3309 PNL-3955 NUREQ/CR-3579 SAND 83-7471 NUREQ/CR-3616 PNL-4542 NUREQ/CR-3070 UCRL-53483 NUREQ/CR-3428 PNL-4543 NUREQ/CR-3071 UCRL-53487 NUREQ/CR-3477 PNL-4583 NUREQ/CR-3104 UCRL-53488 NUREC/CR-3478 PNL-4629 NUREQ/CR-3562 UCRL-53490 NUREC/CR-3483 j
PNL-4692 NUREQ/CR-3580 UCRL-53491 NUREC/CR-3526 PNL-4693 NUREC/CR-3581 UCRL-53492 NUREQ/CR-3536 PNL-4695 NUREQ/CR-3561 WCAP-10475 NUREQ/CR-3661 PNL-4711 NUREQ/CR-3578 WWL/TM-1791-1 NUREQ/CR-3390 PNL-4773 NUREQ/CR-3554 Y/DS-178 NUREQ/CR-3251 PNL-4813 NUREQ/CR-3601 PNL-4817 NUREQ/CR-3602 PNL-4032 NUREQ/CR-3621 i
PNL-4904 NUREQ/CR-3560 j
PNL-4906 NUREQ/CR-3645 PNL-4908 NUREQ/CR-3563 PNL-4923 NUREQ/CR-3573 PNL-4957 NUREQ/CR-3625 l
l i
62
Personal Author index This index lists the personal authors of NRC staff and contractor reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by that author. If further information is needed, refer to the main citation by the NUREG number.
3 ADEL,K.H.
NUREQ/CR-3554: RADIONUCLIDE MIQRATION IN OROUNDWATER. Annual Progress Report For 1902.
ADAMS,R.E.
NUREQ/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly Progress Report For April-June 1903.
ALEXANDER,D.H.
NUREO-1046 DRFT: DISPOSAL OF HICH-LEVEL RADI0 ACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Report For Comment.
ALLCOOD,Q.O.
NUREQ/CR-3622: A PRODADILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUDCHANNEL AS SEEN DY CYLINDRICAL QEOMETRY IMPEDANCE PRODES.
ANKLAN,T.M.
NUREC/CR-3502: HIGH DRYOUT GUALITY FILM DOILINC AND STEAM C00LINC HEAT TRANSFER DATA FROM A ROD DUNDLE.
ARNOLD,W.D.
NUR EQ/CR-3309: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
AYRAULT,C.
NUREQ/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECENDER 1982.
BAILEY,W.J.
NUREQ/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
BALL,D.Q.
NUREQ/CR-3491: OCA-II,A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUDJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
BALL,S.J.
NUREQ/CR-3492 V02: HICH-TEMPERATURE QAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION OUARTERLY PROGRESS REPORT, APRIL 1-VUNE 30,1983.
NUREQ/CR-3492 V03: HIGH-TEMPERATURE CAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION OUARTERLY PROGRESS REPORT, JULY - SEPTEMBER 1983.
BARI,R.A.
NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PR00RANS SPONSORED BY THE OFFICE OF NUCLEAR REQULATORY RESEARCH.Guarterly Progress Report, April-June 1903.
NUREQ/CR-2 SIS: PRODADILISTIC SAFETY ANALYSIS PROCEDURES QUIDE.
63
BARLETTA,R.E.
NUREQ/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
DARRY,L.W.
NUREG-0325 R06:
U. S.
NUCLEAR REQULATORY COMMISSION FUNCTIONAL ORGANIZATION CHARTS.
BARTTER,W.D.
NUREQ/CR-3275: JOB ANALYSIS OF TW ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONEL RELI ABILITY MODEL.
BAUMANN,B.L.
NUREQ/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Annual Summary Report - Fiscal Year 1983.
BEARE,A.N.
NUR EQ/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
EEEDLOW,P.A.
NUREQ/CR-3674: DESIGNING VEGETATION COVERS FOR LONO-TERM STABILIZATION OF URANIUM MILL TAILINGS.
BELJWAS,T.E.
3 NUR EQ/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
BELL,C.R.
NURE0/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERQETICS.
BELL,N.E.
NUREQ/CR-3104: AQUIFER RESTORATION TECHNIQUES FOR IN-SITU LEACH URANIUM MINES.
BENDA,B.J.
NUREQ/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK BROADENING ON TE SEISMIC RESPONSE OF PIPING SYSTEMS.
BERNREUTER,D.L.
NUREQ/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
BIAN,S.H.
NUREQ/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
BICKFORD,R.L.
NUREQ/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERQRANULAR STRESS CORROSION CRACKED INCONEL STEAM QENER ATOR TUBES.
NUREQ/CR-3562: STEAM QENERATOR TUDE INTEGRITY PROGRAM LEAK RATE TESTS-PROGRESS REPORT.
BIRD,S.K.
NUREQ/CR-3067: CALIBRATION SOURCES FOR THE Q-M COUNTER USED WITH THE BNL AIR BAMPLER.
BLACKMAN,H.S.
NUREQ/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREQ/CR-3556: NONINTERACTIVE BIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
BLUHM,D.
NUREQ/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
BLUMENTHAL,H.S.
NUREG-1045: QUIDANCE ON THE APPLICATION OF COMPENSATORY SAFEQUARDS MEASURES FOR POWER REACTOR LICENSEEB.
B0HN,M.P.
NUREQ/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEIBMIC RISK AT THE ZION NUCLEAR POWER PLANT.
BOVELL,C.R.
NUREQ/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
BRADLEY,E.R.
64
NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR l
IFA-432.
' BRAY,M.A.
NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF l
ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
BROCARD,D.N.
l NUREC/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
8%ODZINSKI,R.L.
NUREG/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Roport For 1902.
BROUNS R.J.
NUREC/CR-3584: COMMONLY USED NUCLEAR MATERIAL MEASUREMENTS AND THEIR SOURCES OF ERROR.
> BUCHANAN,J.A.
NUREG/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis.
BUCKALEW,W.H.
NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONDENERGETIC ELECTRON IRRADIATIONS.
' BUEHRING.W.A.
NUREG/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
IBUKHARI.M.
NUREG/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPARATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
BUNPUS,S.E.
i NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
' BURN,R.R.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF 1
UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
'BUSLIK A.J.
NUREQ/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
'BUSSEL L.J.
NUREG/CR-3623: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC j
APERTURE FOCUSING TECHNIQUE FOR ULTRASONIC TESTING (SAFT-UT).
'BYERS,K.R.
NUREC/CR-3584: COMMONLY USED NUCLEAR MATERIAL MEASUREMENTS AND THEIR COURCES OF ERROR.
} CANONICO,D.A.
)
l NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
1 lCARDWELL,R.G.
NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
CASADA M.L.
NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY ADING TREND. Progress Report September 1983.
' CASE F.I.
NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
lCATTON,I.
NUREG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
CER~ONE, R. J.
N""tEG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NOCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June
[
.1983.
66 i-
,-,-.n, n------.a
-,v.
- -...,, = - - -
1 CHAPMAN,R.H.
NUREO/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN i
REPLICATE LOCA SIMULATION TESTS.
CHEN,J.C.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
CHEVERTON,R.D.
NUREG/CR-3491: OCA-II,A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
CHORA,0.K.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1902.
CHRISTENSEN.D.
NUREG/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
CHU W.
l NUREG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
- l CHUANG,T.Y.
NUREG/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK BROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
CHUNG,H.M.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION l
LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
CLARK,L.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM l
FUEL.
CLARK,R.A.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LA3 ORATORY PRODUCED i
INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
j NUREG/CR-3562: STEAM GENERATOR TUBE INTEGRITY PROGRAM LEAK RATE TESTS-PROGRESS REPORT.
NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Rep or t - 1982.
CLARK,R.J.
i NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION
(
DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
CLEVELAND,J.C.
NUREC/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
NUREQ/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION QUARTERLY PROGRESS REPORT, JULY - SEPTEMBER 1983.
COFFMAN W.
NUREQ/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
COHEN L.
NUREG-0037. VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report. July-September 1983.
I COLEMAN P.R.
NUREQ/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT SITING.
COLLINS,H.D.
I NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC 66 i
l APERTURE FOCUSING TECHNIQUE FOR ULTRASONIC TESTING (SAFT-UT).
COOK J.A.
NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
CO3TELLO.F.
NUREG-0837 VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report, July-September 1983.
COVER,L.C.
NUREC/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
COWLEY,P.J.
1 NUREC/CR-3621: SAFETY SYSTEM STATUS MONITORING.
CRAVEN,S.M.
M HCO/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED j
HCDA.
CROSS,K.E.
NUREQ/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
CROWE D.S.
NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
CROWLEY,J.L.
NUREQ/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
CUNNINGHAM M.E.
NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
CURTIS,R.H.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
CUTSHALL N.H.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
CZAJKOWSKI,C.J.
NUREG/CR-3614: CONSTANT EXTENSION RATE TESTING OF SA302 GRADE B 4
I MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
!DALLMAN,D.J.
NUREC/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE i
UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY j
TEST RESULTS.
, DAVIS,L.A.
NUREC/CR-3390: DOCUMENTATION AND USER'S GUIDE:UNSAT2 - VARIABLY I
SATURATED FLOW MODEL.(Including 4 Example Problems).
DAVIS M.S.
nun. 0/CR-3444 VO1-THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION,.ASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annua! Rep ort.
DAVIS R.E.
NUREG/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
DEED 2,W.E.
NUREG/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30,.
1983.
DEUTCCH W.J.
NUREG/CR-3104: AGUIFER RESTCRATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
DHIR.V.K.
67
j NURE6/CR-3619: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
j DOCTOR,P.G.
NUREG/CR-3561 : EDDY CURRENT ROUND ROBIN TEST ON LADORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES NUREC/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Rep ort On Data Acquisition / Statistical Analysis.
DOCTOR,S.R.
NUREQ/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING ' (SAFT-UT).
2 DODD.C.V.
NUREC/CR-2024 VO!: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUDING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING j
PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
DODSON,M.E.
NUREQ/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LINE j
NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress i
Report.
DOERGE,D.H.
3 NUREC/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
1 Summary Report - Plum Brook Reactor Facility.
j DOMANUS.H.M.
NOREG/CR-2896 VO1: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF i
SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User 's Manual.
1 NUREG/CR-2896 VO2: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment.And Verification.
NUREG/CR-3435: A NEW IMPLICIT NUMERICAL SOLUTION SCHEME IN THE COMMIX-1A COMPUTER PROGRAM.
I DORRIS,R.E.
NUREQ/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
DOUGAN,J.R.
l NUREC/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERI A.
DRAME J.B.
NUREG/CR-3491: OCA-II A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND l
3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPERATURE AND PRESSURE TRANSIENTS.
i DURFEE,R.C.
NUREQ/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT j
SITING.
ECONOMAS. C.
j NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis' Program.
I EDMONDS D.P.
NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL.
PIPE WELDS.
EINSIGER R.E.
NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
EL-BASSIONI.A.
I NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
ERASLAN,A.
NUREG/CR-3172: ' FLOWER: A COMPUTER CODE FOR SIMULATING :THREE-DIPEENSIONAL i
-FLOW TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL' REGIONS.
88 i
=- _
E~CAMBRACK,C.B.
NUREQ/CR-3579: STEAM QENERATOR GROUP PROJECT Progress Report On Data Acquisition / Statistical Analysis.
EVANS,D.D.
NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Report For Comment.
EVERTOLE,R.E.
j NUREQ/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR POWER' PLANTS.
FAGER,J.E.
NUREQ/CR-3584: COMMONLY USED NUCLEAR MATERIAL MEASUREE NTS AND THEIR COURCES OF ERROR.
FANDUS,F.
NUREQ/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
i FARNSTROM,K.A.
NUREQ/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR i
POWER PLANTS.
FEDERMAN,P.J.
NUREQ/CR-3275: VOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONPEL RELI ABILITY MODEL.
FENTON,D.L.
NUNEQ/CR-3242: THE LOS ALAMOS NATIONAL LADORATORY/NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
l FISHCHOFF B.
NUREQ/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
FORD,R.E.
NUREQ/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
4 FOWLER,R.D.
NUREQ/CR-3461 : RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE ~ OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
FRA!OLA,J.
NUREQ/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES QUIDE.
1 FRESCO,A.
NUREQ/CR-3531: REVIEW OF SEADROOK UNITS 1 AND 2 AUXILIARY FEEDWATER
)
BYSTEM HELIABILITY ANALYSIS.
l FURBAL.D.T.
NUREQ/CR-2932 VO2: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
GERTMAN,D.I.
NUREQ/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
OILMORE,W.E.
NUREQ/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-QENERATED DISPLAYS.
OINSBERG,T.
NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PROGRANS SPONSORED BY THE OFFICE i
OF NUCLEAR REQULATORY RESEARCH. Quarterly Progress Report. April-June 1983.
CLAIS,J.
NUREQ/CR-3573: PERSONNEL EXPOSURE FROM RICHT CYLINDRICAL SOURCES l
(PERCB). The Theory,The Code And Examples.
l GOODWIN,G.M.
NUREQ/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL l
PIPE WELDS.
GREENE,G.A.
NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE 69
OF NUCLEAR REGULATORY RESEARCH.Guertorly Progross Report April-Juno i_
1983.
CRECORY,W.S.
NUREG/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UN< ERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
GREIMANN,L.
NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
QUIDOTTI.T.E.
NUREG/CR-3642: A COBRA / TRAC, BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
GUPPY,J.C.
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983.
j HADLEY,R.T.
NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES 4
(PERCS). The Theory,The Code And Examples.
HALL R.E.
NUREC/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report. April-June 1983.
NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
HARDTY,R.
NUREC/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES i
(PERCS). The Theory,The Code And Examples.
HARRINGTON,R.M.
l NUREG/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES l
FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, l
APRIL 1-JUNE 30,1983.
NUREC/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, j
JULY - SEPTEMBER,1983.
I HARRIS,D.R.
l NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF i
UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
HARRISON.F.L.
NUREC/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF BLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
NUREQ/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
HARVEY,H.W.
j NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR i
POWER PLANTS.
HEBBLE.T.L.
NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
HEBDON.F.J.
NUREG-1022 SOI: LICENSEE EVENT REPORT SYSTEM. Description Of System And Guidelines For Reporting.
HENSLEY,W.T.
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTI AL NUCLEAR P'sWER PLANT MALFUNCTIONS.
HERMANN,0.W.
NUREC/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS I
SECTION LIBRARY.
HILL.L.J.
70
. ~.
-~
l.
NUR EO/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER.
PLANT.
HOENES,G.R.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics.
HOF,P.J.
NUREG/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis.
HOFFMAN,D.R.
NUREG-1042: TECHNICAL SPECIFICATIONS FOR SUSGUEHANNA STEAM ELECTRIC STATION, UNIT NO.2. Docket No.
50-388.(Pennsylvania Power And Light Company) 4 HOPKINS,G.
NUREC/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING.
PROGRAM. Task Plan / Scaling Analysis Report.
- HORSCHEL.D.S.
NUREG/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT l
JANUARY-MARCH 1983.
j HOY,H.C.
NUREC/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY l
AGING. TREND. Progress Report September 1983.
HSIEH.B.J.
NUREG/CR-3649: DYNAMIC TESTING OF AS-DUILT CIVIL ENGINEERING STRUCTURES I
-A REVIEW AND EVALUATION.
HUCHTON,R.L.
i NUREG/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BNL AIR SAMPLER.
j NUREC/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIDIODINE FROM MILK.
{ ILBERG,D.
NUREQ/CR-2815: PROBABILISTIC SAFETY ANALYSIS. PROCEDURES GUIDE.
ISHIMOTO,W.Y.
i NUREG/CR-3619: SURVEY OF COMMERCIAL NON-NUCLEAR SECURITY' PROGRAMS.
ISKANDER.S.K.
NUREG/CR-3491: OCA-II, A CODE FOR CALCULATING THE BEHAVIDR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPER ATURE AND i
PRESSURE TRANSIENTS.
3 -JACOBS.C.K.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL'INFORMATIDN DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
JOHNSON,J.J.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK j
AT THE ZION NUCLEAR POWER PLANT.
NUREC/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK BROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
~l JOHNSON.J.S.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE'QEOCHEMICAL INFORMATIDN DEVELOPED DY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE' PROJECTS.
- JUNG.J.
l NUREG/CR-3412: CONTAINMENT INTEGRITY PROGRAM 'JUARTERLY REPORT.
i JANUARY-MARCH 1983.
KASSNER,T.F.
NUREG/CR-2970 VO4: MATERIALW SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.'
KELLY,' J. M.
NUREG/CR-3563: COBRA / TRAC SIMULATIDN OF SEMISCALE S-UT-2 TEST.
KELLY,M.J.
NUREG/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
71
KELMERS.A.D.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
KERWIN,C.M.
NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMEhns: A REVIEW OF SELECTED ORGANIZATIONS.
KESSLER,J.H.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED DY DOE HICH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
KETELAAR.D.
NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS KIRDY,L.J.
NUREG/CR-3607: RADIONUCLIDE DISTRIDUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL SITES: 1982 Annual Report of Research Investigations On The Distribution Migration And Containment Of Radionuclides At Maxey Flats, Kentucky.
KJARMA,H.E.
NUREC/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LADORATORY PRODUCTED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
KOT C.A.
NUREG/CR-3649: DYNAMIC TESTING OF AS-DUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION.
KOZINSKY,E.J.
NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
KUPPERMAN,D.S.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTODER-DECEMDER 1982.
LAHEY,R.T.
NUREC/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR DWR APPLICATIONS.
NUREG/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPAR ATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
LAM,J.R.
NUREG/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF DLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
LANNING,D.D.
NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432.
LAPPA.D.A.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
LEE.H.
NUR EG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND i
STRATIFIED POROUS LAYERS.
LEHNER,J.R.
NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
LEWIS.J.R.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
LEWIS,M.
NUREG/CR-35BO: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
i LIKES.R.N.
NUREC/CR-3522 VO1: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF l
SPECI AL NUCLEAR MATERIALS, VOL 1: U Oxide Plus Graphite Powd er.
72
NUREO/CR-3522 VO2: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI AL. Volume 2: Thin Metal Foils OF Highly Enriched Uranium.
- LIN, C. C.
NUREC/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
LIN T.
NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
LIN W.
1 NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS. ESTUARIES AND COASTAL REGIONS.
lLINDEMER T.B.
NUREQ/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION QUARTERLY PROGRESS REPORT, JULY - SEPTEMBER 1983.
,LOCKWOOD,0.J.
NUREQ/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIONS.
LOFCREN,E.
NUR EG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
LONGEST.A.W.
NUREG/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
!LOOMIS.G.G.
i NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
fLOPRESTI.C.A.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCTED j
INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENERATOR TUBES.
'LORENZ,R.A.
NUR EG/CR-3171 : DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
lLOYDLA.V.M.
NUREG/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE,PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL CORROSION.
!LU.S.C.
NUREG/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK BROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
' LUCKAS. W. J.
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE i
OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Report. April-June I
1983.
lLUDWICK.J.D.
NUREQ/CR-2210: TECHNOLOGY, SAFETY AND CDSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
,MAISE.G.
NUR EG/CR-3716: CONTEMPT 4/ MOD 4 A Multicomponent Containment System i
l Analysis Program.
'MANAKTDLA.H.K.
l NUREC/CR-2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE i
CONTAINING CHELATING DECONTAMINATION CHEMICALS.
MARSHALL.R.S.
I NUREG/CR-3448: URANIUM HOLDUP MODELING.
MARTIN,H.L.
NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR 73
_ =
l POWER PLANTS.
MARTIN,R.A.
NUREG/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
MASNIK.M.T.
NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
NAST.P.K.
NUREC/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
MAXFIELD.B.W.
NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983.
MCARTHUR,D.A.
NUR EC/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
MCBRIDE,J.A.
NUR EC/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES 4
i AT NUCLEAR POWER PLANTS.
NCCLUNG.R.W.
NUREG/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING j
PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, l
1983.
MCINTYRE,J.M.
i NUREC/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Rep ort On Data Acquisition / Statistical Analysis.
MCKEON,T.J.
NUREG/CR-3560: EVALUATION METHODS FOR THE CONSEQUENCES OF BELOW WATER TABLE'MINE DISPOSAL OF URANIUM MILL TAILINGS.
MELBER.B.D.
NUREQ/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
I Interviews With Personnel From Nine Plants.
MENDLER.J.
NUREG/CR-3661: PROTOTYPICAL STEAM QENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Neport.
MENSING,R.W.
i NUREC/CR-3420: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK i
AT THE ZION NUCLEAR POWER PLANT.
I MERCER,B.W.
NUREC/CR-3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
MEYER.R.E.
NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
NUREG/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REQULATION OF GEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
NUREG/CR-3730: EVALUATIDN OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
MILLER,0.D.
NUREG/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE L
PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATIDN FROM A SIMULATED l
HCDA.
l MILLER N.E.
NUREG/CR-3427 VO3: LONG-TERM PERFORMANCE DF MATERI ALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
74 l
D i
ZILLER,R.L.
NURE3/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Annual Summary Report - Fiscal Year 1983.
l NUREO/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
% ILLS,M.
NURE3/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
%INOR,E.E.
i NURE3/CR-2932 VO2: EGUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CADLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT l
NO.
2.
MOIYA,P.S.
NURE9/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROCRESS REPORT OCTOBER-DECEMBER 1982.
100RE E.D.
NUREO/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
10REENSTERN,M.
NUREO/CR-3621: SAFETY SYSTEM STATUS MONITORING.
MORRIS,D.G.
NUREG/CR-3502: HIGH DRYOUT GUALITY FILM DOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD DUNDLE.
NOTES,D.G.
NURED/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE DNL AIR SAMPLER.
NUREO/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIGIODINE FROM MILK.
10VL, D. A.
NURE3/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
MULLINS.C.D.
NURE3/CR-3502: HIGH DRYOUT GUALITY FILM DOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD DUNDLE.
MUNSON,L.F.
NURED/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory,The Code And Examples.
1URPHY,G.A.
NURED/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY A3ING TREND. Progress Report September 1983.
1USCARA J.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics.
NUREO/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
MADEL M. V.
NURE0/CR-3601 : MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
MANSTAD,R.K.
NURE3/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
MELSON,R.W.
NUREG/CH-3560: EVALUATION METHODS FOR THE CONSEQUENCES OF DELOW WATER TAELE MINE DISPOSAL OF URANIUM MILL TAILINGS.
4ELSON.W.R.
NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREJ/CR-3631: RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
4EUMAN,0.P.
75
NUREG/CR-3G12: PREDICTION OF FAR-FZELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS. A Multidimensional Stochastic Theory With Application To Fractured Rocks.
NEUMANN,S.P.
NUREC/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNGAT2 - VARI ADLY SATURATED FLOW MODEL.(Including 4 Example Problems).
NEWMAN C.M.
'l NUREG/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS. A Multidimensional Stochastic Theory With Application To Fractured Rocks.
NG, K. K.
NUREQ/CR-3716: CONTEMPT 4/ MOD 4 A Multicomponent Containment System Analysis Program.
NICHOLS,F.A.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: OUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
NICHOLSON,T.J.
j NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Report For Comment.
NORWOOD,K.S.
NUREQ/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT-RELEASE TEST HI-2.
O'CONNELL,W.J.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
O'KELLEY,G.D.
NUREQ/CR-3490: THE ROLE OF CEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF GEOLOGIC DISPOSAL OF HICH-LEVEL RADIOACTIVE WASTE.
OLSON.J.
NUREQ/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
l Interviews With Personnel From Nine Plants.
OPITZ,B.E.
NUREQ/CR-3449: LABORATORY EVALUATION OF LIMESTONE AtlD LINE NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION.Progrest l
Report.
OSBORNE. M. F.
NUREG/CR-3171 : DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
OSTROWSKI N.
NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE. TECHNICAL CONSIDERATIONS. Draft Report For Comment.
OTT,W.R.
NUREG/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
t.
OZTUNALI,0.I.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
PADOWSMI.M.Z.
NUREG/CR-3525: NECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING ^
FOR BWR APPLICATIONS.
PAPAZOGLOU,I.A.
NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.-
NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREG/CR-3530: REVIEW OF THE DAVIS-BESSE JNIT NO. 1 AUXILI AR Y FEEDWATER.
i i
SYSTEM RELIABILITY ANALYSIS.
l NUREG/CR-3531: REVIEW OF SEABROOK UNITS 1 AND 2 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
76
y PARK J.E.
NUREC/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY DF SUBMERGED JETS USING ORSMAC.
PARK J.Y.
l NUREQ/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: QUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
PARKER,J.L.
NUREG/CR-3522 VO1: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI ALS. VOL 1: U Dx ide Plus Graph i te Powd er.
PARKHURST.M.A.
NUREQ/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task l
3-Health Physics, i PARKINSON T.F.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
PARKS.C.V.
NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE 4
l SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/D-V UPDATED CROSS SECTION LIDRARY.
PEERENBOOM.J.P.
NUREG/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-CDST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
PICARD,R.R.
j NUREC/CR-3448: URANIUM HOLDUP MODELING.
POLLACK.H.N.
NUREQ/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
~j PREMUZIC.E.T.
NUREQ/CR-2721: SCDPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE 1
CONTAINING CHELATING DECONTAMINATION CHEMICALS.
lPUGHC.E.
2 NUREQ/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FCR APRIL-JUNE 1983.
i I RAINEY,J.A.
NUREQ/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
I REECE.W.D.
)
NUREQ/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory,The Code And Examples.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task
)
3-Health Physics.
REESE.R.T.
NUREQ/CR-3412: CDNTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT l
J/sNUARY-MARCH 1903.
} REICH.M.
NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1993.
REISENWEAVER.D.
NUREQ/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING q
2 REACTION DURING DRY STDRAGE.
4
! RECT.J.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION i
LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
RIDEOUT.T.B.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
77
7.[7. :1.(
J.). J. [
,. I,N j [M c.' '.
.,! ', j..
Y. [ f
+$h';2.'.'f~7.'..U"..['~
I 3
l ROBERTS,F.P.
NUREG/CR-3584: COMMONLY USEL NUCLEAR MATERI AL MEASUREMENTS AND THEIR SOURCES OF ERROR.
ROBERTS,M.J.
NUREG/CR-3622: A PRODADILISTIC NODEL OF ANNULAR -DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN BY CYLINDRICAL GECMETRY IMPEDANCE PROBES.
RODERTSON,D.E.
NUREG/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
ROLEb,G.W.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
ROUNTREE,S.L.
NUREG/CR-3351: SECURITY 3FFICER TACTICAL TRAINING ISSUES INVOLVING ESS EQUIPMENT.
RUGH,C.E.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
RUSH,R.M.
NUREG/CR-305'/: ANAL / SIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
RUTHER,W.E.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
RYMAN,J.C.
NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SA52 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/D-V UPDATED CROSS SECTION LIDRARY.
SAHA P.
NUREC/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSD7ED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983.
SALOMON,S.N.
NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERIAL TRANSPORTATION.
Final Report.
SAMANTA.P.K.
NUREG/CR-2815: PROBADILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
SASTRE C.
NUREG/CR-2331 VO3 N2: SAFETY RESET 9CH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983.
SCHMITT.R.C.
NUREG'CR-2896 VOI: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT SILJLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User 's Manual.
NUREG/CR-2896 VO2: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Verification.
NUREG/CR-3435: A NEW IMPLICIT NUMERICAL SOLUTION SCHEME IN THE COMMIX-1A COMPUTER PROGRAM.
SCHREIDER,R.E.
NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
SELBY,D.L.
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTI AL NUCLEAR POWER PLANT MALFUNCTIONS.
SERKIZ,A.W.
NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER 78
,._..._...._-.......___.._._,_.....__--_m-------
.PLANTO.Tochnical Findingo Rolovant To USI A-1.
NUREG-0993 RO1: RECULATORY ANALYSIS FOR USI A -1,
" WATER HAMMER."
SE NE,R.J.
NUREG/CR-3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
NUREG/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LIME NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINCS SOLUTION. Progress Report.
SHA,W.T.
NUREG/CR-2896 VO1: COMMIX-1A: A THREE-DIMENSIONAL TRANSIEP'T SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User's Manum 1.
NUREG/CR-2896 VO2: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE CDPFUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Vorification.
NUREG/CR-3435: A NEW IMPLICIT NUERICAL SOLUTION SCHEPE IN THE COMMIX-1A COMPUTER PROGRAM.
SHACK,W.J.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISIDN LIGHT-WATER-REi,CTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
SHADE,J.W.
NUREG/CR-3104: AGUIFER RESTORATION TECHNIQUES FOR IN-SITU LEACH URANIUM MINES.
SHAH,V.L.
NUREG/CR-2896 VO1: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User's Manual.
NUREG/CR-2896 VO2: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Vorification.
NUREQ/CR-3435: A NEW IMPLICIT NUPERICAL SOLUTION SCHEME IN THE COMMIX-1A COMPUTER PROGRAM.
SHARP,R.D.
NUREQ/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
SHIEH,L.C.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
.CIEGEL,A.I.
NUREQ/CR-3275: JOB ANALYSIS OF TK ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONbEL RELI ABILITY MODEL.
DINAN-TOV,I.
NUREG/CR-3492 VO2: HIGH-TEMPERATURE CAS-COOLED REACTOR SAFETY STUDIES l
FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
DIMS, C. S.
NUREG/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
SKIBA,E.L.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
SMITH,B.W.
NUREG/CR-3504: COMMONLY USED NUCLEAR MATERI AL MEASUREPENTS AND THEIR COURCES OF ERROR.
l SMITH,C.M.
.l NUREG/CR-3439 VO1: A DESCRIPTION OF THE ' HARDWARE AND SOFTWARE OF THE i
POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS.ON-LINE I
REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
79
NUREC/CR-3439 VO2: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (P3DREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNI A DISTRIBUTION), VOLUME 2.
SMITH,H.A.
NUREG/CR-3522 VOI: REFERENCE MATERI ALS FCR NONDESlRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIALS,VOL 1: U Oxide Plus Graphite Powd er.
NUREC/CR-3522 VO2: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI AL. Volume 2: Thin Metal Foils Of Highly Enriched Uranium.
SMITH J.H.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM CENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
SMITH,P.R.
NUREG/CR-3242: THE LOS ALAMOS NATIONAL LADORATORY/NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
SNYDER,D.J.
NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
SODA K.
NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
SOLDRIG,R.M.
NUREG/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIOIODINE FROM MILK.
SOMMERS,F.
NUREC/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE DRGANIZ ATION AND
~
ADMINISTRATION OF NUCLEAR POWER PLANTS.
SOO, P.
NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
SPENCE,R.D.
NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EGUILIBRIUM ESTIMATE.
SPRINKLE J.K.
NUREG/CR-3522 VO1: REFERENCE MATERI ALS FGR NONDESTRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIALS.VOL 1: U Oxida Plus Graphite Powd er.
NUREG/CR-3522 VO2: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI AL. Volume 2: Thin Metal Foils Of High ly Enriched Uranium.
SRINIVASAN.M.G.
NUREG/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION.
STACK,D.W.
NUREG/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
STAHL,D.
NUREG/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
SULLIVAN,P.J.
NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
SWAJA R.E.
NUREC/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
SWARTZMAN,0.L.
NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
SWINTH,K.L.
80
NUREO/CR-3504: COMMONLY USED NUCLEAR MATERI AL MEASUREPENTS AND THEIR SOURCES OF ERROR.
CZAWLEWICZ,S.A.
NUREG/CP-OO4B VO1: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY INFORMATION MEETING.
i NUREO/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NURED/CP-OO48 VO3: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREO/CP-OO4B VO4: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREO/CP-OO48 VO5: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY l
RESEARCH INFORMATION MEETING.
NUREO/CP-OO48 VO6: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
TAKEUCHI,K.
NUREO/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
- TALEYARKHAN,R.
NUREG/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR BWR APPLICATIONS.
TANNER,J.E.
NURE9/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory,The Code And Examples.
TAYLOR M.
NUREO-0837 VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report, July-September 1983.
TEICHMANN,T.
NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
,TEPEL,R.C.
NUREO/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER i
PLANT.
THEOFANDUS.T.G.
NUREO/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
THOMPSON,S.L.
1 NUREO/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM CUARTENLY REPORT JULY-SEPTEMBER 1983.
. THOMPSON, T.
NUREO-0837 VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NEYWORK. Progress Report, July-September 1983.
THURCOOD,M.J.
NUREO/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
NUREO/CR-3642: A COBRA / TRAC, BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
,UKACH tK, J. W.
l NUREO/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE-BNL AIR SAMPLER.
VOJIAS,M.L.
NUREO/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly Progress Report For April-June 1983.
VOKAR,N.
l NUREO/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR.1982.
90STE.A.P.
NUREO/CR-3554: RADIONUCLIDE MIGRATION.IN GROUNDWATER. Annual Progress Roport For 1982.
BR AVIB, J. 't.
NUREO/ Cat-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
$WEETON,D.R.
81
[
NUR EG/CR-3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
VAN DYKE,J.W.
i NUREG/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
VAN RODYEN, D.
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Report. April-June 1983.
VANKUIKEN.J.C.
NUREG /CR-3553: AN EFFICIENT SIMUL /. TION APPROACH FOR EVALUATING THE POTENTIAL EFFECTS OF NUCLEAR POWER PLANT SHUTDOWNS ON ELECTRICAL GENERATING SYSTEMS.
j VESELY,W.
NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
VOGT, D.
NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
WART.R.J.
NUREG/CR-3636: DENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
WEDSTER.C.C.
NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SA52 AND ORIGEN-S MODULES OF SCALE WITil AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
WEDSTER.C.S.
NUR EG/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
WEEKS J.R.
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE l
OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1903.
WELLS.J.E.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THX SEISMIC RISK j
AT THE ZION NUCLEAR POWER PLANT.
WHITE,J.R.
NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR POWER PLANTS.
WHITE W.S.
NUREG/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
WICHNER,R.P.
NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
WILSON,C.W.
NUR EG/CR-3251: THE ROLE OF SECURITY DUPING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
WINGES,L.
NUREQ/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants, i
WINTER.C.L.
l NUREQ/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS A Multidimensional Stochastic Theory With Application To Fractured Rocks.
WITTENBROCK N.
NUREG/CR-1755: TECHNOLOGY,EAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
WOMELSDUFF,J.E.
l 82 L
l NUREG/CR-2012: THE RELATIVE IMPORTANCE OF TEMPERATURE,PH AND DORIC ACID l
CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL CORROSION.
WOO,H.H.
NUREG/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE j
RUPTURE LOCATION CRITERIA.
NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1993.
WULFF,W.
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Repor t, April-June 1983.
WYANT F.J.
NUREC/CR-3532: RESPONSE OF RUDDER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIONS.
YADCEE.F.L.
NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
YODER,0.L.
NUREG/CR-3502: HIGH DRYOUT GUALITY FILM DOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD DUNDLE.
YOUNG M.
NUREG/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRAN9IENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
YOUNGBLOOD,R.W.
NUREG/CR-2815: PROBADILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELI ADILITY ANALYSIS.
NUREG/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO.
1 AUXILIARY FEEDWATER SYSTEM RELIADILITY ANALYSIS.
NUREG/CP -3531 : REVIEW OF SEADROOK UNITS I AND 2 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
ZANOTELLI,W.A.
NUREC/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED HCDA.
/
83
Subject index This index was developed from keywords and word strings in titles and ab-stracts. During this development period, there will be some redundancy, which will be removed later when a reasonable thesaurus has been developed through experience. Suggestions for improvements are welcome.
ACRS NUREG-1039: REVIEW AND EVALUATION OF THE NUCLEAR REGULATORY COMMISSION SAFETY RESEARCH PROGRAM FOR FISCAL YEAR 1985.
ALARA NUREQ/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
Abnormal Occurrence NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report September 1983.
Accident Sequence Code NUREQ/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
Accident NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES CUIDE.
NUREG/CR-3067: CALIBRATION SOURCES FOR THE G-M. COUNTER USED WITH THE BNL AIR SAMPLER.
NUREQ/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGRAM GUARTERLY REPORT JULY-SEPTEMBER 1983.
NUREG/CR-3359 VO4: PHYSICS OF REACTOR SAFETY.Guarterly Repert,0ctober-December 1983.
NUREG/CR-3523: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR BWR APPLICATTONS, NUREQ/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEGUENCE /sNALYSIS.
NUREG/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPARATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
N*JREG/CR-3661 : PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
Advective Transport NUREG/CR-3560: EVALUATION METHODS FOR THE CONSEGUENCES OF BELOW WATER TABLE MINE DISPOSAL OF URANIUM MILL TAILINGS.
Aerosol NUREQ/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
NUREG/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly Progress Report For April-June 1983.
Afterheat 85
l NUREQ/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE BAS 2 AND ORICEN-S MODULES OF SCALE WITi.
.N ENDF/B-V UPDATED CROSS SECTION LIBRARY.
Age-Related Failure NUREQ/CR-3543: SURVEY OF DPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report SeptemDer 1983.
l Aging NUREC/CR-2932 VO2: EQUIPMENT GUALIFICATIDN RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO. 2,REPDRT NO.
2.
Air Filter NUREQ/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUCCING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
Air Sampler NUREQ/CR-3067: CALIBRATION SOURCES FOR THE Q-M COUNTER USED WITH THE BNL AIR SAMPLER.
Annual Report To Congress NUREQ-1039: REVIEW AND EVALUATION OF THE NUCLEAR REQULATORY COMMISSION SAFETY RESEARCH PROGRAM FOR FISCAL YEAR 1985.
Annular Flow Channel NUREQ/CR-3484: TRAN B-1: EXPERIMENTAL INVESTICATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
Annular-Dispersed Flow L-NUREQ/CR-3622: A PROBABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A
[ 4, REACTOR SUBCHANNEL AS SEEN BY CYLINDRICAL GEOMETRY IMPEDANCE PROBES.
Answers NUREO-0732 RO1: ANSWERS TO FREQUENTLY ASKED GUESTIONS ABOUT CLEANUP ACTIVITIES AT THREE MILE ISLAND, UNIT 2.
Artificial Intelligence NUR EC/CR-3461 : RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF i
ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
As-Built Structures NUREQ/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERINC STRUCTURES
-A REVIEW AND EVALUATIDN.
Audits NUREQ/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
Auxiliary Feedwcter System NUREQ/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO.
1 AUXILI ARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
Balance OF Plant Modeling NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REQULATORY RESEARCH. Quarterly Progress Report. April-June 1983.
Basalt NUREC/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
NUREQ/OR-3730. EVALUATION OF RADIONUCLIDE CE0 CHEMICAL INFORMATION DEVELOPED BY DDE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
Beta Dosimetry NUREQ/CP-OO50: PROCEEDINGS OF THE INTERNATIONAL BETA DOSIMETRY SYMPOSIUM. Held at Washington,DC February 15-18,1983.
Biological Effects NUREC/CP-OO50: PRDCEEDINGS OF THE INTERNATIONAL BETA DOSIMETRY SYMPOSIUM. Held at Washington DC February 15-18,1983.
Biota l
NUREC/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
86
i Bluogillo NUREG/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF DLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
Boiling Region NUREQ/CR-3502: HIGH DRYOUT GUALITY FILM DOILING AND STEAM COOLING HEAT l
TRANSFER DATA FROM A ROD DUNDLE.
Bolting Failure NUREQ/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983.
Budget NUREG-OO85 102: US NUCLEAR REGULATORY COMMISSION POLICY AND PLANNING QUIDANCE 1983.
CARA NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR POWER PLANTS.
COBRA / TRAC NUREG/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
NUREG/CR-3642: A COBRA / TRAC,BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
COMMIX-1A NUREG/CR-2896 VO1: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: Us er 's Manua l.
NUREQ/CR-3435: A NEW IMPLICIT NUMERICAL SOLUTION SCHEME IN THE COMMIX-1A COMPUTER PROGRAM.
CONTEMPT 4/ MOD 4 NUREQ/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
CYCLE 14 NUREQ/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGRAM CUARTERLY REPORT JULY-SEPTEMBER 1983.
Coblo NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIONS.
Calibration NUREG/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BNL AIR SAMPLER.
Capccitor Discharge Vaporization NUREG/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly Progress Report For April-June 1983.
i Cotogory I Structures NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REQULATORY RESEARCH. Quarterly Progress Repor t, April-June 1983.
l Coucos NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTS. Technical Findings Relevant To USI A-1.
Comant solidification NUREG/CR-3496: REVIEW DF A TEST PROGRAM FOR QUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
Chcnnel Head Decontamination NURE9/CR-35BO: STEAM QENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
Cholating Pecontamination Chemicals NUREG/CS2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WAGTE CONTAINING CHELATING DECONTAMINATION CHEMICALS.
C1cdding NUREG/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN~ SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
87
NUREQ/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
NUREG/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly i
Progress Report For April-JJne 1983.
i NUREQ/CR-3491: OCA-II,A CODE FOR CALCULATING THE DEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESEURE VESSEL SUBJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
Cleanup tPIREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT 'HREE MILE ISLAND UNIT 2.
NUREG-0732 RO1: ANSWERS TO FREGUENTLY ASKED QUESTIONS ABOUT CL PJ.ANUP ACTIVITIES AT THREE MILE ISLAND, UNIT 2.
NUREQ/CR-3496: REVIEW OF A TEST PROGRAM FOR QUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
Code NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORICEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM GUARTERLY REPORY JULY-SEPTEMBER 1983.
NUREG/CR-3390: DOCUMENTATION AND USER'S GUIDE:UNSAT2 - VARIADLY SATURATED FLOW MODEL.(Including 4 Example Problems).
Cembustion NUREG/CR-3242: THE'LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
Comparison Studies NUREG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
Compensatory Safeguards NUREG-104 5: GUIDANCE ON THE APPLICATION OF COMPENSATORY SAFEGUARDS MEASURES FOR POWER REACTOR LICENSEES.
Computer Aid NUREG/CR-3461: RESPONSE TREE EVALUATIO** - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREG/CR-3631: RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
Computer Code NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
NUREG/CR-3435: A PEW IMPLICIT NUPEERICAL SOLUTION SCHEPE IN THE COMMIX-1A COMPUTER PROGRAM.
NUREG/CR-3491: OCA-II A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D EURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPERATURE AND PRESSURE TRANSIENTS.
NUREQ/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
I NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
NUREQ/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
Ccaputer Generated displays NUREQ/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GEMERATED DISPLAYS.
Ccaputer Maps l
NUREQ/CR-3056: POPULATION DISTRIBUTION ' AreALYSIS FOR NUCLEAR POtJER ~ PLANT SITING.
Ccaputer Program i
NUREG/CR-2624 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING l
PROGRAM GUARTERLY PROGRESS REPGtT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-3642: A COBRA / TRAC, BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK
ACCIDENT IN A PWR EGUIPPED WITH UPPER HEAD INJECTION.
NUREQ/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System g
Analysis Program.
Computer NUREG/CR-2896 VO1: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT
?
SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF Z
SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User 's Manual.
5 NUREO/CR-2096 VO2: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT i
SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And M
Verification.
NUREC/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
NUREO/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
NUREQ/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
NUREQ/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE i
ASSESSMENT.
Containment Integrity i
NUREC/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
Containment Structure 4
NUR EQ/CN -3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUAR/-MARCH 1903.
Containment System NUREG/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1983.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
NURFG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
i "ontainment Vessel NUREQ/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
Containment I
NUREC/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERIA.
Contract Research i
NUREO-0975 VO2: COMPILATION OF CONTRACT RESEARCH FOR THE MATERIALS ENGINEERING DRANCH DIVISION OF ENGINEERING TECHNOLOGY. Annual Report For FY 1983.
Control Room NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER
=
PLANT CONTROL ROOM TASKS.
g NUREO/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREQ/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
i NUREO/CR-3631: RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
Coolant System NUREQ/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
Coolant NUREQ/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION f
EXPERIMENTS.
Cooling Region NUR EG/CR-3502: HIGH DRYOUT GUALITY FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD BUNDLE.
Cooling System NUREQ/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER 7
ENVIRONS.
Coppor r
89
NUREO/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF BLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
NUREC/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
(
Core Damage NUREQ/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
i NUREG/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR BWR APPLICATIONS.
Core Disruptive Accident NUREG/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
Core Melt 1
NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EGUILIBRIUM ESTIMATE.
NUREQ/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK l
AT THE ZION NUCLEAR POWER PLANT.
Core Modeling NUREG/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR BWR APPLICATIONS.
Core-Disruptive Accident NUREQ/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
Core NUREC/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
l Corrosion NUR EC/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL i
CORROSION.
NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period Apri!-September 1983.
NUREQ/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
Cost NUREG/CR-2210: TECHNOLOCY, SAFETY AND COSTS OF~ DECOMMISSIONING REFERENCE
)
INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
NUREC/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
NUREG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
NUREQ/CR-3667: A QUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
Countercurrent NUREG/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPARATION AND i
DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
Crcck NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY FROGRESS REPORT FOR JULY-SEPTEMBER 1983.
NUREQ/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE' LOCATION CRITERIA.
NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING-(SAFT-UT).
Criteria NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
Crud NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF 90
l LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
1 Cylindrical Geometry NUREG/CR-3622: - A PROBABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN BY CYLINDRICAL GEOMETRY IMPEDANCE PROBES.
)
_DECON i
NUREG/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
-D:cping NUREG/CR-3526: IMPACT -OF CHANGES IN DAMPING AND SPECTRUM PEAK BRDADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
NUREG/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION.
i Dato NUREG-OO2O VOB NO1: LICENSED OPERATING REACTORS STATUS
SUMMARY
j REPORT. Data As Of December 31,1983.(Greg Book)
NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
I Da Minimis Waste Disposal NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
Dscommissioning NUREG/CR-1755: TECHNOLOGY, SAFETY AND CDSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-223 0: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
NUREC/CR-3550: EVALUATION OF~ NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
l Annual Summary Report - Fiscal Year 1983.
NUREG/CR-3605: EVALUATION OF NUCLEAR FALJLITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
j Dacontamination NUREQ/CR-2721: SCDPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE CONTAINING CHELATING DECONTAMINATION CHEMICALS.
NUREQ/CR-3444 VO1: THE-IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATIDN, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
Dafects NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIQUE FOR ULTRASONIC TESTING (SAFT-UT),
Daforcation i
NUREG/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
, Dogradatior.
NUREQ/CR-2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE CONTAINING CHELATING DECONTAMINATION CHEMICALS.
Datoctors NUREG/CR-3522 Vol: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI ALS. VOL 1: U Oxide Plus Graphite Powd er.
Directory NUREG/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
'Diepocal NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draft Report For Comment.
NUREG/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON -
i SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXFDSURE. Annual Report.
NUREG/CR-3560: EVALUATION NETHODS FOR-THE CONSEGUENCES OF~BELOW WATER 91
TABLE MINE DISPOSAL OF URANIUM MILL TAILINGS.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
D200s NUREG/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
Dry Storage NUREQ/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
Drgcut Point NUREQ/CR-3502: HICH DRYOUT GUALITY FILM BOILING AND STEAM COOLING HEAT a
TRANSFER DATA FROM A ROD BUNDLE.
ENTOMB NUREG/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR i
REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
EPICOR-II Liners NUREQ/CR-3496: REVIEW OF A TEST PROGRAM FOR GUAL1'.YING THE i
SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
Earthquake NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As OF November 30,1983.(Greg Book)
NUREG/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report, October 1982 - September 1983.
Econgstems NUR EC/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
Eddy Current NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
Eddy-Current NUREQ/CR-2824 VO1: EDDY-CURRENT INSPECTION-FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDIf1G MARCH 31,1982.
NUREQ/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM OENERATOR TUBING PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
NUREQ/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Rep ort On Data Acquisition / Statistical Analgsis.
i EfPluent Water NUREC/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
Effluent NUREG/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE l
VICINITY OF SUBPERGED JETS USING ORSMAC.
NUREQ/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF BLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
i EIoctric Cables NUREG/CR-2932 VO2: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
- 2. REPORT NO.
2.
Electrical Utility Generating System NUREQ/CR-3553: AN EFFICIENT SIMULATION APPROACH FOR EVALUATING THE POTENTIAL EFFECTS OF NUCLEAR POWER PLANT SHUTDOWNS ON ELECTRICAL GEERATING SYSTEMS.
Electrician NUREG/CR-3275: JOB ANALYSIS OF - TE ELECTRICI AN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONEL RELI ABILITY MODEL.
Easrgency Feedwater System NUREG/CR-3529: REVIEW OF THE ARMANSAS NUCLEAR ONE GENERATING. STATION 92
UNIT NO.1 EMERCENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREQ/CR-3531: REVIEW OF SEABROOK UNITS 1 AND 2 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
Escrgency NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
Enforcement Actions NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As OF November 30,1983.(Greg Book)
Engagement Simulation. System NUREG/CR-3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS EQUIPMENT.
Engineering Expertise NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
- Ente =bment NUREG/CR-1755
- TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
Environment NUREQ/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
NUREG/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
Environmental Assessment NUREG-0647: SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT,THREE MILE ISLAND NUCLEAR STATION UNIT NO.
- 2. Docket No. 50-320.
(Metropolitan Edison Company Jersey Central Power And Light Company And i
i Pennsylvania Electric Company) lEnvircnmental Impact Appraisal NUREG-1049: ENVIRONMENTAL IMPACT APPRAISAL FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO.
SNM-42. Docket No. 70-27.
(Babcock &
Wilcox Company, Naval Nuclear Fuel Division).
lEronien 3
NUREG/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION l
OF URANIUM MILL TAILINGS.
) Error Rates l
NUREQ/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL RDOM TASKS.
'Excaination l
NUREQ/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1992.
j NURED/CR-3580: STEAM QENERATOR GROUP PROJECT. Semiannual Progress l
Roport, July-December 1982.
IExcitotion NURED/CR-3649: DYNAMIC TESTING DF AS-BUILT CIVIL ENGINEERING STRUCTURES i
-A REVIEW AND EVALUATIDN.
!Expcoure Reduction l'
NUREG/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR PDWER PLANTS.
iExtroco Cold j
NURED-0800 07.1 RO3: STANDARD REVIEW PLAN FOR THE REVIEW DF SAFETY j
ANALYSIS. REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To Section 7.1, Revision 1 To Appendix A.
NUREG-OOOO 07.5 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY
{
ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. 3 i
To Section 7.5.
NUREO-OBOO 07. 7 RO3: STANDARD REVIEW PLAN FOR THE REVIEW DF SAFETY
}
ANALYSIS REPORTS FOR. NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. - 3 l
To Section 7.7.
'FALT
- NURE9/CR-3422 VO2: AEROSOL RELEAEE AND : TRANSPORT PROGRAM. Guarterly 93
Progroos Roport For April-June 1983.
FLOWER NUREQ/CR-3172: FLOWER; A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
FORTRAN IV NUREQ/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
FY 1985 Budget Estimates NUREG-1040: FY 1985 BUDGET ESTIMATES.
Foilure Data NUREQ/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELI ABILITY ANALYSIS.
Failure NUREQ/CR-3547: A SETS USER 'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
For-Field Assay NUREQ/CR-3522 VOI: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIALS.VOL 1: U Oxide Plus Graphite Powd er.
For-Field Dispersion NUREQ/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS. A Multidimensional Stochastic Theory With Application To Fractured Rocks.
Fest-Transient NUREC/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW. TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
Fatigue Loadings NUREQ/CR-3483: A STUDY OF THE REQULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERIA.
Forrite NUREQ /CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
Filter Plugging NUREQ/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUQQING TEST FACILITY DESCRIPTION AND PRELIMINARY l
TEST RESULTS.
Final Environmental Statement NUREG-0775: DRAFT ENVIRONMENTAL STATEMENT RELATED TO THE OPERATION OF COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2. Docket Nos. 50-445 and 50-446.(Texas Utilities Generating Company) l Fire Accident NUREQ/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
Fishery NUREQ/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
Fission Products NUREQ/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
NUREQ/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
Flaws NUREQ/CR-DB24 VO1: EDDY-CURRENT INSPECTION FOR STEAM QENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31.1982.
NUREQ/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY l
PROGRESS REPORT FOR APRIL-JUNE 1983.
NUREQ/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY j
94
PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
Frccturo Flcw NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT CHALLOW LAND DURIAL SITES: 1982 Annual Report of Research Investigations On The Distribution, Migration And Containment Of R.1dionuclides At Maxey Flats, Kentucky.
Frccture-Mechanics NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
Froo-Surface Flow NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
Frooring NUREQ/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
Frochwater Ecosystems NUREG/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
Fuol Aerosol Simulant Test NUREG/CR-3422 VO2: AERC3OL RELEASE AND TRANSPORT PROGRAM.Guarterly Pregt-ess Report For April-June 1983.
Fool crust NURZG/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
Fuol Design Changes NURIIG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
Fuol Fabrication NUREG-0430 UO4 NO1: LICENSED FUEL FACILITY STATUS REPORT. Inventory i
Difference Data. January 1983 - June 1983.(Greg Book)
Fuol Performance NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
Fuol Removal NUREG/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
Fuol NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS CECTION LIBRARY.
NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
0-M Datector NUREG/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BPA. AIR SAMPLER.
Galvanized Steel NUREQ/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE,PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM CALVANIZED STEEL CORROSION.
Ocama Radiation Fields NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics, i
Ccome-Ray-Based Nondestructive Assay NUREG/CR-3522 VO2: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF CPECI AL NUCLEAR MATERIAL. Volume 2: Thin Metal Foils Of Highly Enriched Uranium.
San Pressures NUREG/CR-3071: IRRADIATION HIST (=Y-AND INTERIM POSTIRRADIATION DATA FOR-IFA-432.
GaO-Ccoled Resctor 95 r
w w-
+e
---v-,-
e ie
NURE3/CM-3492 VO3: HIGH-TEMPER ATURE CAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, JULY - SEPTEMBER,1983.
Generic Issue 45 NUREG-0800 07.1 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. 3 To Section 7.1, Revision 1 To Appendix A.
NUREG-0800 07.5 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. 3 To Section 7.5.
NUREG-0800 07. 7 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To Section 7.7.
Geochemical Factors NUREG/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REQULATION OF GEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
Geochemical Models NUREG/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
Oeochemical NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
Geologic Disposal NUREG/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF GEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
Geologic Repositories NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draft Report For Comment.
Geomechanical Stress NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
Goals NUREG-0885 102: US NUCLEAR REGULATORY COMMISSION POLICY AND PLANNING GUIDANCE 1983.
Ormphite-Resistance Furnace NUREC/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
Groundwater NUR EC/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
j NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
l Guidance NUREG-OB85 IO2: US NUCLEAR REGULATORY COMMISSION POLICY AND PLANNING QUIDANCE 1983.
NUREG-1022 SO1: LICENSEE EVENT REPORT SYSTEM. Descrip tion Of System And Guidelines For Reporting.
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF FUTENTIAL NUCLEAR POWER PLANT MALFUNCTIONS.
NUEZG/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
Ouide NUREG/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNSAT2 - VARI ABLY SATURATED FLOW MODEL.(Including 4 Example Problems).
NUREG/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
Cuidelines NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF l
SELECTED ORGANIZATIONS.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
NUREG/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND 96
ADMINISTRATION OF NUCLEAR POWER PLANTS.
!HCDA NUNEO/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE L
PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED l
HCDA.
HSDT NURES/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
Haldon Fuel Assembly i
NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR j
IFA-432.
- Heep Leach NUREO/CR-2869 Rol
- DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
Hsot'Rajection NUREG/CR-2335: RESULTS DF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
!Hsot Transfer I
NUREO/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM CUARTERLY REPORT JULY-SEPTEMBER 1983.
iHmotod-Shroud NUREO/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN i
REPLICATE LOCA SIMULATIDN TESTS.
.Hsovy-Section Steel Technology NUREO/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGAESS REPORT FOR APRIL-JUNE 1983.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
!High Tcaperature NUREQ/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FRDM A SIMULATED i
HCDA.
High-Burnup Fuel NUREO/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1987
- High-Lovel Nuclear Waste Repository NUREO/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DDE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
iHigh-Lovel Radioactive Weste NURE2-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WAPTES IN THE UNSATURATED ZONE: TECHNICAL CDNSIDERATIONS. Draft Report For Comment.
i NURE9/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF GEOLOGIC DISPOSAL DF HIGH-LEVEL RADIOACTIVE WASTE.
lHigh-Lovel Waste-NURED/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
High-Tcaparature Gas-Cooled Reactor NURED/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION DF ACCIDENT EVALUATION-GUARTERLY PROGRESS REPDRT, APRIL 1-JUNE 30,1983.
.High-Tcaperature NURED/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST l
HI-2.
NUREO/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATIDN QUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1993.
NUREC/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTDR ' SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATIDN GUARTERLY PROGRESS' REPORT, i
JULY - SEPTEMBER,1983.
iHuman Engineering 9'7
NUREO/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
Human Error Probabilities NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
Human Error NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Report, April-June 1983.
3 l
NUREG/CR-2015: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
NUREG /CR-3621: SAFETY SYSTEM STATUS NONITORING.
Human Factors j
NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Report, April-June 1983.
Human Reliability NUREG/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE NUCLEAR POWER FLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
NUREQ/CR-3309: A SIMULATDR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
Hydraulic Conductivity NUREG/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCL7 DE DISPERSION CDEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUMEMENTS.A Multidimensional Stochestic Theory With Application To Fractured Rocks.
Hydrodynamac Load NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity B-10.
Hydrogen Generation NUREC/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE.PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL CDRRDSIDN.
l ICSCC NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSIDN CRACKED. INCONEL STEAM GENER ATDR TUBES.
NUREG/CR-3562: STEAM QENERATOR TUBE INTEGRITY PROGRAM LEAK R ATE TESTS-PROGRESS REPORT.
Icpacts NUREC/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
In-Situ NUREG/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECDVERY FACILITIES.
Independent Spent Fuel Storage NOREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMICSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
Infiltration NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLDW LAND BURI AL SITES: 1982 Annual Report of Researc h Investigations On The Distribution, Migration And Containment Of Radionuclides At Maxey Flats. Kentucky.
Inservice Inspection NUREC/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Rep ort On Data Acquisition / Statistical Aralysis.
Inspection NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERI AL TRANSPORTATION.
l Final Report.
l NUREG/CR-2824 VOi: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPGtT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-3200 VO3: EDDY-CURRENT-INSPECTION FOR STEAM GENERATOR TUBING 98
V PROGRAM OUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST DN LABORATORY PRODUCED INTERGRANULAR STRESS CORROSIDN CRACKED INCONEL STEAM GENERATOR TUBES.
i NUREQ/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR PDWER PLANTS.
Instrument Drift NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY A9ING TREND. Progress Report September 1983.
Instrumentation NUREG/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
Insulation Debris NUREG/CR-3616: TRANSPORT AND SCREEN BLDCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
Insulction NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIONS.
Intorgranular Stress Corrosion NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST DN LABDRATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENERATOR TUBES.
Invontory NUREG-0430 VO4 NO1: LICENSED FUEL FACILITY STATUS REPORT. Inventory Difference Data. January 1983 - June 1983.(Greg Book)
Ion-Exchange NUREQ/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
Ions NUREG/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A S?.MULATED HCDA.
NUREG/CR-3607: RADIONUCLIDE DISTRI3UTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL SITES:1982 Annual Report of Research Investigations On The Distribution, Migration And Containment Of Radionuclides At Maxey Flats Kentucky.
Irrodiation NUREG/CR-3070: MEASVRED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FDR IFA-527.
Jsb Analysis t
NUREC/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
Kogword Index NUR EC/CR-3645: A QUIDE TO LITERATURE RELEVANT TO THE ORGANIZATION AND
~ ADMINISTRATION OF NUCLEAR POWER PLANTS.
LCS NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION QUARTERLY PROGRESS REPORT, JULY - SEPTEMBER 1983.
LER NUREG-1022 S01: LICENSEE EVENT REPORT SYSTEM. Description Of System And l
Ouidelines For Reporting.
NUREC/CR-2OOO VO3 N2: LICENSEE EVENT REPDRT (LER) COMPILATION.For Month i
l OF February 1984.
I NUREC/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY A9INC TREND. Progress Report September 1983.
LEU NUREQ/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHPENT URANIUM FUEL.
LMFBR Safety Research l
99
l NUREG/CR-2679 VO3: ADVANCED REACTOR SAFETY RESEARCH GUARTERLY l
REPORT, JULY-SEPTEMBER 1982.
l LMFBR NUREG/CR-3359 VO4: PHYSICS OF REACTOR SAFETY.Guarterly Report,0ctober-December 1983.
l LOCA NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD I
DEFINITION. Generic Technical Activity B-10.
NUREG/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
LOCA/MSLB NUREG/CR-2932 VO2: EGUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
i LOFT NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGRAM GUARTERLY REPORT JULY-SEPTEMBER 1983.
Large-Break Accident NUREG/CR-3642: A COBRA / TRAC BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
Leach NUREG/CR-3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
l Leachates NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURI AL SITES: 1982 Annual Report of Researc h Investigations On The Distribution, Migration And Containment Of Radionuclides At Maxey Flats Kentucky.
l Leaching NUREG/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
Leak Rate Testing NUREC/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERIA.
Leak Rate l
NUREC/CR-3562: STEAM GENERATOR TUBE INTEGRITY PROGRAM LEAK R ATE TESTS-PROGRESS REPORT.
Leakage I
NUREG/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERIA.
l License Renewal NUREG-1007 S01: SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL AND POWER INCREASE FOR THE NATIONAL BUREAU OF STANDARDS REACTOR. Docket No.
50-184.
Licensed Operating Reactor NUREG-OO2O VO7 N11: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of October 31,1983.(Grey Book)
Licensee Event Report NUREG-1022 S01: LICENSEE EVENT REPORT SYSTEM. Description Of System And Guidelines For Reporting.
NUREC/CR-2OOO VO3 N1: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of January 1984.
NUREG/CR-2OOO VO3 N2: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of February 1984.
I NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY l
AGING TREND. Progress Report September 1983.
Licensing Actions NUREG-0748 VO3 N11: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of November 30,1983.(Orange Book) 100
2 NUREG-0748 VO4 NO1: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. DSta As OP January 31,1984.(Orcngo Book) l Licensing Delay NUREO/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER P L At'T.
Licensing Reviews NUREO-0500 V12 N12: REGULATORY LICENSING STATUS
SUMMARY
REPORT. Data As OF December 31,1983.(Blue Book)
Licostene/ Lime Treatment Of Acidic Tailings NUREO/CR-3449: LADORATORY EVALUATION OF LIMESTONE AND LIME NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Roport.
lLinsor Models NUR EG/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION.
'Linar Cooling System NUREO/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, JULY - SEPTEMBER,1983.
Litoroture NUR E0/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS.
JLivor Metalloproteins NURE0/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF I
BLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
!Locding 1
NUREG/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
Long-Torm Low Temperature Whole Rod Test NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF l
LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
Loss OF Flow NUREG/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
Loos Of Heat Sink NUR EC/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENEROETICS.
Lons OF Main Feedwater NUREC/CR-3529: REVIEW OF THE ARMANSAS NUCLEAR ONE GENERATING STATION 4
UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREC/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO. 1 AUXILIARY FEEDUATER SYSTEM RELIABILITY ANALYSIS.
' Lose Of Offsite Electric Power NUREC/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
Loss 07 Offsite Power NURED/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO.
1 AUXILI ARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
l Loon-OP-Coolant Accident NUREO/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
NUREG/CR-2812: THE RELATIVE IMPORTANCE OF TEMPERATURE,PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM QALVANIZED STEEL CORROSION.
NUREO/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
NURED/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF l
REFLECTIVE METALLIC INSULATION MATERIALS.
l NURED/CR-3642: A COBRA / TRAC, BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK i
' ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
l NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
101
V Leu Enriched Urcniua NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
Lcw-Level Radioactive Burial Sites NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERIAL TRANSPORTATION.
Final Report.
Lcw-Level Waste Disposal NUREC/CR-2721 : SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE CDNTAINING CHELATING DECONTAMINATION CHEMICALS.
Lcw-Resolution Detector NUREC/CR-3522 VO2: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIAL. Volume 2: Thin Metal Foils Of Highly Enriched Uranium.
MAC NUREC/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
MOD 1 NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM GUARTERLY REPORT JULY-SEPTEMBER 1983.
Maintenance NUREG/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
Malfunction NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTIAL NUCLEAR POWER PLANT MALFUNCTIONS.
Management Audit NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
Mark III NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity B-10.
Material Gualification NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
M3asurement Bias NUREG/CR-3584: COMMONLY USED NUCLEAR MATERIAL MEASUREPENTS AND THEIR SOURCES OF ERROR.
M3asurement Systems NUREC/CR-35S4: COMMONLY USED NUCLEAR MATERIAL MEASUREMENTS AND THEIR SOURCES OF ERROR.
M3chanical Loading NUREC/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983.
M3chanical Piping NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE-OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report April-June 1983.
M31tdown NUREC/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELOCATIDN MODELING FOR BWR APPLICATIONS.
M3thodology NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
Migration NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
Milk NUREG/CR-3512: RAPID FIELD METHOD FOR THE CDNCENTRATION OF R ADIDIODINE FROM MILK.
10:2
Minorclized Roll-Front Doposits NUREC/CR -3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
Manitoring NUREG-0837 VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report, July-September 1983.
NUREC/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BNL AIR SAMPLER.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
Mancenergetic Electrons NUREC/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONDENERGETIC ELECTRON IRRADIATIONS.
Natural Circulation NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM GUARTERLY REPORT JULY-SEPTEMBER 1983.
Natural Convection NUREC/CR-3359 VO4: PHYSICS OF REACTOR SAFETY. Guarterly Report,0ctober-December 1983.
N2ptunium NUREC/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
N2utralization Of Acidic Uranium Mill Solutions NUREG/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LINE NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report.
Non-Condensible Gas NUR EG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
N2ndostructive Assay NUREG/CR-3522 Vol: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIALS.VOL 1:U Oxide Plus Graphite Powder.
Nondestructive Testing NUREC/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
Nuclear Power Plant Sites NUREG/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT SITING.
Nuclear Waste Repositories NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
Nuclides NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND NINERALS.
OCA-II NUR EG/CR-3491: OCA-II. A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
ORICEN-2 NUREC/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTIDN LIBRARY.
ORSMAC NUREC/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
Occupational Radiation Exposure NUREG-0698 RO2: NRC PLAN FCR CLEANUP OPERATIONS AT THREE MILE ISLAND 103
UNIT 2.
Occupational Radiological Monitoring NUREG/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
Offsite NUREQ/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
Onsite Data Gathering NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
Dnsite NUREC/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
Operating Experience NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
Operating Reactors NUREG-0748 VO3 N11: OPEPATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As OF November 30,198*o.(Orange Book)
NUREG-0748 VO4 NO1: OPERATING KEACTORS LICENSING ACTIONS
SUMMARY
. Data As Of January 31,1984.(Orange Book)
Operating Units NUREG-OO2O VO7 N11: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As OF October 31,1983.(Grey Book)
Operators NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREG/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED j
DISPLAYS.
Organization And Administration NUREQ/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS.
Organization Chart NUREG-0325 RO3: US NUCLEAR REGULATORY COMMISSION FUNCTIONAL ORGANIZATION CHARTS.
Organizational Assessment NUR EQ/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED DRGANIZATIONS.
Outage NUREQ/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-CDST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
PEIS NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
PERCS NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory,The Code And Examples.
PRA NUREG-1050 DRFT: PROBABILISTIC RISM ASSESSMENT (PRA): STATUS REPORT AND GUIDANCE FOR REGULATORY APPLICATION. Draft Report For Comment.
PSDREC NUREG/CR-3439 VO1: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
NUREG/CR-3439 VO2: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 2.
Personnel Exposure NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
Petition 104
-n- - -
NUREG-0936 VO2 NO4: NRC REGULATORY AGENDA.Guarterly Report,0ctober-December 1983.
Phase Separation NUREG/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPAR ATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
Piping System NUR EG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL 1NTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREG/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERI A.
NUREC/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK DROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
Piping NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As OF November 30,1983.(Grey Book)
Plugged Tubes NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
Point Kernel NUREC/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory The Code And Examples.
Polyolefin Extruded Insulation NUREC/CR-2932 VO2: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
Population NUREC/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT SITING.
NUREG/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
Postirradiation NUREC/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432.
Postulated Pipe Rupture NUREG/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERIA.
Power Increase NUREG-1007: SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL AND POWER INCREASE FOR THE NATIONAL BUREAU OF STANDARDS REACTOR. Docket No. 50-184.
Power Plant Mortality NUREC/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
Pauor Spectral Density Recognition NUREG/CR-3439 Vol: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
NUREG/CR-3439 VO2: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 2.
Power NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE.
SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTIDN LIBRARY.
Proirradiation NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION OBSERVATIONS FOR IFA-527.
105 m
NUREC/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432.
Pressure Drop NUREC/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
Pressure Vessel NUREG/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1983.
NUREC/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
NUR EC/CR-3491: OCA-II,A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESCEL SUBJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
NUREC/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK DROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
Pressure-Suppression Containment NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity D-10.
Pretransport Generator NUREC/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual 'rogress Report, July-December 1982.
Probabilistic Risk Assessment NUREG-1050 DRFT: PROBABILISTIC RISK ASSESSMENT (PRA): STATUS REPORT AND GUIDANCE FOR REGULATORY APPLICATION. Draft Report For Comment.
NUREG/CR-3547: A SETS USER 'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
Probabilistic Safety Assessment NUREC/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
Procedure Guides NUREC/CR-2815: PROBASILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
Procedures NUREC/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
NUR EG/CR-3601 : MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
NUREG/CR-3619: SURVEY OF COMMERCIAL NON-NUCLEAR SECURITY PROGRAMS.
NUR EC/CR-3621: SAFETY SYSTEM STATUS MONITORING.
Proceedings NUREC/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
Production Weld NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
Profile NUREC/CR-2869 RO1: DIRECTORY AND PROFILE UF LICENSED URANIUM-RECOVERY FACILITIES.
Program NUREC/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
Programmatic Environmental Impact Statement NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
Protection Standards NUREG/CP-OO50: PROCEEDINGS OF THE INTERNATIONAL BETA DOSIMETRY SYMPOSIUM. Held at Washington,DC February 15-18,1983.
Cuestion-and-Answer Report NUREG-0732 RO1: ANSWERS TO FREGUENTLY ASKED GUESTIONS ABOUT CLEANUP ACTIVITIES AT THREE MILE ISLAND. UNIT 2.
RAMONA-38 NUREG/CR-2331 VO3 NP: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Repor t, April-June 1983.
106
RELAPS NUREG/CR-3329 VQ3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM GUARTERLY REPORT JULY-SEPTEMBER 1983.
Radiation Doses NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
Radiation Exposure NUR EG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
Radiation Field Reduction NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
Radiation NUREG/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-2932 VO2: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
NUREC/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
Radioactive Material NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERI AL TRANSPORTATION.
Final Report.
Radioactive Release NUREG/CR-7478: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ' ION NUCLEAR POWER PLANT.
t Radioactive Waste NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
Radiciodine NUREG/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIDIODINE FROM MILK.
Radiological Field Mapping NUREG/CR-3500: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report. July-December 1982.
NUREG/CR-3501: a:EAM GENERATOR GROUP PROJECT. Annual Report - 1982.
Radionuclide Dispersion Coefficients NUREG/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS. A Multidimensional Stochastic Theory With Application To Fractured Rocks.
Radionuclide Migration NUREG/CR-3554: RADIONUCLIDE MIGRATsud IN GROUNDWATER. Annual Progress Report For 1982.
Radionuclides NUREC/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Rep or t.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
NUREG/CR-3607: RADIONUCLIDE DISTR'BUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL SITES: 1982 Annual Report of Researc h Investigations On The Distribution Migration And Containment OF Radionuclides At Maxey Flats, Kentucky.
NUREQ/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
Raioiodine NUREG/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE BNL AIR SAMPLER.
10'7
Rocctivity Insortion NUREG /CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
Rocctor Core NUREC/CR-3359 VO4: PHYSICS OF REACTOR SAFETY. Guartarly Report,0ctober-December 1983.
Rocctor Safety NUREC/CP-OO48 VO1: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY INFORMATION MEETING.
NUREC/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VO3: PROCEEDINGS OF THE ELEVENTH WATER REACTDR SAFETY RESLARCH INFORMATION MEETING.
NUREC/CP-OO48 VO4: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VOS: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATICN MEETING.
NUREC/CP-OO48 VO6: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
NUREC/CR-3359 VO3: PHYSICS OF REACTOR SAFETY. Guarterly Report, July-September 1983.
Rocctor Shutdown NUREC/CR-3553: AN EFFICIENT SIMULATION APPROACH FOR EVALUATING THE POTENTIAL EFFECTS OF NUCLEAR PDWER PLANT SHUTDOWNS ON ELECTRICAL CENERATING SYSTEMS.
Reector Subchannel NUREC/CR-3622: A PROBABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN BY CYLINDRICAL GEOMETRY IMPEDANCE PROBES.
Rocctors Program Plan NUREC/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
Recirculation Line Safe-End Cracking NUREC/CR-3483: A STUDY DF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRI lRIA.
Rocovery NUREC/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Annual Summary Report - Fiscal Year 1983.
Regulatory Agenda NUREG-0936 VO2 NO4: NRC REGULATORY AGENDA.Guarterly Report,0ctober-December 1983.
Regulatory And Technical Reports NUREG-0304 VOB NO4: REQULATORY AND TECHNICAL REPDRT. Annual Compilation For 1983.
Rogulatory Guide NUREC/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPDNSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Quarterly Progress Report, April-June 1983.
NUREC/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK BROADENING ON THE SEISMIC RESPJNSE OF PIPING SYSTEMS.
Rogulatory Licensing NUREG-0500 V12 N12: REGULATORY LICENSING STATUS
SUMMARY
REPORT. Data As Of December 3.,1983.(Blue Book)
Releate Tests NUREG/CR-3171: DATA
SUMMARY
REPDRT FOR FISSION PRODUCT RELEASE TEST HI-2.
Release NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
NUREG/CR-3536: SIMULATION OF LGADING CONDITIONS FOR A TYPE A PACKAGE 10B
CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983.
<eliability Analysis NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
olichility NUREG/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
- onowal NUREG-1043: SAFETY EVALUATION REPORT RELATED TO THE RENEWAL OF THE OPERATING LICENSE FOR THE TR/.INING AND RESEARCH REACTOR AT THE UNIVERSITY OF MARYLAND. Docket No.
50-166.
toportable Occurrence NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report September 1983.
opository System NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
.ssoarch Reactor NUREG/CR 3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
_osearch NUREG-0975 VO2: COMPILATION OF CONTRACT RESEARCH FOR THE MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING TECHNOLOGY. Annual Report For FY 1983.
NUR EG/CR-3581 : STEAM GENEDATOR GROUP PROJECT. Annual Rep or t - 1982.
esin Solidification NUREG/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
esistance NUREC/CR-3127: PROBADILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
osponse Tree NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREG/CR-3631 : RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
isk Management NUREC/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
isks NUREG-OB85 102: US NUCLEAR REGULATORY COMMISSION POLICY AND PLANNING GUIDANCE 1983.
obotics NUREC/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR POWER PLANTS.
od Bundle NUREG/CR-3502: HIGH DRYOUT GUALITY FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD BUNDLE.
od Elongation NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432.
od Failure NUREC/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIAT ION ODSERVATIONS FOR IFA-527.
ulos NUREG-0936 VO2 NO4: NRC REGULATORY AGENDA.Guarterly Report. October-December 1983.
NUREG-1022 SO1: LICENSEE EVENT REPORT SYSTEM. Description Of System And Guidelines For Reporting.
A302 Grade B Material 109
~
~
l
l NUREC/CR-3614: CONSTANT EXTENSION RATE TESTING OF SA302 GRADE B MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
SAFSTOR NUREQ/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
j NUREC/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
NUREC/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
l Summary Report - Plum Brook Reactor Facility.
SAFT-UT NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING (SAFT-UT).
SAS2 NUREG/CR-2397: FUEL INVENTGRY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
SBLOCA NUREC/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
SCALE l
NUREC/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
SETS NUREC/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEQUENCE ANALYSIS.
SGCP NUREC/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis.
NUREG/CR-35BO: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
NUREC/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
SHMED NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERI AL TRANSPORTATION.
Final Report.
SIMPLEST-ANL NUREC/CR-3435: A EW IMPLICIT NUPERICAL SOLUTION SCHEPE IN THE COMMIX-1A COMPUTER PROGRAM.
SSEL NUREC-0525 ROB: SAFEGUARDS
SUMMARY
EVENT LIST (SSEL).
STA NUREC/CR-3396: EXPERIENCE WITH TW SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
Safe Storage NUREC/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOP STATIONS.
Sofaguards Summary Event List NUREG-0525 ROB: SAFEQUARDS
SUMMARY
EVENT LIST (SSEL).
Sofaguards NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED'BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH Guarterly Progress Report, April-June 1983.
i Safoty Evaluation Report NUREG-0519 SO1: SAFETY EVALUATION REPORT RELATED TO TE OPER ATION OF LASALLE COUNTY STATION UNITS 1 AND 2. Docket Nos. 50-373 and 374.
(Commonwealth Edison Company)
NUREG-0675 S17: SAFETY EVALUATION REPORT RELATED TO TE OPER ATION OF DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-275 And 50-323. (Pacific Gas And Electric Company)
NUREG-0675 S22: SAFETY EVALUATION REPORT RELATED TO TE OPERATION OF l
110
'DIABLO CANYON NUCLEAR POWER PLANT, Units 1 AND 2. Docket Nos. 50-275 And 50-323. '(Pacific Gas and Electric Company)
NUREG-0776 SO6: SAFETY EVALUATION REPORT RELATED TO THE OPER ATION OF SUSGUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2. Docket Nos. 50-387 L
And 50-388.(Pennsylvania Power And Light Companys A11egheng Electric Cooperative, Incorporated)
NUREG-OB47: SAFETY EVALUATIOf3 REPORT RELATED TO THE OPERATION OF THE WATTS HAR NUCLEAR PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And-50-391.(Tennessee Valley Authority)
~NUREG-OB87 SO4: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-440 And 50-441.(Cleveland Electric Illuminating Company)
NUREG-1007: SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL AND POWER INCREASE FOR THE NATIONAL BUREAU OF STANDARDS REACTOR. Docket No. 50-184.
NUREG-1043: SAFETY EVALUATION REPORT RELATED TO THE RENEWAL OF THE i
OPERATING LICENSE FOR THE TRAINING AND RESEARCH REACTOR AT THE UNIVERSITY OF MARYLAND. Docket No.
50-166.
Safety Evaluation NUREG-0647: SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT, THREE MILE ISLAND NUCLEAR STATION, UNIT NO.
- 2. Docket No.
50-320. (Metropolitan Edison Compang, Jersey Central Power And Light Company And Pennsgivania Electric Company)
Safety Goal Policy Statement NUREG-1050 DRFT: PROBABILISTIC RISK ASSESSMENT (PRA): STATUS REPORT AND l
GUIDANCE FOR REGULATORY APPLICATION. Draft Report For Comment.
Safety Goals NUREG/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
Safetg Research Program NUREG-1039: REVIEW AND EVALUATION OF THE NUCLEAR REGULATORY COMMISSION SAFETY RESEARCH PROGRAM FOR FISCAL YEAR 1985.
NUREC/CR-2331 VO3 N2: SAFETY RESEARCH PROGRANS SPONSORED BY THE OFFICE l
OF NUCLEAR PEGULATORY RESEARCH. Guarterly Progress Report, April-June 1983.
Safety Research
~
NUREC/CP-OO48 Vol: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY INFORMATION MEETING.
NUREC/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREC/CP-OO48 VO3: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VO4: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREC/CP-OO48 VO5: PHOCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY l
RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VO6: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY i
'RESEARCH INFORMATION MEETING.
NUREC/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF. ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT,-
APRIL 1-JUNE 30,1983.
Safoty Studies NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES
-FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT,-
l JULY -: SEPTEMBER,1983.
)
Safety System NUREG/CR-3428: APPLICATION'OF THE SSMRP METHODOLOGY.TO THE SEISMIC RISK 1
AT THE ZION NUCLEAR POWER PLANT.
NUREC/CR-3621: SAFETY SYSTEM STATUS MONITORING.
Sofoty-Related Emergencies
'111 l
1
NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
Safety NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
NUREG/CR-3581: STEAM QENERATOR GROUP PROJECT. Annual Report - 1982.
Salinity NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL i
FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
Screen Blockage i
NUREC/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
S2curity Officer NUREC/CR-3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS EQUIPMENT.
l Sscurity 1
NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES i
AT NUCLEAR POWER PLANTS.
{
NUREC/CR-3619: SURVEY OF COMMERCIAL NON-NUCLEAR SECURITY PROGRAMS.
i Soismic Resistance NUREG/CR-3127: PROBABILISTIC SEISMIC RESiS TANCE OF STEEL CONTAINMENTS.
Soismic NUREC/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK i
BROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
Soismograph Network 4
NUREG/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
Semi-Annual Summarg i
NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
Sociscale MOD-2A NUREG/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
Somiscale Mod-2A NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
I Sociscale NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGR AM GUARTERLY REPORT JULY-SEPTEMBER 1983.
Sat Equation Transformation System NUREG/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
ShcIlow Land Burial NUREG/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
Sholl NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics.
Shielding NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES 4
(PERCS). The Theory,The Code And Examples.
NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
Shutdown NUREC/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
Significant Enforcement Actions NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Greg Book) 112 1
Simulctor-Training l
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTIAL NUCLEAR POWER PLANT MALFUNCTIONS.
l Single-Rod l
NUREG/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
Sanko Detector NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983.
Sodium Uranantes NUREG/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED HCDA.
Solidification NUREG/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
Sorption NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
Source NUREC/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1983.
Spont Fuel Rods NUREG/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF LWR RO7S USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
Spont Fuel NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Greg Book)
NUREG-OO2O VOS NO1: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Greg Book)
NUREG/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
NUREG/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERIALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
Spant Ion Exchange Media NUREG/CR-3496: REVIEW OF.A TEST PROGRAM FOR GUALIFYING THE SDLIDIFICATION OF EPICOR II RESINS WITH CEMENT.
Spent Ion-Exchange Resins NUREC/CR-3444 Vol: THE IMPACT OF LWR DECONTAMINATIONS ON i
SOLIDIFICATION WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
l Stainless Steel Cladding NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
Stendcrd Review Plan NUREG-OGOO 07.1 RO3: STANDARD REVIEW PLAN FDR THE REVIEW OF SAFETY ANALYSIS REPDRTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. 3 l
To Section 7.1, Revision 1 To Appendix A.
l NUREG-0800 07. 5 RO3: STANDARD REVIEW PLAN FOR THE REVIEW DF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revi sion No. 3 To Section 7.5.
NUREG-OBOO 07. 7 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPDRTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No. 3 To Section 7.7.
113 r-w
Stonderd NUREG/CR-3500: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS, State Hazardous Materials Enforcement NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERIAL TRANSPORTATION.
Final Report.
Status Report NUREC-OO2O VO7 N12: LICENSED OPERATING REACTORS STAlJS
SUMMARY
REPORT. Data As Of November 30,1983.(Grey Book)
NUREG-OO2O VOB NO1: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Grey Book)
Status Summary NUREG-OO2O VOB NO2: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of January 31,1984.(Grey Book)
Status NUREC-0580 V12 N12: REGULATORY LICENSING STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Blue Book)
Steam Generator Group Project NUREC/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report - 1982.
Steam Generator Tubing NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED 3Y THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Guarterly Progress Report. April-June 1983.
NUREC/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
NUREC/CR-3562: STEAM GENERATOR TUDE INTEGRITY PROGRAM LEAK R ATE TESTS-PROGRESS REPORT.
NUREG/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis.
Steam Generator NUREG/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics.
NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report, July-December 1982.
NUREC /CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
Steel Containment NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
Stochastic Age NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
Stochastic Recruitment Model NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
Stochastic Theory NUREG/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS. A Multidimensional Stochastic Theory With Application To Fractured Rocks.
Stress Corrosion Cracking NUREC/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report, April-June 1983.
Stress Corrosion NUREG/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE 114
RUPTURE LOCATION CRITERI A.
Stripod Bass NUREG/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR
[
ASSESSMENT POWER PLANT IMPACT.
i Structural Analysis NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
Subourface Water NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURIAL SITES: 1982 Annual Report of Research Investigations On The Distribution, Migration And Containment Of Radionuclides At Ma x ey Fl ats, Kentuc k y.
Surp Screen NUREQ/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
Suppression Pool NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity B-10.
Surface Covers NUREQ/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION r,F URANIUM MIL' TAILINGS.
Surface Flaws NUREQ/CR-3491: OCA-II.A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPER ATURE AND PRESSURE TRANSIENTS.
Surveillance System NUREG/CR-3439 VO1: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
NUREQ/CR-3439 VO2: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER F?ECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTJR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 2.
Surveillance NUREG-10I5: STATE SURVEILLANCE OF RADIOACTIVE MATERI AL TRANSPORTATION.
Final Report.
NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
Synthetic Aperture Focusing NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIQUE FOR ULTRASONIC TESTING (SAFT-U T ).
Systsmatic Evaluation Program NUREG-0485 VO5 N11: SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Buff Book)
TLD NUREG-0837 VO3 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report, July-September 1983.
Tactical Improvement Package 2
.90 REG /CR-3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS 4
EGUIPMENT.
( Tactical Training NUREG/CR-3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS l.
EGUIPMENT.
. NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
Technical Findings NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTS. Technical Findings Relevant To USI A-1.
Tochnical Specifications NUREG-1042: TECHNICAL BPECIFICATIONS FOR SUSGUEHANNA STEAM ELECTRIC QTATION UNIT NO.2. Docket No. 50-388.(Pennsylvania Power And Light r
i
.115 i
I
~
Company)
Tamperature NUREG/CR-3071: IRRADIATION HISTORY AND INTERIM POSTIRRADIATION DATA FOR IFA-432.
NUREC/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERNS IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW. TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
Test Program NUREG/CR-3422 VO2: AEROSOL RELEASE AND TRAN3 PORT PROGRAM.Guarterly Progress Report For April-June 1983.
Test NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS.Semiaanual Report Covering The Period April-September 1983.
NUR EG/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
NUREG/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIDIODINE FROM MILK.
NUREG/CR-3549: EVALUATION OF CGTAINMENT LEAK R ATE TESTING CRITERI A.
NUR EG/CR-3614: CONSTANT EXTENSIL^4 RATE TESTING OF SA302 GRADE B MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
NUREG/CR73649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES
-A REVIEW AND EVALUATION.
Thermal Analysis NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
Thermal Conduction NUREG/CR-3636: DENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
Thermal-Hydraulic Reactor NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH.Guarterly Progress Report. April-June 1983..
Thermal-Hydraulic hUREG/CR-3642: A COBRA / TRAC.BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EGUIPPED WITH UPPER HEAD INJECTION.
NUREG/CR-3359 VO3: PHYSICS OF REACTOR SAFETY.Guarterly Report. July-September 1983.
NUREG/CR-3359 VO4: PHYSICS OF REACTOR SAFETY.Guarterly Report. October-December 1983.
NUR EG/CR-3502: HIGH DRYOUT GUALITY FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FRDM A ROD DUNDLE.
Thermal-Shock NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
Thermoluminescent Dosimeter NUREG-0837 VO2 NO3: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report. July-September 1983.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT Pr. OGRESS REPORT. Task 3-Health Physics.
Through-Wall NUREG/CR-3562: STEAM GENERATOR TUDE INTEGRITY PROGRAM LEAK R ATE TESTS.-PROGRESS REPORT.
Title List NUREG-0540 VO5 N11: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILADLE. November 1-30.1983.
NUREG-0540 VO5 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. December 1-31.1983.
Training _ Program NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE 116
TRAINING IMPORTANCE OF POTENTI AL NUCLEAR POWER PLANT MALFUNCTIONG.
Training Rocctor NUREC/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
Trcnsgranular Cracking NUREG/CR-3514: CONSTANT EXTENSION RATE TESTINO OF SA302 GRADE B NATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
Trensportation NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERI AL TRANSPORTATIDN.
Final Report.
Trcnsuranic Radionuclides NURF7/CR-3554: RADIONUCLIDE MIGRATION IN GROUNLWATER. Annual Progress R< port For 1982.
Trootment Of Uranium Mill Tailings NUREG/CR-3449: LADORATORY EVALUATION OF LIMESTONE AND LIME NF.UTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report.
Tube Defect NUREG/CR-3562: STEAM GENERATOR TUBE INTEGRITY PROGRAM LEAK RATE TESTS-PROGRESS REPORT.
Tubing NUREG/CR-2824 Vol: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUSING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
Two Phase Flow NUREC/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HONOGENEDUS AND STRATIFIED POROUS LAYERS.
Two-Phase Void Fractions NUREC/CR-3622: A PRODABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUDCHANNEL AS SEEN BY CYLINDRICAL GEOMETRY IMPEDANCE PRDBES.
Type A Package NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AIRPORT IN JANUARY 1933.
UNSAT2 NUREG/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNSAT2 - VARIABLY SATURATED FLOW MODEL.(Including 4 Example Problems).
USI A-1 NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTS. Technical Findings Relevant To USI A-1.
NUREG-0993 RO1: REQULATORY ANALYSIS FOR USI A-1,
" WATER HAMMER. "
Ultrasonic Testing NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING (SAFT-UT).
Unresolved Safety Issue A-1 Nt.' REC-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTO. Technical Findings Relevant To USI A-1.
NUREG-0993 RO1: REGULATORY ANALYSIS FOR USI A-1,
" WATER HAMMER. "
Unresolved Safety Issues NUREG-0540 VO5 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. December 1-31,1983.
Uppor Head Injection NUREG/CR-3642: A COBRA / TRAC.BEST-EST. MATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
Uranium Holdup Modeling NUREG/CR-3448: URANIUM HOLDUP MODELING.
Uranium Mill Tailings NUREG/CR-3449: LADORATORY EVALUATION OF LIMESTONE AND LINE NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report.
117 I
I-
NURED/CR-3560: EVALUATION METHODS FOR THE CONSEGUcNCES OF BELOW WATER TABLE MINE DISPDSAL OF UR ANIUM MILL TAILINGS.
NUREG/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION OF URANIUM MILL TAILINGS.
Uranium Mills NUREC/CR-3598: OCCUPATIDNAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
Uranium-Bearing Samples NUREC/CR-3522 VO1: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF i
SPECIAL NUCLEAR MATERIALS,VOL 1: U Oxide Plus Graphite Powd er.
Uranium NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF 1
URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/9-V UPDATED CROSS SECTION LIBRARY.
NUREG/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED HCDA.
NUREC/CR-3104: AGUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
Volence Effects NUREC/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
Value-Impact NUREG-0993 RO1: REGULATDRY ANALYSIS FOR USI A-1,
" WATER HAMMER. "
Vapor Pressure NUREC/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
Vaporization NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
d Variably-Saturated Flow Model NUREC/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNSAT2 - VARI ABLY 4
SATURATED FLOW MODEL.(Including 4 Example Problems).
Vogetation NUREC/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION OF URAN'UM MILL TAILINGS.
Vibra ti on NUREC/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
Visual Examination NUREC/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERI2ATION OF LWR RODS USED IN THE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
Void Fraction NUREC/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
Wmste Disposal NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZDNE: TECHNICAL CONSIDERATIONS. Draf t Report For Comment.
W30te Package NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION
)
TESTS. Semiannual Rep ort Covering The Period April-September 1983.
NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
Waste Repository NUREQ/CR-3490: THE ROLE OF QEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF QEDLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
i Water Bodies l
NUREC/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND 118
i l
COASTAL REDIONS.
W3 tor Hammer NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTS. Technical Findings Relevant To USI A-1.
NUREG-0993 RO1: REGULATORY ANALYSIS FOR USI A-1,
" WATER HAMMER. "
Wator Reactor Safety NUREG/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION I
LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
Water Reactor NUREC/CP-OO48 VO1: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY INFORMATION MEETING.
NUREG/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
I NUREG/CP-OO48 VO3: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY l
RESEARCH INFORMATION MEETING.
j NUREG/CP-OO48 VO4: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY l
RESEARCH INFORMATION MEETING.
NUREQ/CP-OO48 VO5: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY l
RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VO6: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
Wnter-Mobilized Nuclides NUR EC/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF CEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
Wald NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL j
PIPE WELDS.
- Wastinghouse MB-2 Model Boiler Test Facility NUR EG/CR-3661
- PROTOTYPICAL STEAM QENERATOR (MB-2) TRANSIENT TESTING i
i PROGRAM. Task Plan / Scaling Analysis Report.
! Wind-Stress Coupling NUREG/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW TEMPERATURE AND SALINITY CONDITIONS IN RIVERS. ESTUARIES AND COASTAL REGIONE.
Workbook
+
NUREC/CR-3645: A QUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS.
Workshop NUREC/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
Yollowcake NUREC/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
! Zircolog Cladding NUREC/CR-2810: VARIATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
l
\\
l l
l l
119
- - = _ _ -. _
NRC Originating Organization Index (Staff Reports)
This index lists those NRC organizations that have published staff reports. The index is arranged alphabetically by major NRC organizations (e.g., program offices) and then by subsections of these (e.g., divisions, branches) where ap-propriate. Each entry is followed by a NUREG number and title of the report (s).
If further information is needed, refer to the main citation by NUREG number.
ADVISORY COMMITTEE (S)
ACRS - ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUREG-1039: REVIEW AND EVALUATION OF THE NUCLEAR PEGULATORY COMMISSION SAFETY RESEARCH PROGRAM FOR FISCAL YEAR 1985.
OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
REGION 1, OFFICE OF DIRECTOR NUREG-OB37 VO3 NO3: NRC TLD DIRECT RADIATION NONITORING NETWORK. Progress Report. July-September 1983.
REGION 4, OFFICE OF DIRECTOR 5
NUREG-OO40 VO7 NO4: LICENSEE CONTRACTOR AND VENDOR INSPECTION STATUS REPORT. Ouarterly Report,0ctober 1983 - December 1983.(White Book) l EDO - OFFICE OF ADMINISTRATION DIVISION OF TECHNICAL INFORMATION 8: DCCUMENT CONTROL NUREG-0304 VOB NO4: REGULATORY AND TECHNICAL REPORT. Annual Compilation For 1983.
NUREG-0540 VO5 N11: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. November 1-30,1983.
NUREG-0540 VOS N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE.Pecember 1-31 1983.
NUREG-0750 Vis B01: NUCLEAR REGULATORY COMMISSICN ISSUANCES. July -
September 1982.Pages 1-1,210.
NUREG-0750 V16 B02: NUCLEAR REGULATORY COMMISSION ISSUANCES. October-December 1982.Pages 1,229-2,140.
j NUREG-0750 V1B 101: INDEXdS TO NUCLEAR REGULATORY COMMISSION ISSUANCES. July-September 1983.
NUREG-0750 V10 NO3: NUCLEAR REQULATORY COMMISSION ISSUANCES. September 1983. Pages 299-742.
4 NUREG-0750 V10 NO4: NLCLEAR REQULATORY COMMISSION ISSUANCES. October 1993.Pages 743-1,137.
NUREG-0750 V18 N05: NUCLEAR RE0'JLAT09Y COMMISSION IbSUANCES. November 1993.Pages 1,139-1,301.
121
DIVISION OF RULES AND RECORDS NUREG-0936 VO2 NO4: NRC REGULATORY AGENDA. Quarterly Report,0ctober-December 1983.
EDO - OFFICE OF STATE PROGRAMS OFFICE OF STATE PROGRAMS, DIRECTOR NUREG-1015: STATE SURVEILLANCE OF RADIOACTIVE MATERIAL TRANSPORTATION. Final Report.
EDO - OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA DIRECTOR'S OFFICE NUREG-1022 G01: LICENSEE EVENT REPORT SYSTEM. Description Of System And Guidelines For Reporting.
OFFICE OF INSPECTION & ENFORCEMENT (POST 12/11/80)
DIRECTOR'S OFFICE, OFFICE OF INSPECTION AND ENFORCEMENT NUREG-0430 VO4 NO1: LICENSED FUEL FACILITY STATUS REPORT. Inventory DiPFerence Data. January 1983 - June 1983.(Grey Book)
NUREG-0940 VO2 NO4: ENFORCEMENT ACTIONS: SIGNIFICANT ACTIONS RESOLVED. Quarterly Progress Report,0ctober-December 1983.
OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS DIVISION OF FUEL CYCLE & MATERIAL SAFETY NUREG-1049: ENVIRONMENTAL IMPACT APPRAISAL FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-42. Docket No. 70-27.
(Babcock &
Wilcox Company Naval Nuclear Fuel Division).
DIVISION OF SAFEGUARDS NUREG-0525 ROB: SAFEGUARDS
SUMMARY
EVENT LIST (SSEL).
NUREG-1045: GUIDANCE ON THE APPLICATION OF COMPENSATORY SAFEGUARDS MEASURES FOR POWER REACTOR LICENSEES.
U. S.
NUCLEAR REGULATORY COMMISSION COMMISSIONERS NUREG-0885 103: US NUCLEAR REGULATORY COMMISSION POLICY AND PLANNING GUIDANCE 1984.
NRC - NO DETAILED AFFILIATION GIVEN NUREC/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
NUREC/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOORAPHIC CRITERIA.
NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982'.
OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 4/05/81)
OFFICE OF NUCLEAR REGULATORY RESEARCH, DIRECTOR NUREG/CP-OO50: PROCEEDINGS OF THE INTERNATIONAL BETA DOSINETRY SYMPOSIUM. Held at Washington,DC February 15-18,1983.
DIVISION OF HEALTH, SITING & WASTE MANAGEMENT 122
l l
NUREO-1046 DRFT: DISPOSAL OF HICH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Repor t For Commen t.
DIVISION DF RISK ANALYSIS & DPERATIONS (POST 840429) l NUREG-1050 DRFT: PROBAEILISTIC RISK ASSESSMENT (PRA): STATUS REPORT AND QUIDANCE FOR REGULATORY APPLICATION. Draf t Report For Comment.
DIVISION OF ENGINEERING TECHNOLOGY NUREG-0975 VO2: COMPILATION OF CONTRACT RESEARCH FOR THE MATERI ALS ENGINEERING BRANCH DIVISION OF ENGINEERING TECHNOLOGY. Annual Report For FY 1983.
NUREQ/CP-OO49: PROCEEDINGS OF THE WORKSHOP DN SPENT FUEL / CLADDING REACTION DURING DRY STORAGE.
EDO-RESOURCE MANAGEMENT OFFICE OF RESOURCE MANAGEMENT, DIRECTOR NUREG-O.725 R06:
U. S.
NUCLEAR REGULATORY COMMISSION FUNCTIONAL ORGANIZATION CHARTS.
NUREG-0485 VOS N11: SYSTEMATIC EVALUATION PROGRAM, STATUS
SUMMARY
]
REPDRT. Data As Of November 30,1983.(Buff Book)
DIVISION OF BUDGET & ANALYSIS NUREG-1040: FY 1985 BUDGET ESTIMATES.
i DIVISION OF DATA AUTOMATION & MANAGEMENT INFORMATION NUREG-0748 VO3 N11: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data i
As Of November 30,1983.(Orange Book)
NUREG-0748 VO3 N12: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of December 31,1983.(Orange Dook)
NUREG-0748 VO4 NO1: OPERATING REACTORS LICENSING ACTIONS
SUMMARY
. Data As Of January 31,1984.(Orange Book)
MANAGEMENT INFORMATION BRANCH NUREG-OO2O VO7 N11: LICENSED OPERATING REACTORS STATUS
SUMMARY
6 REPORT. Data As Of October 31,1983.(Greg Book)
NUREG-OO2O VO7 N12: LICENSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of November 30,1983.(Greg Book)
NUREG-OO2O VOB NO1: LICcNSED OPERATING REACTORS STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Greg Book)
NUREG-OO2O VOB NO2: LICENSED OPENATING REACTORS STATUS
SUMMARY
REPORT. Data As Of January 31,1984.(Greg Book)
NUREG-0580 V12 N12: REGULATORY LICENSING STATUS
SUMMARY
REPORT. Data As Of December 31,1983.(Blue Book)
NUREG-0606 VO6 NO1: UNRESOLVED SAFETY ISSUES
SUMMARY
. Data As Of February 17,1984.(Agua Book) i DFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80)
DFFICE OF NUCLEAR REACTOR REQULATION, DIRECTOR NUREG-0647: SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT,THREE MILE ISLAND NUCLEAR STATION, UNIT NO.
- 2. Docket No. 50-320.
(Metropolitan Edison Company, Jersey Central Power And Light Company And Pennsylvania Electric Company)
NUREG-0775: FINAL ENVIRDNMENTAL 3TATEMENT RELATED TO THE OPERATION OF CDMANCHE PEAK STEAM ELECTRIC STATION, UNIT NOS. 1 AND 2.
Docket Nos.
50-445 And 50-446. (Texas Utilities Generating Company )
i NUREG-0800 07.1 RO3: STANDARD REVIEW PLAN FOR THE FEVIEW OF SAFETY ANALYSIS REPORTS FDR NUCLEAR POWER PLANTS. LWR Ed:, tion. Revision No.
1 23
'3 To Saction 7.1,Rovision 1 To Appandix A.
NUREO-0800 07. 5 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY 4
ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition.htevision No 3 To Section 7.5.
NUREG-OBOO 07. 7 RO3: STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS. LWR Edition. Revision No.
j 3 To Section 7.7.
TMI PROGRAM OFFICE NUREG-0698 RO2: NRC PLAN FOR CLEANUP OPERATIONS AT THREE MILE ISLAND UNIT 2.
NUREG-0732 RO1: ANSWERS TO FREQUENTLY ASKED GUESTIONS ABOUT CLEANUP 4
ACTIVITIES AT THREE MILE ISLAND, UNIT 2.
i DIVISION OF SYSTEMS INTEGRATION (PDST 011005) l NUREG-0978 FC: MARK III LOCA-RELATED HYDRODYNAMIC LOAD DEFINITION. Generic Technical Activity B-10.
DIVISIDN OF LICENSING 3
l NUREG-0519 SOS: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF LA SALLE COUNTY STATION, UNITS 1 AND 2. Docket Nos. 50-373 And 50-374.(Commonwealth Edison Company)
NUREG-0675 E17: SAFETY EVALUATIDN REPORT RELATED TO THE OPERATION OF DIABLO CANYDN NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-275 And 50-323.(Pacift Gas And Electric Company)
NUREG-0675 S22: SAFETY EVALUATIDN REPORT RELATED TO THE OPERATION OF DI ABLO CANYDN NUCLEAR POWER PLANT, Units 1 AND 2. Doc k et Nos. 50-275 And 50-323. (Pacific Gas and Electric Company)
}
NUREG-0776 SO6: BAFETY EVALUATION REPORT RELATED TO THE OPERATION OF SUSGUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2. Docket Nos. 50-397 And 50-388.(Pennsylvania Power And Light Companys Allegheny
}
Electric Cooperative, Incorporated)
NUREG-0847 S02: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391. (Tennessee Valley Authority)
NUREG-0887 SO4: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2. Docket Nos. 50-4 40 And i
50-441.(Cleveland Electric Illuminating Company)
NUREG-1007 Ell: SAFETY EVALUATION REPORT RELATED TO THE LICENSE 1
{
RENEWAL AND POWER INCREASE FOR THE NATIONAL BUREAU OF STANDARDS REACTOR. Docket No. 50-184.
{
NUREG-1042: TECHNICAL SPECIFICATIONS FOR SUSQUEHAtJNA STEAM ELECTRIC STATION, UNIT NO.2. Docket No. 50-388.(Pennsv1vania Power And Light Company) l NUREG-1043: SAFETY EVALUATION REPORT RELATED TO THE RENEWAL OF THE OPERATING LICENSE FOR THE TRAINING AND RESEARCH REACTOR AT THE UNIVERSITY DF MARYLAND. Docket No. 50-166.
l DIVISION OF SAFETY TECHNOLOGY l
NUREG-0927 RO1: EVALUATION OF WATER HAMMER OCCURRENCE IN NUCLEAR POWER PLANTS. Technical Findings Relevant To USI A-1.
NUREG-0993 RO1: REGULATORY ' ANALYSIS FOR USI A-1,
" WATER HAMMER."
I 124
NRC Contract Sponsor Index (Contractor Reports)
This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g.,
divisions) where appropriate. The sponsor organization is followed by the NUREG/CR number and title of the report (s) prepared by that organization. If further information is needed, refer to the main citation by the NUREG/CR number.
EDO - OFFICE OF STATE PROGRAMS OFFICE OF STATE PROGRAMS, DIRECTOR NURE0/CR-2869 ROI: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
EDO - OFFICE FOR ANALYSIS 8e EVALUATION OF OPERATIONAL DATA DIRECTOR'S OFFICE NUREO/CR-2OOO VO2N12: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of December 1993.
NUREC/CR-2OOO VO3 N1: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of January 1984.
NUREC/CR-2OOO VO3 N2: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of February 1984.
OFFICE OF NUCLEAR MATERIAL CAFETY & SAFEGUARDS DIVISION OF FUEL CYCLE 8e MATERIAL SAFETY b
NUREQ/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT METRO AlHPORT IN JANUARY 1983.
DIVISION OF SAFEGUARDS NUREQ/CR -3351: SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING l
ESS EQUIPMENT.
NUREQ/CR-3619: SURVEY OF CONMERCIAL NON-NUCLEAR SECURITY PROGRAMS.
DIVISION OF WASTE MANAGEMENT l
NUREC/CR-2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAQING WASTE I
CONTAINING CHELATING DECONTAMINATION CHEMICALC NUREQ/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
NUREC/CR-3390: DOCurtENTATION AND USER'S CUIDE: UNSAT2 - VAR I ABLY EATURATED FLOW MODEL.(Including 4 Example Problems),
i NUREC/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT, NUREQ/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS NETHODOLOGY.
125 l
i NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
NUREC/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
NURES/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION I
DEVE.* OPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 4/05/81)
OFFICE OF NUCLEAR REGULATORY RESEARCH, DIRECTOR NUREG/CR-2924 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENER ATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOk) ENDING MARCH 31,1982.
NUREC/CR-2970 VO4 MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAM: GUARTERLY PROGRESS l
REPORT OCTOBER-DECEMBER 1982.
NUREG/CR-3439 VO1: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
NUREC/CR-3553: AN EFFICIENT SIMULATION APPROACH FP EVALUATING THE POTENTIAL EFFECTS OF NUCLEAR POWER PLANT SHUTDOWNS ON ELECTRICAL j
GENERATING SYSTEMS.
4 ACCIDENT SOURCE TERM PROGRAM OFFICE i
NUREC/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
DIVISION OF ACCIDENT EVALUATION (PRE 840101)
NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
NUREC/CR-2810: VARI ATIONS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
JUREC/CR-2012: THE RELATIVE IMPORTANCE OF TEMPERATURE. PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL i
CORROSION.
NUREC/CR-2926: SIMS AND ESCA STUDIES OF POSSIBLE SODIUM UR ANATE i
PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED l
HCDA.
NUREQ/CR-3070: PEASURED IN-REACTOR DATA AND POSTIRRMDIATION OBSERVATIONS FOR IFA-527.
NUREG/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
NUREG/CR-3359 VO3: PHYSICS OF REACTOR SAFETY.GuarterIg Report, July-September 1983.
NUREQ/CR-3435: A NEW IMPLICIT NUMERICAL SOLUTION SCEME IN THE
^
j Corm!X-1 A COPPUTER PROGRAM.
NUREC/CR-3484: TRAN B-1: EXPERIPENTAL INYrSTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAN FLt.M CHANNEL.
NUREG/CR-3502: HIGH DRYOUT GUALITV FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD BUdDLE.
NUREG/CR-3525: PECHANISTIC CORE-WIDE MELTDOWN AND RELOCATION MODELING FOR BWR APPLICATIONS.
NUREG/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.'
NUREC/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPARATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
NUREG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POMOUS LAYERS.
DIVISION OF ACCIDENT EVALUATION NUREG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. GuarterIg Progress Report April-June 1993.
NUREC/CR-2679 VO3: ADVANCED REACTOR SAFETY RESEARCH GUARTERLY 126
l I
REPDRT, JULY-SEPTEMBER 1982.
NUREG/CR-2896 VO1: CDMMIX-1A: A THREE-DIMENSIONAL TRANSIENT l
SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS DF SINGLE AND MULTICDMPONENT SYSTEMS. Volume I: User 's. Manual.
NURED/CR-2896 VO2: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE CONFUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Vorification.
NURED/CR-3071: -IRRADI ATION HISTORY AND INTERIM POSTIRRADI ATIDN DATA FOR IFA-432.
NUREO/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EQUILIBRIUM ESTIMATE.
NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYSIS RESEARCH PROGRAM GUARTERLY REPORT JULY-SEPTEMDER 1983.
NUREG/CR-3359. VO4: PHYSICS OF REACTOR SAFETY.Guarterly Ropot t,0c tober-Dec ember 1983.
NURE0/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM. Guarterly Progress Report For April-June 1983.
NUREG/CR-3492 VO2: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FDR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30,1983.
- NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAF-COOLED REACTOR SAFETY SiUDIES FOR THE DIVISION OF ACCIDENT EVALUAT'uN GUARTERLY PROGRESS REPORT, JULY - SEPTEMBER,1983.
NUREQ/CR-3622: A PROBABILISTIC-MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN BY CYLINDRICAL GEOMETRY IMPEDANCE PROBES.
NUREQ/CR-3642: A COBRA / TRAC BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD' INJECTION.
NUREG/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS UF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
DIVISION OF FACILITY OPERATIONS NUREQ/CR-3067: CALIBRATION SOURCES FOR THE G-M COUNTER USED WITH THE.
BNL AIR SAMPLER.
NUREG/CR-3251: THE. ROLE OF SECURITY. DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
NUREG/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR-THE NUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
NURE0/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
NUREC/CR-3439 VO2: - A DESCRIPTION OF THE HARDWARE AND SOFTWARE DF THE I
POWER SP2CTRAL DENSITY RECOGNITION (PSDREC) CDNTINUOUS~ON-LINE l
REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 2.
. NU3EG/CR-3448: URANIUM HOLDUP MODELING.
! NUREG/CR-3461:. RESPONSE TREE EVALUATION NPLICATIONS FOR-THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREO/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF l
RADIDIODINE FROM MILK.
' NUREO/CR-3522 VO1: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI ALS, VOL 1: U Oxide Plus Graphite Powder.
! NURE0/CR-3522'VO2: REFERENCE MATERIALS FOR NONDESTRUCTIVE ASSAY OF l
SPECI AL NUCLEAR MATERIAL. Volume 2: Thin Metal ' Foils Of Highly Enriched Uranium.
NURE3/CR-3523: A RANKING SCHEME FOR MAKING DEC ISIONS ON THE RELATIVE '
(
TRAINING IMPORTANCE OF POTENTIAL NUCLEAR PORR PLANT MALFUNCTIONS.
i NUREC/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED l27 i
i DISPLAYS.
NUREQ/CR-3584: COMMONLY USED NUCLEAR MATERI AL hEASUREMENTS AND THEIR 4
j SOURCES OF ERROR.
NUREG/CR-3598: DCCUPATIONAL RADIOLOGICAL MONITOR ING AT URANIUM MILLS.
NUREC/CR-3631: RESPONSE TREES AND EXPERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
NUREC/CR-3717: EVALUATION OF ROBOTIC INSPECTION SYSTEMS AT NUCLEAR PDWER PLANTS.
DIVISIDN OF HEALTH, SITING & WASTE MANAGEMENT NUREG/CR-3056: PDPULATION DISTRIBUTIDN ANALYSIS FOR NUCLEAR POWER PLANT SITING.
NUREQ/CR-3057-. ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
NUREG/CR-3104: AQUIFER RESTORATION TECHNIGUES FOR IN-SITU LEACH URANIUM MINES.
NUREG/CR-3145 VO2: GEDPHYSICAL INVESTIGATION OF THE WESTERN DHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
NUREG/CR-3153: CALCULATION OF FLUID CIRCULATION PATTERF3 IN THE VICINITY OF SUBMERGED JETS USING ORSMAC.
NUREQ/CR-3172: FLOWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIDNAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
NUREC/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS j-AND MINERALS.
i NUREQ/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERI ALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
NUREG/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LINE NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report.
NUREC/CR-3477: CONCENTRATIONS OF COPPER-BINDING PROTEINS IN LIVERS OF BLUEGILLS EXPDSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
NUREC/CR-3478: REVIEW OF IMPACT OF CDPPER RELEASED INTO FRESHWATER ENVIRONS.
NUREC/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF OEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
NUREQ/CR-3501: THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
NUREQ/CR-3554: RADIONUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
NUREG/CR-3560: EVALUATION METHODS FOR THE CONSEGUENCES OF BELOW WATER TABLE MINE DISPOSAL OF URANIUM MILL TAILINGS.
NUREG/CR-3607: RADIDNUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT SHALLOW LAND BURI AL SITES: 1982 Annual Report of Research Investigations On The Distribution, Migration And Containment Of Radionuclides At Maxey Flats, Kentucky.
NUREQ/CR-3612: PREDICTION OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION CDEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS.A Multidimensional Stochastic Theorg With Application To Fractured Rocks.
NUREG/CR-3645: A QUIDE TO LITERATURE RELEVANT TO THE DRGANIZATIDN AND l
ADMINISTRATION OF NUCLEAR PO6ER PLANTS.
l NUREG/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION OF URANIUM MILL TAILINGS.
NUREC/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT POWER PLANT IMPACT.
DIVISION OF RISK ANALYSIS ts OPERATIONS (POST S40429)
NUREQ/CR-3242: THE LOS ALAMOS NATIONAL LABORATORY /NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND 128
PRELIMINARY TEST RESULTS.
NUREG/CR-3508: STANDARD SETTING STANDARDS:A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
NUREG/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEQUENCE ANALYSIS.
)IVISION OF ENGINEERING TECHNOLOGY NUREG/CR-1755: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS.
NUREG/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/B-V UPDATED CROSS SECTION LIBRARY.
NUREG/CR-2932 VO2: EGUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENER ATOR TUDING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
NUREQ/CR-3285: PRE-TEST VISUAL EXAMINATION AND CRUD CHARACTERIZATION OF LWR RODS USED IN THE LONG-TERM LOW-TEMPERATURE WHOLE ROD TEST.
NUREG/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1983.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1983.
NUREC/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
NUREG/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
NUREG/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERIA.
NUREG/CR-3491: DCA-II. A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPERATURE AND PRESSURE TRANSIENTS.
NUREG/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK DROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIONS.
NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report September 1983.
NUREG/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERIA.
NUREC/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS. Annual Summary Report - Fiscal Year 1983.
NUREG/CR-3561: EDDY CURRENT ROUND ROBIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENERATOR TUBES.
NUREG/CR-3562: STEAM GENERATOR TUBE INTEGRITY PROGRAM LEAK RATE TESTS-PROGRESS REPORT.
NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory,The code And Examples.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRT.SS REPORT. Task 3-Health Physics.
NUREG/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition /Statistica! Analysis.
NUREG/CR-3580: STEAM GENERATOR GROUP PROJECT. Semiannual Progress 129
.. ~
f Report,' July-Dacambor 1982.
NUREC/CR-3581: STEAM GENERATOR GROUP PROJECT. Annual Report 1982.
NUREG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING l
PROJECTS.' Summary Report - Plum Brook Reactor Facility.
NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT OF SYNTHETIC l
APERTURE FOCUSING TECHNIGUE FOR ULTRASONIC TESTING (SAFT-UT).
NUREG/CR-3649: DYNAMIC TESTING OF AS-BUILT CIVIL ENGINEERING STRUCTURES -A REVIEW AND EVALUATION.
{
OFFICE OF NUCLEAR REACTOR REGULATION (POST-4/28/RO)
CLINCH RIVER BREEDER REACTOR PROGRAM OFFICE NUREG/CR-3224: AN ASSESSMENT OF CRBR CORE DISRUPTIVE ACCIDENT ENERGETICS.
DIVISION OF ENGINEERING NUREG/CR-3127: PROBABILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
NUREG/CR-3614: CONSTANT EXTENSION RATE TESTING OF SA302 GRADE B MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
DIVISION OF HUMAN FACTORS SAFETY NUREG/CR-3396: EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED ORGANIZATIONS.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
i l
DIVISION OF SYSTEMS INTEGRATION (POST B11005) j NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1992.
1 NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
DIVISION OF SAFETY TECHNOLOGY NUREG/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES QUIDE.
NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION j
UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREG/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO.
1 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREC/CR-3531: REVIEW OF SEABROOK UNITS 1 AND 2 AUXILI AAY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
l NUREG/CR-3616: TRANSPORT AND. SCREEN BLOCKAGE CHARACTERISTICS OF' REFLECTIVE METALLIC INSULATION MATERIALS.
i l
l 130
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 number.
ACRES AMERICAN, INC.
NUREC/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
ALDEN RESEARCH LABORATORY NUREC/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
APPLIED SCIENCE ASSOCIATES. INC.
NUREC/CR-3275: JOB ANALYSIS OF TFE ELECTRICI AN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
ARCONNE NATIONAL LABORATORY NUREC/CR-2869 RO1: DIRECTORY AND PROFILE OF LICENSED URANIUM-RECOVERY FACILITIES.
NUREC/CR-2896 VO1: COMMIX-1A: A THREE-DIMENSIONAL TRANSIENT SINCLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume I: User 's Manua l.
NUREC/CR-2896 VO2: COMMIX-1 A: A THREE-DIMENSIONAL TRANSIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HYDRAULIC ANALYSIS OF SINGLE AND MULTICOMPONENT SYSTEMS. Volume II: Assessment And Verification.
NUREQ/CR-2970 VO4: MATERIALS SCIENCE AND TECHNOLOGY DIVISION LIGHT-WATER-REACTOR SAFETY RESEARCH PROGRAN: GUARTERLY PROGRESS REPORT OCTOBER-DECEMBER 1982.
NUREQ/CR-3359 VO3: PHYSICS OF REACTOR SAFETY.Guarterly Report. July-September 1983.
NUREQ/CR-3359 VO4: PHYSICS OF REACTOR SAFETY.Guarterly Repnrt,Ortober-Dernmher 1983.
NUREC/CR-3435: A NEW IMPLICIT NUPERICAL SOLUTION SCHErE IN THE COMMIX-1A COMPUTER PROGRAM.
NUREC/CR-3553: AN EFFICIENT SIMULATION APPROACH FOR EVALUATING THE POTENTIAL EFFECTS OF NUCLEAR POWER PLANT SHUTDOWNS ON ELECTRICAL CENERATING SYSTEMS.
g NUREQ/CR-3649: DYNAMIC TESTING OF AS-DUILT CIVIL ENGIPEERING STRUCTURES
-A REVIEW AND EVALUATION.
NUREQ/CR-3667: A GUIDE FOR REVIEWING ESTIMATES OF PRODUCTION-COST INCREASES THAT RESULT FROM NUCLEAR POWER PLANT OUTAGES.
ARIZONA, UNIV.
Or*,
TUCSON, AZ NUREQ/CR-3612: PREDICi!ON OF FAR-FIELD SUBSURFACE RADIONUCLIDE DISPERSION COEFFICIENTS FROM HYDRAULIC CONDUCTIVITY MEASUREMENTS.A Multidimensional Stochastic Theorg With Application To Fractured Rocks.
BATTELLE HUMAN AFFAIRS RESEARCH CENTERS 131
NUREQ/CR-3601 : MANAGEMENT AND ORGANIZ ATIONAL ASSESSMENTS: A REVIEW OF SELECTED DRGANIZATIONS.
NUREG/CR-3645: A GUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS.
BATTELLE MEMORIAL INSTITUTE, COLUMBUS LADORATORIES NUREC/CR-2815: PROBADILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
NUREQ/CR-3427 VO3: LONG-TERM PERFORMANCE OF MATERI ALS USED FOR HIGH-LEVEL WASTE PACKAGING. Third Guarterly Report,0ctober-December 1983.
BATTELLE MEMORIAL INGTITUTE. PACIFIC NORTHWEST LADORATORIES NUREC/CR-1755: 1ECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING NUCLEAR REACTORS AT MULTIPLE-REACTOR STATIONS.
NUREG/CR-2210: TECHNOLOGY, SAFETY AND COSTS OF DECOMMISSIONING REFERENCE INDEPENDENT SPENT FUEL STORAGE INSTALLATIONS, NUREG/CR-3070: MEASURED IN-REACTOR DATA AND POSTIRRADIATION ODSERVATIONS FOR IFA-527.
NUREQ/CR-3071: IRRADI ATION HISTORY AND INTERIM POSTIRRADI ATION DATA FOR IFA-432.
NUREC/CR-3104: AGUIFER RESTORATION TECHNIQUES FOR IN-SITU LEACH URANIUM MINES.
NUREG/CR-3396-EXPERIENCE WITH THE SHIFT TECHNICAL ADVISOR POSITION.
Interviews With Personnel From Nine Plants.
NUREG/CR-3449: LABORATORY EVALUATION OF LIMESTONE AND LIME NEUTRALIZATION OF ACIDIC URANIUM MILL TAILINGS SOLUTION. Progress Report.
NUREQ/CR-3554: RADIDNUCLIDE MIGRATION IN GROUNDWATER. Annual Progress Report For 1982.
NUREG/CR-3560: EVALUATION METHODS FOR THE CONSEQUENCES OF BELOW WATER TABLE MINE DISPOSAL OF URANIUM MILL TAILINGS.
NUREQ/CR-3561: EDDY CURRENT ROUND RODIN TEST ON LABORATORY PRODUCED INTERGRANULAR STRESS CORROSION CRACKED INCONEL STEAM GENER ATOR TUBES.
NUREG/CR-3562: STEAM GENERATOR TUBE INTEGRITY PROGRAM LEAK RATE TESTS-PROGRESS REPORT.
NUREQ/CR-3563: COBRA / TRAC SIMULATION OF SEMISCALE S-UT-2 TEST.
NUREG/CR-3573: PERSONNEL EXPOSURE FROM RIGHT CYLINDRICAL SOURCES (PERCS). The Theory The Coda And Examples.
NUREG/CR-3578: STEAM GENERATOR GROUP PROJECT PROGRESS REPORT. Task 3-Health Physics.
NUREQ/CR-3579: STEAM GENERATOR GROUP PROJECT. Progress Report On Data Acquisition / Statistical Analysis.
NUREG/CR-35aO: STEAM GENERATOR GROUP PROJECT. Semiannual Progress Report. July-Derember 1982.
NUR EG/CR-3581 : S*.EAM GENERATOR GROUP PROJECT. Annual Report - 1982.
NUREC/CR-3584: CONMONLY USED NUCLEAR MATERIAL MEASUREMENTS AND THEIR l
SOURCES OF ERROR.
NUREG/CR-3601: MANAGEMENT AND ORGANIZATIONAL ASSESSMENTS: A REVIEW OF SELECTED DRGANIZATIONS.
NUREG/CR-3602: FUEL PERFORMANCE ANNUAL REPORT FOR 1982.
il NUREG/CR-3607: RADIONUCLIDE DISTRIBUTIONS AND MIGRATION MECHANISMS AT J
SHALLOW LAND BURI AL SITES: 1982 Annual Report of Research Investigations On The Distribution, Migration And Containment Of Radionuclides At Maxey Flats. Kentucky.
NUREG/CR-3621: SAFETY SYSTEM STATUS MONITORING.
NUREG/CR-3625: REVIEW AND DISCUSSION OF THE DEVELOPMENT CF SYNTHETIC APERTURE FOCUSING TECHNIQUE FOR ULTRASONIC TESTING ( S AFT-U T ).
NUREG/CR-3642: A COBRA / TRAC BEST-ESTIMATE ANALYSIS OF A LARGE-BREAK ACCIDENT IN A PWR EQUIPPED WITH UPPER HEAD INJECTION.
NUREG/CR-3645: A QUIDE TO LITERATURE RELEVANT TO THE ORGANIZ ATION AND ADMINISTRATION OF NUCLEAR POWER PLANTS.
NUREG/CR-3674: DESIGNING VEGETATION COVERS FOR LONG-TERM STABILIZATION l
132
OF URANfUM MILL TAILINCC.
BROOKHAVEN NATIONAL LABORATORY NUHEG/CR-2331 VO3 N2: SAFETY RESEARCH PROGRAMS SPONSORED BY THE OFFICE OF NUCLEAR REGULATORY RESEARCH. Quarterly Progress Report. April-June 1983.
NUREG/CR-2721: SCOPING STUDY OF THE ALTERNATIVES FOR MANAGING WASTE CONTAINING CHELATING DECONTAMINATION CHEMICALS.
NUREQ/CR-E015: PRODABILISTIC SAFETY ANALYSIS PROCEDURES.JIDE.
NUREG/CR-3091 VO3: REVIEW OF WASTE PACKAGE VERIFICATION TESTS. Semiannual Report Covering The Period April-September 1983.
NUREG/CR-3444 VO1: THE IMPACT OF LWR DECONTAMINATIONS ON SOLIDIFICATION, WASTE DISPOSAL AND ASSOCIATED OCCUPATIONAL EXPOSURE. Annual Report.
NUREG/CR-3496: REVIEW OF A TEST PROGRAM FOR GUALIFYING THE SOLIDIFICATION OF EPICOR II RESINS WITH CEMENT, NUREG/CR-3529: REVIEW OF THE ARKANSAS NUCLEAR ONE GENERATING STATION UNIT NO.1 EMERGENCY FEEDWATER SYSTEM RELI ABILITY ANALYSIS.
NUREC/CR-3530: REVIEW OF THE DAVIS-BESSE UNIT NO.
1 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREG/CR-3531: REVIEW OF SEADROOK UNITS 1 AND 2 AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS.
NUREQ/CR-3614: CONSTANT EXTENSION RATE TESTING OF SA302 GRADE B MATERIAL IN NEUTRAL AND CHLORIDE SOLUTIONS.
NUREG/CR-3716: CONTEMPT 4/ MOD 4.A Multicomponent Containment System Analysis Program.
CALIFORNIA, UNIV. OF, LOS ANGELES, CA NUREG/CR-3615: HYDRODYNAMICS OF TWO PHASE FLOW THROUGH HOMOGENEOUS AND STRATIFIED POROUS LAYERS.
CORSTAR RESEARCH, INC.
NUREG/CR-3699: A
SUMMARY
OF CODES FOR WASTE PACKAGE PERFORMANCE ASSESSMENT.
DAMES & MOORE NUREG/CR-3585: DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY.
DECISION RESEARCH,INC.
NUREG/CR-3508: STANDARD SETTING STANDARDS: A SYSTEMATIC APPROACH TO MANAGING PUDLIC HEALTH AND SAFETY RISKS.
EG&G, INC.
NUREG/CR-2335: RESULTS OF THE SEMISCALE MOD-2A NATURAL CIRCULATION EXPERIMENTS.
NUREG/CR-3461: RESPONSE TREE EVALUATION - IMPLICATIONS FOR THE USE OF ARTIFICIAL INTELLIGENCE IN PROCESS CONTROL ROOMS.
NUREG/CR-3556: NONINTERACTIVE SIMULATION EVALUATION FOR CRT-GENERATED DISPLAYS.
NUREG/CR-3631 : RESPONSE TREES AND EXFERT SYSTEMS FOR NUCLEAR REACTOR OPERATORS.
ENERGY, DEPT. OF NUREG/CP-OO50: PROCEEDINGS OF THE INTERNATIONAL BETA DOSIMETRY SYMPOSIUM. Held at Washington. DC February 15-18,1983.
- EVANS, D. D.
NUREG-1046 DRFT: DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN THE UNSATURATED ZONE: TECHNICAL CONSIDERATIONS. Draf t Report Fst Comment.
EXXON NUCLEAR CO.,
INC. (SUBS. OF EXXON CORP.)
NUREG/CR-3067: CALIDRATION SOURCES FOR THE G-M COUNTER USED WITH THE DNL AIR SAMPLER.
NUR EG/CR-3512: RAPID FIELD METHOD FOR THE CONCENTRATION OF R ADIDIODINE FROM MILK.
GENERAL PHYSICS CORP.
NUREQ/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
HANFORD ENGINEERING DEVELOPMENT LABORATORY 133
NUREG/CR-3285: PRE-TEST VISUAL EXAMINATIOM AMD CRUD CHARACTERIZATION OF LWR RODS USED IN T HE LONG-TERM, LOW-TEMPERATURE WHOLE ROD TEST.
HEALTH PHYSICS SOCIETY NUREC/CP-OO50: PROCEEDINGS OF THE INTERNATIONAL DETA DOSIMETRY SYMPOSIUM. Held at Washington,DC February 15-18,1983.
IOWA STATE UNIV., AMES, IA NUUEG/CR-3127: PRODADILISTIC SEISMIC RESISTANCE OF STEEL CONTAINMENTS.
LAWRENCE LIVERMORE LADORATORY NUREG/CR-3428: APPLICATION OF THE SSMRP METHODOLOGY TO THE SEISMIC RISK AT THE ZION NUCLEAR POWER PLANT.
NUREG/CR-3477: CONCENTRATIONS OF COPPER-DINDING PROTEINS IN LIVERS OF DLUEGILLS EXPOSED TO INCREASED CONCENTRATIONS OF SOLUBLE COPPER.
NUREC/CR-3478: REVIEW OF IMPACT OF COPPER RELEASED INTO FRESHWATER ENVIRONS.
NUREC/CR-3483: A STUDY OF THE REGULATORY POSITION ON POSTULATED PIPE RUPTURE LOCATION CRITERIA.
NUREG/CR-3526: IMPACT OF CHANGES IN DAMPING AND SPECTRUM PEAK DROADENING ON THE SEISMIC RESPONSE OF PIPING SYSTEMS.
NUREG/CR-3536: SIMULATION OF LOADING CONDITIONS FOR A TYPE A PACKAGE CONTAINING AMERICIUM-241 INVOLVED IN AN AIRPLANE CRASH AT DETROIT
=
METRO AIRPORT IN JANUARY 1983.
LOS ALAMOS SCIENTIFIC LABORATORY NUREG/CR-3224: AN ASSESSMENT OF CRDR CORE DISRUPTIVE ACCIDENT ENERGETICS.
NUREG/CR-3242: THE LOS ALAMOS NATIONAL LADORATORY/NEW MEXICO STATE UNIVERSITY FILTER PLUGGING TEST FACILITY DESCRIPTION AND PRELIMINARY TEST RESULTS.
NUREG/CR-3440: URANIUM HOLDUP MODELING.
NUREG/CR-3522 VO1: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF SPECIAL NUCLEAR MATERIALS,VOL 1:U Oxide Plus Graphite Powder.
NUREG/CR-3522 VO2: REFERENCE MATERI ALS FOR NONDESTRUCTIVE ASSAY OF SPECI AL NUCLEAR MATERI AL. Volume 2: Thin Metal Foils Of H12hly Enriched Uranium.
MICHIGAN, UNIV. OF, ANN ARBOR, MI NUREC/CR-3145 VO2: GEOPHYSICAL INVESTIGATION OF THE WESTERN OHIO -
INDIANA REGION. Annual Report,0ctober 1982 - September 1983.
MOUND FACILITY /MONSANTO RESEARCH CORP.
NUREC/CR-2926: SIMS AND ESCA STUDIES OF POSSIDLE SODIUM URANATE PRECURSORS AS RELATED TO AEROSOL CHARACTERIZATION FROM A SIMULATED HCDA.
DAK RIDGE NATIONAL LADORATORY NUREG/CR-2OOO VO2N12: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of December 1983.
NUREG/CR-2OOO VO3 N1: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of January 1984.
NUREG/CR-2OOO VO3 N2: LICENSEE EVENT REPORT (LER) COMPILATION.For Month Of February 1984.
NUREC/CR-2397: FUEL INVENTORY AND AFTERHEAT POWER STUDIES OF URANIUM-FUELED PRESSURIZED WATER REACTOR FUEL ASSEMBLIES USING THE SAS2 AND ORIGEN-S MODULES OF SCALE WITH AN ENDF/D-V UPDATED CROSS SECTION LIDRARY.
NUREG/CR-2810: VARIATICNS IN ZIRCALOY-4 CLADDING DEFORMATION IN REPLICATE LOCA SIMULATION TESTS.
NUREC/CR-2824 VO1: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING MARCH 31,1982.
NUREG/CR-3056: POPULATION DISTRIBUTION ANALYSIS FOR NUCLEAR POWER PLANT SITING.
NUREG/CR-3057: ANALYSIS OF AVAILABILITY OF PREVIOUSLY IDENTIFIED SITES UNDER ALTERNATIVE DEMOGRAPHIC CRITERIA.
NUREC/CR-3153: CALCULATION OF FLUID CIJCULATION PATTERNS IN THE 134
VICINITY OF SUBMERGED JETS USING ORSMAC.
NUREG/CR-3171: DATA
SUMMARY
REPORT FOR FISSION PRODUCT RELEASE TEST HI-2.
NUREG/CR-3172: FLDWER: A COMPUTER CODE FOR SIMULATING THREE-DIMENSIONAL FLOW, TEMPERATURE AND SALINITY CONDITIONS IN RIVERS, ESTUARIES AND COASTAL REGIONS.
NUREG/CR-3181: GUANTITY AND NATURE OF LWR AEROSOLS PRODUCED IN THE PRESSURE VESSEL DURING CORE HEATUP ACCIDENTS - A CHEMICAL EGUILIBRIUM ESTIMATE.
NUREG/CR-32OO VO3: EDDY-CURRENT INSPECTION FOR STEAM GENERATOR TUBING PROGRAM GUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1983.
NUREG/CR-3275: JOB ANALYSIS OF THE ELECTRICIAN POSITION FOR THE NUCLEAR POWER PLANT MAINTENANCE PERSONNEL RELIABILITY MODEL.
NUREG/CR-3334 VO2: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1983.
NUREG/CR-3334 VO3: HEAVY-SECTION STEEL TECHNOLOGY PROGRAM GUARTERLY PROGRESS REPORT FOR JULY-SEPTEMBER 1993.
NUREG/CR-3389: VALENCE EFFECTS ON THE SORPTION OF NUCLIDES ON ROCKS AND MINERALS.
NUREC/CR-3422 VO2: AEROSOL RELEASE AND TRANSPORT PROGRAM.Guarterly Progress Report For April-June 1983.
NUREG/CR-3439 VO1: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 1.
NUREG/CR-3439 VO2: A DESCRIPTION OF THE HARDWARE AND SOFTWARE OF THE POWER SPECTRAL DENSITY RECOGNITION (PSDREC) CONTINUOUS ON-LINE REACTOR SURVEILLANCE SYSTEM (CALIFORNIA DISTRIBUTION), VOLUME 2.
NUREG/CR-3482: ANALYSIS OF FERRITE DATA FROM PRODUCTION STAINLESS STEEL PIPE WELDS.
NUREG/CR-3490: THE ROLE OF GEOCHEMICAL FACTORS IN THE ASSESSMENT AND REGULATION OF GEOLOGIC DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE.
NUREG/CR-3491: OCA-II,A CODE FOR CALCULATING THE BEHAVIOR OF 2-D AND 3-D SURFACE FLAWS IN A PRESSURE VESSEL SUBJECTED TO TEMPERATURE AND PRESSURE TRANSIENTS.
NUREG/CR-3492 V02: HIGH-TEMPER ATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, APRIL 1 JUNE 30,1983.
NUREG/CR-3492 VO3: HIGH-TEMPERATURE GAS-COOLED REACTOR SAFETY STUDIES FOR THE DIVISION OF ACCIDENT EVALUATION GUARTERLY PROGRESS REPORT, JULY - SEPTEMBER,1983.
NUREG/CR-3501 : THE EFFECTS OF DELAYING THE OPERATION OF A NUCLEAR POWER PLANT.
NUREG/CR-3502: HIGH DRYOUT QUALITY FILM BOILING AND STEAM COOLING HEAT TRANSFER DATA FROM A ROD BUNDLE.
NUREG/CR-3508: STANDARD SETTING STANDARDS:A SYSTEMATIC APPROACH TO MANAGING PUBLIC HEALTH AND SAFETY RISKS.
NUREG/CR-3523: A RANKING SCHEME FOR MAKING DECISIONS ON THE RELATIVE TRAINING IMPORTANCE OF POTENTI AL NUCLEAR POWER PLANT MALFUNCTIONS.
NUREG/CR-3525: MECHANISTIC CORE-WIDE MELTDOWN AND RELDCATION MODELING FOR BWR APPLICATIONS.
NUREG/CR-3543: SURVEY OF OPERATING EXPERIENCE FROM LERS TO IDENTIFY AGING TREND. Progress Report September 1983.
NUREG/CR-3549: EVALUATION OF CONTAINMENT LEAK RATE TESTING CRITERI A.
NUREC/CR-3598: OCCUPATIONAL RADIOLOGICAL MONITORING AT URANIUM MILLS.
NUREG/CR-3622: A PROBABILISTIC MODEL OF ANNULAR-DISPERSED FLOW IN A REACTOR SUBCHANNEL AS SEEN DY CYLINDRICAL GEOMETRY IMPEDANCE PROBES.
NUREG/CR-3730: EVALUATION OF RADIONUCLIDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS.
REMOTE TECHNOLOGY CORP.
135
i NUREG/CR-3717: EVALUATION OF RODOTIC INSPECTION SYSTEMS AT NUCLEAR POWER PLANTS.
RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY NUREQ/CR-3577: THE MEASUREMENT OF COUNTERCURRENT PHASE SEPAR ATION AND DISTRIBUTION IN A TWO-DIMENSIONAL TEST SECTION.
NUREG/CR-3666: ASSESSMENT OF THE IMPLICATIONS OF CONVERSION OF UNIVERSITY RESEARCH AND TRAINING REACTORS TO LOW ENRICHMENT URANIUM FUEL.
SANDIA LABORATORIES NUREG/CR-2679 VO3: ADVANCTD REACTOR SAFETY RESEARCH GUARTERLY REPORT, JULY-SEPTEMBER 1982.
NUREG/CR-3812: THE RELATIVE IMPORTANCE OF TEMPERATURE PH AND BORIC ACID CONCENTRATION ON RATES OF H2 PRODUCTION FROM GALVANIZED STEEL CORROSION.
NUREC/CR-2932 VO2: EQUIPMENT GUALIFICATION RESEARCH TEST OF ELECTRIC CABLE WITH FACTORY SPLICES AND INSULATION REWORK TEST NO.
2, REPORT NO.
2.
NUREG/CR-3309: A SIMULATOR-BASED STUDY OF HUMAN ERRORS IN NUCLEAR POWER PLANT CONTROL ROOM TASKS.
NUREG/CR-3329 VO3: THERMAL / HYDRAULIC ANALYS!S RESEARCH PROGR AM GUARTERLY REPORT JULY-SEPTEMBER 1983.
NUREQ/CR-3351 : SECURITY OFFICER TACTICAL TRAINING ISSUES INVOLVING ESS EQUIPMENT.
NUREC/CR-3412: CONTAINMENT INTEGRITY PROGRAM GUARTERLY REPORT JANUARY-MARCH 1983.
NUREG/CR-3484: TRAN B-1: EXPERIMENTAL INVESTIGATION OF FUEL CRUST STABILITY ON SURFACES OF AN ANNULAR FLOW CHANNEL.
NUREG/CR-3532: RESPONSE OF RUBBER INSULATION MATERIALS TO MONOENERGETIC ELECTRON IRRADIATIDNS.
NUREQ/CR-3547: A SETS USER'S MANUAL FOR ACCIDENT SEGUENCE ANALYSIS.
NUREQ/CR-3616: TRANSPORT AND SCREEN BLOCKAGE CHARACTERISTICS OF REFLECTIVE METALLIC INSULATION MATERIALS.
BAS OF TEXAS, LTD.
NUREG/CR-3619: SURVEY OF COMMERCIAL NON-NUCLEAR SECURITY PROGRAMS.
SCIENCE APPLICATIONS, INC.
NUREQ/CR-2815: PROBABILISTIC SAFETY ANALYSIS PROCEDURES GUIDE.
CZAWLEWICZ, S. A.
NUREG/CP-OO48 VO1: PROCEEDINGS OF THE ELEVENTH WATER REACTOR FAFETY INFORMATION MEETING.
NUREG/CP-OO48 VO2: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CP-OO48 VO3: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARC.1 INFORMATION MEETING.
NUREG/CP-OO48 V04: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREG/CP-0048 V05: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
NUREQ/CP-OO48 V06: PROCEEDINGS OF THE ELEVENTH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING.
TEKNEKRON, INC.
NUREG/CR-3636: BENCHMARK PROBLEMS FOR REPOSITORY DESIGN MODELS.
UNION CARBIDE CORP.
NUREG/CR-3251: THE ROLE OF SECURITY DURING SAFETY-RELATED EMERGENCIES AT NUCLEAR POWER PLANTS.
UNITED NUCLEAR CORP.
NUREG/CR-3550: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Annual Summary Report - Fiscal Year 1983.
NUREG/CR-3605: EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROJECTS.
Summary Report - Plum Brook Reactor Facility.
WASHINGTON, UNIV. OF, SEATTLE, WA 13S
I NURED/CR-3698: AN AGE STRUCTURED STOCHASTIC RECRUITMENT MODEL FOR ASSESSMENT. POWER PLANT IMPACT.
WATER. WASTE & LAND, INC.
NUREC/CR-3390: DOCUMENTATION AND USER 'S GUIDE: UNSAT2 - VARI ABLY SATURATED FLOW MODEL.(Including 4 Example Problems).
WESTINGHOUSE ELECTRIC CORP.
NUREC/CR-3661: PROTOTYPICAL STEAM GENERATOR (MB-2) TRANSIENT TESTING PROGRAM. Task Plan / Scaling Analysis Report.
c.
5 a
5 4
9' a.
1 I
i 1
S C
4,1 *,
- J}
l
- k
.i l
dtf^jN &
I 137 l-
Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If fur =
ther information is needed, refer to the main citation by the NUREG number.
50*313 Arkansas.euclear Une, Unit 1, Arkansas Po.er L Lia%t C6 NU8EG/CR*3529 70 0027 bancock 4 pticon Co., Lynchoura, WA, Nu8EGat049 50-537 Citnen wiver oreeoer weactor, Project manapement Corp.
NUREG/Cn=322e 50-445 Comanche reak Steam Electric Sta., unit 1, ie,as uttltttes Generatin NukEG=077S 50 446 Comanche ream Steam Electric sta., unit 2, Tesah utiltttes Generattn N64cG*0775 50-386 Devin.nesse Nuctear Power Station, unit 1, Teleco Eatson Co.
NueCG/CN=3530 S0-275 Otsulo Canyon Nuclear Power Plant, Unit 1, Pacific bas 6 Electric Co Nu tG*0675 317 a
S@=275 Ossolo Canyon Nuclear Pomee Plant, untt 1, Pacific has s Electric Co NuktG=067S 522 S0-323 Diaolo Conven Nuclear Power Plant, unit 2, Pactitt has & Cloctric Co NuREG=067S 317 50*323 Diaolo Canyon Nwelear Power Plant, unit 2, Pacific Gas 6 Electric to NuREG=0675 522 50-173 LaSalle County atation, unit 1, Co**onwealem totson Co.
Nuh(G=0S19 aos
$0*37e LaSalle Co.aty btatione Unit de Coemonwealtn Ectgon Co, hwatG.051w 30s 50-184 National sureau of stanoares heactor, hattonal bureau of Stancerne NURtGalv07 304 50*440 Perry Nuclear Po.se Plant, Unit t, Clevelseo Electric illu=tnating C NL#EG=0867 30e 50-448 Perry huclear Powee Plant, unit 2, Clevelano Electetc tiluminating C bu tG=0e87 304 s
50-30 Plum droon Hesearch Reactor Facility, NASA NURCG/CN=3605 S0-443 Seaoroot euclear 3tation, Unit 1, Public Service Co. of he Hamponte huREC/CE*3S31 50-444 Seaorocu.euclear Station, Unit 2, Public Service Co. of New Naepshir NuREC/C4=4531 50-367 Susquenanna stes Electric 6tation, Unit 1, Peensylvente Power 6 Lig NuR(G*077b 506 50-368 Susquehanna 5 team Electric Station, unit 2, Peensylvente Po.er & Lig huhEG=07Fe $06 50-368 Susquenanna Steam Electric heation, unit de Pennsylvante Power & Lig NUREG*l042 50-320 inroe alle as6and Nuclear Station, unit 2, betropoltten Eatson Go.
NuREG=0647 50*320 fnroe Mlle Island Nuclear Station, unit 2, Metropolttan Ectson Co.
NueEG.0e9e R02 50-320 fnree Ptle as6and huclear Station, unit 2, Petropslit;n Eatson Co.
NumiG=0732 401 50-166 Univ. of Harylano sesearch heactor hueCG-1043 50*190 aatts See Nuclear Plant, unit 1, Tennessee Valley Authority NudLG=0061 802 50*391 matts Der N.ctsar Plant, ' snit ?,
tennettee Volley Aufmertt, NUREG=0ae7 502 50=295 Zion Nuclear Po.ee station, Unit le Common =ealtn Lotson Co.
NuREG/CN=3828 50-30e 2 ton huelear vower station, Unit 2, Coecon.ealth toison Co.
NuREG/CA-3420 8
l 139
=u w
u.s a--
a n-A w
-=
.1,---m-_.
a--.-a
.m--
g---
e I
1 i
l I
J l
i i
I I
1 i
l 1
l l
I l
8
I leRC FORM 335 U S. NUCLE AR REGULATORT COe8Mit$ ION I RtPORY NuM85 A f Asspwd 9y Tt0C. sea vee No. er eaFi (2 Set Ifo'" 'S*-
BISUOGRAPHIC DATA SHEET NUREG-0304, Vol. 9, No. 1 l
(
si..NirsuCr ON ON vM. Riv Rs.
i 2 YlTLE ANQ SveieTLE 3 Lggyg gLa Regulatory and Technical. ports
/
Compilation for First Qua er 1984
/
/'
4 oATE REPORY COMPLETED MONTM
- EAR S auTMO^tsi e DATE REPORT InavtD MONYM vtAR May 1984 7 FinF OAU4NG ORGANi2 AteON NaME AND MaeLiNG Acomes5 fear le Cosw a PROJECYiYasn WORE UNif NvMeta Division of Technical Informatio nd Document C trol Office of Administration
- P'N oa oa N' N Mata U.S. Nuclear Regulatory Comission l
Washington, DC 20555 l
10 Se'ON50 RING ORG ant 2 4 TION N AME AND MacLsNG AcoRESS trewee le Cope, s ee TYPE OF REPORT Quarterly Same as 7, above.
,,,,,,,,co,,,,,,,_,,_,
January - March 1984 12 SUPFLEMENT ARY NOf t1 13 AS$TR ACf #100 weres er 'essi This compilation lists all NRC regula ry and techn al reports published under l
the NUREG series during the first qua er of 1984.
.. oOCuME N r.N.L,s.......ORos o sCR.. roms 4 a,v,*g;r -
abstract Unlimited ind:x
't $1CURif f CLASS'8sCatiON f Fag pages
. oiNri.. AtOPtN Noio n RMs Unclassified o r. -,,
Unclassified 17 hvMetR OF PAGES
.., R,C.
UNITED STATES nest ctass unit t s raio NUCLEAR REGULATOSY COMMISSION N5 ' ' ','g WASHINGTON, D.C. 20566 ansa 3 c piessi n. s11 PENALTY FOR PRIVATE E. 4300 Main Citations and Abstracts Contractor Report Number index Personal Author Index Subject Index 120555078877 1
99999 US NRC ADM-DIV 0F TIDC POI.!CY C PUB MGT BR-PDR NURFG W-501 NRC Originating WASHINGTON DC 20555 Organization Index NRC Contractor SponsorIndex Contractor index L
Licensed Facility index
.