ML20052E470
| ML20052E470 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1982 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V03-S01, NUREG-304, NUREG-304-V3-S1, NUDOCS 8205110137 | |
| Download: ML20052E470 (26) | |
Text
NUREG-0304 Vol. 3 Supplement Regulatory and Technical Reports l
Compilation for 1975-1978 i
Office of Administration U.S. Nuclear Regulatory Commission p ** "aui,,
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Regulatory and Technical Reports Compilation for 1975-1978 Date Published: April 1982 Division of Technical Information and Document Control Office of Administration U.S. Nuclear Regulatory Commission Washington, D.C. 20555 p.. m,
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1 CONTENTS Preface.
y Thumb Tab Sequential List of Reports in Report-Number Order.
1 Keyword Index.
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PREFACE i
This brief compilation lists formal reports issued by the U.S. Nuclear
- Regulatdry Commission in 1975 through 1978 that were not listed in the
" Regulatory and Technical Reports Compilation for 1975-1978," NUREG-0304, Vol. 3.
This compilation is divided into two sections.
The first cor.sists of a sequential listing of all reports in report-number order.
The second j
section consists of an index developed from keywords in report titles and abstracts.
Each keyword is cross-referenced to the report or reports concerning that subject.
How to Read Citations The principal bibliographic elements in a typical report citation are as follows:
NUREG-0142 Environmental Impact Appraisals for Licensee Safeguards Contingency Plans June 1977 GP0 NTIS The bibliographic elements are (1) report number, (2) report title, (3) date report issued, and (4) availability.
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-GP0 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 VISA charge card by calling the NRC-GPO Sales Office on (301) 492-9530.
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- Non-U.S. customers must make payment in advance either by International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.
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Sequential List of Reports in Report-Number Order i
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Report No.
Bibliographic Data NUREG-75/074 Loss of Coolant Accident (LOCA) Temperature Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
August 1975 GP0 NTIS The applicability of the Zircaloy-oriented temperature limit of 10 CFR 50.46 to ttainless steel clad fuel is reviewed.
The review provides a basis for the selection of an exact Peak Cladding Temperature (PCT) limit.
The review leads to the conclusion that the behavior of stainless steel clad fuel under loss of coolant acc; dent (LOCA) condition 3 would be conser-vative reiative to Zircaloy clad fuel when considering the refinements of those evaluation models (EM) complying with 10 CFR 50.46.
Furthermore, the PCT criterion of 2300 F appears applicable to stainless steel cladding when the 10 CFR 50.46 emergency core cooling system-ems are used.
NUREG-75/105 Safety Evaluation Report for the Preliminary Design Approval Related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design November 1975 GP0 NTIS A Safety Evaluation Report related to C. F. Braun and Company's BRAUN Safety Analysis Report (BRAUN SAR),
which contains safety information for a standard turbine island design to be utilized in conjunction with General Electric Company's GESSAR-238 standard design for the BWR-6/ Mark III nuclear island, has been published by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC).
It consists of a technical review and NRC staff evaluation on:
(1) design, fabrication, testing criteria and performance characteristics of the turbine building structures, systems and components important to safety; (2) C. F. Braun and Company's design, engineering and' QA organization; and (3) design criteria for systems to control the turbine island's radiological effluents.
The NRC staff has concluded that when the GESSAR-238/
BRAUN SAR is paired with an acceptable utility applicant balance of plant design and a suitable site is selected, taking into consideration the site criteria contained in 10 CFR Part 100, the proposed
Report No.
Bibliographic Data facility can be constructed and operated without undue risk to the health and safety of the public.
NUREG-0011 Safety Evaluation Report of the Sequoyah Nuclear Plant Units 1 and 2 January 1976 GPO NTIS A safety evaluation of the Tennessee Valley Authority's application for a license to operate its Sequoyah Nuclear Plant, Units 1 and 2 (Docket Nos. 50-327 and 50-328), located in Hamilton County, Tennessee, has been prepared by the Office of Nuclear Reactor 1
Regulation of the Nuclear Regulatory Commission.
It consists of a technical review and staff evaluation of applicant information on:
(1) population density, land use, and physical characteristics of the site area; (2) design, fabrication, construction, testing criteria, and performance characteri'stics of plant structures, systems, and components important to safety; (3) expected response of the facility to anticipated operating transients, and to postulated l
design basis accidents; (4) applicant engineering and construction organization, and plans for the conduct of plant-operations; and (5) design criteria for a system to control the plant's radiological effluents.
The staff has concluded that the plant can be operated by the Tennessee Valley Authority without endangering the health and safety of the public provided that the-outstanding matters discussed in the report are favorably resolved.
NUREG-0047-1 Evaluation of Pressure Drop Across Area Changes During Blowdown:
Quarterly Progress Report February 1976 GPO NTIS Transient pressure drops across abrupt area changes are to be determined in a series of blowdown experiments.
These tests are to be conducted, with Freon 113 as the test fluid, in a well instrumented apparatus.
All necessary instrumentation and readout have not yet been received.
Only' preliminary blowdown runs were
.therefore possible.
The preliminary runs indicated the
' revised loop configuration to be generally satisfactory.
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Report No.
Bibliographic Data The apparatus is now being revised to remedy hardware failures and to add some additional instrumentation.
The void sensors to be used in the final system have been built and the steady state apparatus for their calibration is nearly complete.
Work is proceeding on the computational procedures needed for data analysis.
A finite difference procedure has been developed and the computer program largely completed.
A parallel effort, using the method of characteristics, shows real characteristics for the conditions examined.
NUREG-0047-8 Evaluation of Pressure Drop Across Area Changes During Blowdown July 1977 GPO NTIS Transient pressure drops across area changes were determined in a series of blowdown experiments.
These tests were conducted with Freon 113 as the test fluid in a well instrumented apparatus.
During this period, some additional check runs were made with the 3/4" x 1/2" pipe expansion in place.
These runs marked the conclusion of the experimental program.
The data for all runs have been reduced to engineering units and recorded on a series of 4 magnetic tapes.
In addition, a final report, containing graphical displays of all data and instructions for use of the magnetic tapes, was prepared.
NUREG-0051 Supplement No. 2 to Safety Evaluation Report for the Koshkonong Nuclear Plant, Units 1 and 2 June 1976 GPO NTIS 5
Supplement No. 2 to the Safety Evaluation Report of Wisconsin Electric Power Company's application for
. licenses to construct and operate their proposed Koshkonong Nuclear Plant, Units 1 and 2 (Docket Nos. STN 50-502 and STN 50-503), located in Jefferson County,. Wisconsin, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory 3
F' t
1 Report No.
Bibliographic Data Commission.
This supplement presents the final resolution of those items that were outstanding at the time of the publication of Supplement No. 1.
NUREG-0057 Supplement No. 1 to Safety Evaluation Report for Jamesport Nuclear Power Station, Units 1 and 2 March 1976 GPO NTIS Supplement No. 1 to the Safety Evaluation Report of Long Island Lighting Company's application for licenses to construct and operate their proposed Jamesport Nuclear Power Station, Units 1 and 2 (Docket Nos.
STN 50-516 and STN 50-517), located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission.
This supplement reports the status of certain items that had not been completely resolved at the time of publication of the Safety Evaluation Report.
j NUREG-0061 Safety Evaluation Report Related to Operation of Browns Ferry, Units 1 and 2 Following the March 22, 1975 Fire March 1976 GP0 NTIS The Safety Evaluation Report issued February 23, 1976, presents the NRC evaluation regarding the acceptability of the restoration and modifications at the Browns Ferry Plant Units 1 and 2, following the March 22, 1975 fire, to establish that the facility may be operated in the restored and modified condition without endangering the health and safety of the public.
The modifications involved enhancing separation of redundant safeguards equipment by some rerouting of cable and by the application of a fire-retardant coating to the cable; enhancing fire extinguishing capability by the addition of fixed spray and sprinkler systems and expanded smoke and heat detection systems; and enhancing the overall fire protection program by changes in procedures, training, and organization. The NRC staff indicated some items that remained to be resolved prior to operation and concluded that subject to their satis-factory resolution the restoration of Browns Ferry Nuclear Plants Units 1 and 2 including the modifi-cations is acceptable and that there is reasonable -
assurance that the health and safety of the public will 4
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Bibliographic Data not be endangered by operation of the facility as restored and modified.
' Final Environmental Statement Related to Construction of Montague Nuclear Power Station, Units 1 and 2 July 1976 GPO NTIS A Final Environmental Statement for the Northeast Nuclear Energy Company for the construction of the Montague Nuclear Power Station, Units 1 and 2 (Docket Nos. 50-496 and 50-497), located in Franklin County, Massachusetts, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC).
This statement provides (1) a summary of environmental impact and adverse effects of the proposed facility, and (2) a consideration of principal alternatives.
Also included are comments of f
governmental agencies and other organizations on the Draft Environmental Statement for this project, and staff responses to these comments.
The NRC staff has concluded, based on a weighing of environmental, economic, technical, and other benefits against environmental costs and available alternatives, that construction permits could be granted.
The applicant will be required to submit to the staff, for review and approval, prior to issuance of the construction permit, a revised design for the closed-cycle cooling system utilizing a cooling tower design that mitigates the aesthetic impact of the natural draft towers, or, alternatively, a detailed analysis that establishes that such alternatives are not feasible.
The applicant shall also provide a study of the distribution and relative abundances of shad and shortnose sturgeon larvae and young juveniles in the Holyoke Pool along with its proposed intake design and location based on these data for review and approval to the Commission prior to beginning co'nstruction of the intake structure.
NUREG-0095 Joint ERDA/NRC Task Force on Safeguards ERDA 77-34 Final Report July 1976 (UNCLASSIFIED VERSION)
July 1976 GPO NTIS 5
rn Report No.
Bibliographic Data A joint ERDA/NRC task force was formed on March 17, 1976, to propose a plan of action for improving safeguards at certain nuclear fuel cycle facilities.
This was a joint undertaking because it focused upon NRC licensees who are also ERDA contractors.
The task force concentrated on physical protection and control of nuclear material.
It did not address the matter of nuclear material accountability or the problem of protection against sabotage.
It confined its examina-tion to a limited number of facilities possessing strategic quantities of weapons-usable special nuclear materials (SSNM) and did not consider safeguards at nuclear reactors or for nuclear materials in transport.
The task force recommended that NRC and ERDA initiate actions to upgrade safeguards to a level affording high-confidence protection against theft of SSNM by internal conspiracies and determined violent assaults.
Since they found no evidence of serious threats to the industry, the task force did not believe emergency measures such as shutdown of the-industry or immediate use of federal security forces were warranted.
NUREG-0108 Tornado-Borne Missile Speeds April 1976 GPO NTIS At the request of the U.S. Nuclear Regulatory Commission (NRC) the National Bureau of Standards (NBS) has carried out an independent investigation into-the question of tornado-borne missile speeds, with a view
'to assisting NRC in identifying pertinent areas of uncertainty and in estimating credible tornado-borne missile speeds - within the limitations inherent in the present state of the art.
The investigation consists of two parts:
- 1) a study, covered in this report, in which a rational model for the missile motion is proposed, and numerical experiments are carried out corresponding to various assumptions on the initial conditions of the missile motion, the structure of the tornado flow, and the aerodynamic properties of the missile; 2) a theoretical and experimental study of tornado-borne missile aerodynamics, conducted by Colorado State Univ. (CSU) under contract with'NBS, to be covered in a separate report by CSU.
In the present report, the factors affecting missile motion, and their influence upon such motion, are examined..Information is provided on a computer program developed for calculating missile speeds.
Maximum speeds for a number of specified potential tornado-borne missiles 6
Report No.
Bibliographic Data are presented, corresponding to a set of assumptions believed by the writers to be reasonable for design purposes.
It is pointed out that higher speeds are conceivable if it is assumed that certain circum-l stances, examined in the body of the report, will obtain.
It is the judgment of the writers that the probabilities of occurrence of such higher speeds for any given tornado stnike are low.
More than quali-tative estimates of such probabilities are, however,.
beyond the scope of this investigation.
NUREG-0142 Environmental Impact Appraisals for Licensee Safeguards Contingency Plans June 1977 GPO NTIS The environmental impact of a rule to require licensees to develop, implement, and follow safeguards contin-gency plans was appraised.
The required plans would be largely procedural in nature, using resources already
'in hand for the physical protection of licensed nuclear material and facilities.
No adverse environmental effects have been identified.
No natural resources will be committed to the ir.;plementation of the regulation.
Based upon the evaluation of all factors of potential significance, the NRC decided not to prepare an environmental impact statement.
NUREG-0149 Final Environmental Statement for the Construction of the Midland Plant Units 1 and 2, Consumers Power-Company Jan. 1977 (Reprint 1)
GPO NTIS f
A Final Environmental Statement for the construction of Consumers Power Company's Midland Plant, Units 1 and 2 (Docket Nos. 50-329 and 50-330) located in Midland
'7 County, Michigan, was prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC) (formerly AtomicLEnergy Commission).
This statement prcvided (1) a summary of environmental impacts and adverse effects, and (2) a consideration of principal alternatives.
Also included are. comments of Federal agencies and other State and local organiza-tions on the Draft Environmental Statement for this j
plant, and staff responses to those comments.
Based on 7
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Bibliographic Data a weighing of the environmental, economic, technical, and other benefits against environmental costs and available alternatives, construction permits were granted in December 1972.
This is not a final licensing action.
The applicant is required to assure that adverse enviconmental impacts from construction activities are kept to a minimum.
NUREG-0191 Final Environmental Statement Related to the Conversion from a Provisional to a Full-Term Operating License Lacrosse Boiling Water Reactor February 1977 GPO NTIS A Final Environmental Statement for the Dairyland Power Cooperative for the conversion from a provisional to a full-term operating license for the Lacrosse Boiling Water Reactor, Docket No. 50-409, located in Vernon County, Wisconsin, has been prepared by the Office of
[
Nuclear Reactor Regulation.
This statement provides (1) a summary of environmental impacts and adverse effects of operation of tt'e facility, and (2) a consideration of principal alternatives (including removal of LACBWR from service alternative cooling methodology, and alternative waste treatment systems).
Also included are the comments of Federal, State and local governmental agencies and certain non-governmantal organizations on the Lacrosse Draft Environmental Statement and staff responses to these comments.
After weighing environmental, economic, and technical benefits and liabilities, the staff recom-mends conversion from a provisional operating license to a full-term operating license, subject to specific environmental protection limitations.
An operational monitoring program shall be established as part of the Environmental Technical Specifications.
NUREG-0446 Calculation of Releases of Radioactive Materials in Gaseous Effluents from Nuciear-Powered Merchant Ships (NMS-GEFF Code)
June 1978 GPO NTIS This report provides a method for the determination of the releases of radioactive material in gaseous effluents from nuclear powered merchant ships and the 8
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Bibliographic Data control exercised by the ships over these releases.
The NRC staff has developed a computerized model, the NMS-GEFF Code, which calculates releases of radioactive material in gaseous effluents for nuclear powered merchant ships (NMS) using pressurizen water reactors.
The calculations are based on nuclear steam supply system, auxiliary system and radwaste system designs applicable to the NMS.
The calculations are also based on data and parameters applicable to the NMS.
This report provides instructions for using the NMS-GEFF Code.
It describes the parameters incor-porated in the Code, the input data required, and a step-by-step procedure for completing the input data cards.
It provides parameters for an assessment of reactor and radwaste system performance for normal operation including anticipated operational occur-rences.
It also contains a Fortran IV listing of the NMS-GEFF Code, a form for entering the input data, and a sample calculation.
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Keyword Index l
Keywo/d Listing Report Title Report No.
Balance of Plant Safety Evaluation Report for the Preliminary NUREG-75/105 Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design Blowdown Experiments Evaluation of Pressure Drop Across Area NUREG-0047-1 Changes During Blowdown:
Quarterly Progress Report Blowdown Experiments Evaluation of Pressure Drop Across Area Changes NUREG-0047-8 During Blowdown BRAUN SAR Safety Evaluation Report for the Preliminary NUREG-75/105 Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design Browns Ferry Safety Evaluation Report related to operation NUREG-0061 of Browns -Ferry, Units 1 and 2 Following the March 22, 1975 Fire Cladding Loss of Coolant Accident (LOCA) Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
Closed-Cycle Cooling Final Environmental Statement related to NUREG-0084 construction of Montague Nuclear Power Station, Units 1 and 2
Keyword Listing Report Title Report No.
Construction Final Environmental Statement for the NUREG-0149 ccnstruction of the Midland Plant Units 1 and 2, Consumers Power Company Construction Permit Final Environmental Statement related to NUREG-0084 construction of.Montague Nuclear Power Station, Units 1 and 2 Cooling Methodology Final Environmental Statement related to the NUREG-0191 conversion from a provisional to a full-term operating license Lacrosse Boiling Water Reactor ECCS Loss of Coolant Accident (LOCA) Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
EIAs Environmental Impact Appraisals for Licensee NUREG-0142 Safeguards Contingency Plans Environmental Impacts Environmental Impact Appraisals for Licensee NUREG-0142 Safeguards Contingency Plans ERDA/NRC Joint ERDA/NRC Task Force on Safeguards NUREG-0095 Final Report July 1976 (UNCLASSIFIED VERSION)
ERDA 77-34
-FES Final Environmental Statement related to NUREG-0084 construction of Montague Nuclear Power Station, Units 1 and 2
Keyword Listing Report Title Report No.
FES Final Environmental Statement for the NUREG-0149 construction of the Midland Plant Units 1 and 2, Consumers Power Company FES Final Environmental Statement related to the NUREG-0191 conversion from a provisional to a full-term operating license Lacrosse Boiling Water Reactor Fire Extinguishing Safety Evaluation Report related to operation NUREG-0061 of Browns Ferry, Units 1 and 2 Following the March 22, 1975 Fire Fire Protection Safety Evaluation Report related to operation NUREG-0061 of Browns Ferry, Units 1 and 2 Following the March 22, 1975 Fire 1
Fire-Retardant Coating Safety Evaluation Report related to operation NUREG-0061 of Browns Ferry, Units 1 and 2 Following the March 22, 1975 Fire Freon 113 Evaluation of Pressure Drop Across Area Changes NUREG-0047-8 During Blowdown Gaseous-Effluent Calculation of Releases of Radioactive NUREG-0446 b
Materials in Gaseous Effluents from Nuclear-Powered Merchant Ships (NMS-GEFF Code)
Keyword Listing Report Title Report No.
NUREG-75/105-GESSAR-238 Safety Evaluation Report for the Preliminary Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design Final Environmental Statement related to NUREG-0084 Intake Structure construction of Montague Nuclear Power Station, Units 1 and 2 Jamesport Supplement No. 1 to Safety Eyaluation Report NUREG-0057 for Jamesport Nuclear Power Station, Units 1 and 2 NUREG-0051 Supplement No. 2 to Safety Evaluation Report Koshkonong for the Koshkonong Nuclear Plant, Units 1 and 2 l
l Final Environmental Statement related to the NUREG-0191 LACBWR conversion from a provisional to a full-term I
operating license Lacrosse Boiling Water Reactor Final Environmental Statement related to the NUREG-0191 Lacrosse conversion from a provisional to a full-term operating license Lacrosse Boiling Water Reactor Loss of Coolant Accident ~(LOCA) Temperature NUREG-75/074 LOCA Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
Keyword Listing Report Title Report'No.
Merchant Ships Calculation of Releases of Radioactive NUREG-0446 Materials in Gaseous Effluents from Nuclear-Powered Merchant Ships (NMS-GEFF Code)
Midland Final Environmental Statement for the NUREG-0149 construction of the Midland Plant Units 1 and 2, Consumers Power Company Missiles Tornado-Borne Missile Speeds NUREG-0108 Montague Final Environmental Statement related to NUREG-0084 construction of Montague Nuclear Power Station, Units 1 and 2 NMS-GEFF Code Calculation of Releases of Radioactive NUREG-0446 Materials in Gaseous Effluents from Nuclear-Powered Merchant Ships (NMS-GEFF Code)
Nuclear Material Joint ERDA/NRC Task Force on Safeguards NUREG-0095 Final Report July 1976 (UNCLASSIFIED VERSION)
ERDA 77-34 Operating License Final Environmental Statement related to the NUREG-0191 conversion from a provisional to a full-term operating license Lacrosse Boiling Water Reactor PCT Loss of Coolant Accident (LOCA). Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
Keyword Listing Report Title Report No.
Physical Protection Joint.ERDA/NRC Task Force on Safeguards NUREG-0095 Final Report July 1976 (UNCLASSIFIED VERSION)
ERDA 77-34 Physical Protection Environmental Impact Appraisals for Licensee NUREG-0142 Safeguards Contingency Plans PWR Loss of Coolant Accident (LOCA) Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
Radioactive Material Calculation of Releases of Radioactive NUREG-0446 Materials in Gaseous Effluents from Nuclear-Powered Merchant Ships (NMS-GEFF Code)
Radiological Effluents Safety Evaluation Report for the Preliminary NUREG-75/105 Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design Safeguard Plans Environmental Impact Appraisals for Licensee NUREG-0142 l-Safeguards Contingency Plans I
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. Safeguards Joint ERDA/NRC Task Force on Safeguards NUREG-0095 Final. Report July 1976 (UNCLASSIFIED VERSION)
ERDA 77-34 Sequoyah Safety Evaluation Report of the Sequoyah Nuclear NUREG-0011 Plant Units 1 and 2 l
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iKeyword Listing.
Report Title Report No.
SER Safety Evaluation Report for the Preliminary NUREG-75/105 Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a
. Standard Turbine Island Design
-SER Safety Evaluation Report of the Sequoyah Nuclear NUREG-0011 Plant Units 1 and 2 SER Supplement No. 2 to Safety Evaluation Report NUREG-0051 for the Koshkonong Nuclear Plant, Units 1 and 2 r
SER Supplement No. 1 to Safety Evaluation Report NUREG-0057 for Jamesport Nuclear Power Station, Units 1 and 2 SER Safety Evaluation Report related to operation NUREG-0061 of Browns Ferry, Units 1 and 2 Following the March 22, 1975 Fire SSNM Joint ERDA/NRC Task Force on Safeguards NUREG-0095 Final. Report July 1976 (UNCLASSIFIED VERSION)
ERDA 77-34 Stainless Steel Loss of Coolant Accident (LOCA) Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel in a Pressurized Water Reactor (PWR)
Standard Turbine Island Design Safety Evaluation Report for the Preliminary NUREG-75/105 Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design
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Keyword Listing Report Title Report No.
Tornadoes Tornado-Borne Missile Speeds NUREG-0108 Transient Pressure Drups Evaluation of Pressure Drop Across Area Changes NUREG-0047-8 During Blowdown Transient Pressure Drops Evaluation of P'..ssure Drop Across Area NUREG-0047-1 Changes During b iwdown:
Quarterly Progress Report
.Turb ne Bui Iding Safety Evaluation Report for the Preliminary
.NUREG-75/105 i
Design Approval related to C. F. Braun and Company's BRAUN Safety Analysis Report for a Standard Turbine Island Design Waste Treatment Final Environmental Statement related to the NUREG-0191 conversion from a provisional to a full-term operating license Lacrosse Boiling Water Reactor Zircaloy Loss of Coolant Accident (LOCA) Temperature NUREG-75/074 Criterion for Stainless Steel Clad Fuel-in a Pressurized Water Reactor (PWR) 4 f
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U.S. NUCLEAR REGULATORY COMMISSION
-BIBLIOGRAPHIC DATA SHEET g 1fm9nt
- 4. TITLE AND SUBTtiLE LAdd Vo/urne No.,if apprmnatel
- 2. (Leave blanki Regulatory and Technical Reports
- 3. RECIPIENT'S ACCESSION NO.
Compilation for 1975-1978
/ AUTH0HlS)'
- 5. DATE HEPORT COMPLE TED MON TH l YEAR
- 9. PEHF ORMING ORGANIZATION NAME AND MAILING ADDHESS //nclude lip Codel DATE REPORT ISSUED Division of Technical Information and Document Control ipyj"1 I 19"g
^
Office of-Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 g
,t,,,,
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- 12. SPONSOHING ORG(NIZATION NAME AND MAILING ADDRESS (/nclude Ira Code /
- 10. PROJECT / TASK / WORK UNIT NO.
same as 9
- 11. CONTRACT NO.
- 13. TYPE OF REPORT PE RIOD COVE RE D (/nclusive dates)
Bibliographic 1975 - 1978
- 15. SUPPLEMENTARY NOTES
- 14. (Leave Nank/
- 16. ABSTRACT (200 words or less)
This compilation lists formal staff and contractor reports issued by the U.S. Nuclear Regulatory Commission that were not listed in " Regulatory.
and Technical Reports for 1975 - 1978," NUREG-0304, Vol. 3.
This compila-tion contains a listing of reports and their abstracts and a keyword index.
- 17. KEY WORDS AND DJCUMENT ANALYSIS 17a. DESCRiPTORS 17b. IDENTIFIERS!OPEN ENDED TERMS
- 18. AVAILABILITY STATEMENT
/
- 19. SECURITY CLASS (This reportl
- 21. NO. OF PAGES Unclassified Unlimited 20.giTYgSyni,, p,9e/
- 22. PRICE NQC FORM 335 (7 771.
UNITED STATES I
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