ML20149E315
| ML20149E315 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1997 |
| From: | Garver M NRC OFFICE OF THE CONTROLLER |
| To: | |
| References | |
| NUREG-1350, NUREG-1350-V09, NUREG-1350-V9, NUDOCS 9707180165 | |
| Download: ML20149E315 (144) | |
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- Availability Notice 1 4
5 Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
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Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and cpplicant and licen'see docu-ments and correspondence.
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- . - . .. . . . .. x ., .. .-, panw nycu-ii NUCLEAR REGULATORY COMMISSION 4
.: MGQgggggy Abstract The Nudear Regulatory Commission Infor- reports that are submitted directly to the NRC motion Digest (digest) provides a summary of by the licensee. This information is reviewed information about the U.S. Nuclear Regulo- by the NRC for consistency only and no tory Commission (NRC), NRC's regulatory independent validation and/or verification responsibilities, NRC licensed activities, and is performed.
general information on domestic and world-wide nudear energy. The digest, published Comments and/or suggestions on the data ,
annt, ally, is a compilation of nuclear- and presented are welcomed and should be NRC-re:ated data and is designed to provide directed to Melanie Garver, United States a quick reference to major fac;3 about the Nudear Regulatory Commission, Office of agency and the industry it regulates. In the Chief Financial Officer, Division of general, the data cover 1975 through 1996, Budget and Analysis, Washington, DC with exceptions noted. Information on gen- 20555-0001. For detailed and complete eroting capacity and average capacity factor information about tables and figures, refer for operating U.S. commercial nudear powerto the source publications.
- reactors is obtained from monthly operating x_ nan.x 1997 INFORMATION DIGEST iii
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..[ AW 32MM7%DT Contents Abstract........................................................................................................................iii For More I nformati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
J NRC a s a Regulatory Agency . . . . . . .... .. . . . . .. . . . ... .. . .. . . .. . . . . .. . .. .. . .. . . ... .. ..... ... ..... ... .. . ... . ... .. . . . .. . 1 l Mission and Statutory Authority .. .......... .. ............ ... ............ ...................... . .. . ........... 2 Principles of Good Regulation ............. ... ..... ... .. ........... ..... .... .................... .............. 3 Ma jor Activi ti es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4 Organizations a nd Fu nctions . .. ... . .. . . .. .. . .. . . . . . . . . .. . . . . . .. . . . .. . . . . .. . .... . .. ....... .. ... ... .... . .. . . ... 5 N R C Loca t ion s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
NRC Fiscal Year 1997 Resources ........... . ......................... ............ ......................... 10 U.S. and Worldwide Energy . . . . .. . .. . . . . .. . . . .. . . . . . .. . .. . .. .. . . . . . . ... ... ..... . .. . . . . ... . . . . . . . . . . . . .. . . .. .. . .. 15 U . S . Elec tricity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
U.S. Electricity Generated by Commercial Nuclear Power ........................................ 23 ;
Worldwide Electricity Generated by Commercial Nuclear Power.............................. 26 Operating Nuc!ea r Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .j i
l U.S. Commercial Nuclear Power Reactors .............................................................. 30 Performance at U.S. Commercial Nuclear Power Reactors ....................................... 41 Future U.S. Commercial Nuclear Power Reac%r Licensing........................................ 44 U.S. Nuclear Nonpower Reactors .............. .............. .... ...... . ..... ... ........ .... ........ ... .... 50 Nuclea r Regulatory Research ............ . .. . ....... . .... .... ... .......... . ......... ........ . .. . . .... .... .... 52 l
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1997 INFORMATION DIGEST v '
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. L ;nmsmggyn Nuclear Material Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,
i i U.S. Fuel Cycle Facilities . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . .. .. . . . . . . . . . . . . .. . . . . . .
U .S. Mate rial Licen ses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .
l U.S. Nudear Material Transportation and Safeguards ............................................. 63 Intemational Nuclear Safety and Safeguards .......................................................... 64 Rad ioactive Wa ste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
U.S. Low-level Radioactive Waste Disposal ............................................................ 66 1
U.S. High-level Radioactive Waste Disposal .............................................. ........ ... 73 l 4
Decom m i s si on i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Append ices . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,
1 List of Abbreviations Used in Appendices ..................................................................... 85 A. U.S. Commercial Nuclear Power Reactors ............ ................................................. 86 B. U.S. Commercial Nuclear Power Reactors Formerly Licensed To Operate................100 C. Canceled U.S. Commercial Nuclear Power Reactors .............................................. 102 D. U.S. Commercial Nuclear Power Reactors by Licensee ........................................... 106 E. U.S. Nuclea r Nonpower Reactors . ... ...... .......... ......... ... . . .. . .. . ....... ... . .... ... .. ... ..... .. 108 F. NRC Performance Indicators: Annual Industry Averages .... .................................... I 11 G. NRC-Approved Dry Spent Fuel Storage Designs ................................... ............... 112 H. NRC Dry Spent Fuel Storage Licensees ................................................................. 113
- 1. World List of Nudear Power Reactors ............. ..................................................... I 14 f
l J. Nuclear Power Units by Reactor Type, Worldwide .......... ..................................... 115 K. Top 50 Reactors by Capacity Factor, Worldwide ................................................ .. I 16
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. 'J hiB M fLTLE2 L Top 50 Reactors by Generation, Worldwide ......................................................... 118 M. Quick Reference Metric Conversion Tables ........................................................... 120 Glossary...................................................................................................................123 Figures
- 1. U.S. Nuclear Regulatory Commission (NRC) Organization Chart ............................... 6
- 2. Map of N RC Region s . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 3. Distribution of NRC Fiscal Year 1997 Budget Authority and Staff .............................11
- 4. NRC Budget Authority, Fiscal Years 1 975- 1 997 . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2
- 5. NRC Personnel Ceiling, Fiscal Years 1 975-1 9 97 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3
- 6. Sources of NRC Fiscal Year 1997 Budget Authority........ ................... .................... 14
- 7. 1995 U.S. Electric Capability and Net Generation by Energy Source.......................... 17
- 8. Map of 1995 Net Electricity Generated in Each State by N udea r Power . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 9. U.S. Net Electric Generation by Source, 1 975- 1 995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20
- 10. U.S. Electric Generating Capability and Electricity Generated by Source, 1 9 8 6- 1 9 9 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 11. U.S. Average Nuclear Reactor and Coal-Fired Plant Production Expenses, 1 9 8 6- 1 99 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 12. Net Generation of U.S. Nuclear Electricity, 1 975-1 9 96 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24
- 13. 1995 Net Nuclear Electric Power as Percent of World Nuclear and Total Domestic Electricity Generation .................................................. 27
- 14. Diogram of a Typical Nuclear Reactor ......... ... ..................................................... 31
- 15. Map of U.S. Commercial Nuclear Power Reactors ..................... ............................. 32 (Continued)
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- 16. Map of NRC Region I Commercial Nuclear Power Reactors ........... ......................... 33
- 17. Map of NRC Region 11 Commercial Nuclear Power Reactors .................................... 34
- 18. Map of NRC Region 111 Commercial Nuclear Power Reactors ................................... 35
- 19. Map of NRC Region IV Commercial Nuclear Power Reactors ................................... 36
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- 20. Fiscal Year 1996 NRC Inspection Effort at Operating Reactors................................. 37 l i
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- 21. U.S. Commercial Nuclear Power Reactor Operating Licenses issued by Year..... ....... 39 l
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- 22. NRC Performance Indicators; AnnualIndustry Averages, 1985-1996 ... .................. 42
- 23. U.S. Commercial Nudear Power Reactors-Years of Operation ............................... 45 I i
- 24. U.S. Commercial Nuclear Power Reactor Operating Licenses-Expiration Date by Year Assuming Construction Recapture ...................................... 47
- 25. U.S. Commercial Nuclear Power Reactor Generating Capacity, 1960-2060 ............ 48
- 26. Map of U.S. Nuclear Nonpower Reactor Sites ........................................................ 51
- 27. Research Budget Trends, FY 1 975- 1 9 97 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 28. Map of Major U.S. Fuel Cycle Facility Sites ............................................................. 58
- 29. Map of N RC Agreement States .. ...................... ....... .......... ..... . ........ .. . .... ........ ..... .. 61
- 30. Diagram of Materials Licensing Business Process Redesign....................................... 62
- 31. Diagram of a low-level Waste Disposal Site .......................................................... 67
- 32. 1995 Volume of low-Level Radioactive Waste Received at U . S . Disposal Faciliti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 33. Volume of low-level Waste Received at U.S. Disposal Facilities, l 1984-1995........................................................................................................69 l
l 34. Radioactivity of low-level Waste Received at U.S. Disposal Facilities, l 1984-1995.........................................................................................................70 viii NUCLEAR REGULATORY COMMISSION
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- 35. Map of U.S. Low-level Waste Compacts ................................................................ 72
- 36. Diagram of the Yucca Mountain Storage Plan ......................................................... 74
- 37. Diagram of a Nuclear Fuel Siorage Pool ................................................................ 75 j 38. Diagram of the Storage of High-level Radioactive Waste ........................................ 76
- 39. Operating Independent Spent Fuel Storage Installations .......................................... 79 Tables
- 1. NRC Budget Authority, Fiscal Years 1 975- 1 9 97 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 2. NRC Personnel Ceiling, F' scal Years 1 975- 1 997 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I
, 3. 1995 Electric Generating Capability and Electricity Generated in Each State by Nuclear Power ............................................................ 18
- 4. U.S. Net Electric Generation by Source, 1 975- 1 995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20
! 5. U.S. Electric Generating Capability by Source, 1986-1995 . . . . . .. . . . . . . . . ... . . . . .. .. . . . . .. . .. . . 21 j 6. U.S. Average Nuclear Reactor and Coal Fired Plant Production Expenses, 1 9 8 6- 1 995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2 7. U.S. Commercial Nuclear Power Reactor Average Capacity Factor and Net Generation, 1 975- 1 9 96 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4
- 8. U.S. Commercial Nuclear Power Reactor Average Capacity Factor by Vendor and Reactor Type, 1 994- 1 996 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 9. 1996 Commercial Nuclear Power Reactor Average Gross Capacity Factor and Gross Generation by Selected Country ............................ ..................... 28
- 10. Commercial Nuclear Power Reactor Average Gross Capacity Factor by Selected Country, 1 9 8 6- 1 9 9 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 11. U.S. Commercial Nuclear Power Reactor Operating Licenses i s s ued by Yea r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
(Continued)
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- 12. U.S. Commercial Nuclear Power Reactor Operating Licenses-l Expi ration Date by Yea r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 13. U.S. Mc'erial Licenses by State .......... ...... ....... .... ..... . ......... .. .... ...... ... ..... ... .. .......... 60
- 14. U.S. Low-level Wa ste Compacts ........ . ..................... ..... .. ... ................ ... ...... ... ... ..... 71
- 15. Spent Nuclear Fuel Stored at U.S. Commercial Nuclear Power Reactors-Total Metric Tons by State ................... ................... .. .... . .. ............... ........ 78
- 16. Site Decommissioning Management Plan Site List ............................ ....................... 81 i
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ii For More information...
& U.S. Nudeor Regulatory Commission available for sole at both the Government (NRC) offers a variety of programs to make Printing Office and the National Technical agency, licensee, and nudear indestry infor- Information Service. Copies of agency publi-motion available to the public. b ogency cations are also routinely sent to U.S. Deposi-maintains a Public Document Room (PDR) in tory Libraries throughout the United States and Washington, D.C. that provides for the public the Commonwealth of Puerto Rico.
a com arehensive collection of over 2 million aublic y released documents related to NRC h NRC announces the schedules of selected icensing proceedings, rulemaking activities, meetings open lo the public. Recorded infor-ond the setting of polic/ for nucleor regulation motion about open meetings of the following in the United States. h PDR suppods access organizations is available at the ogency to these documents by the public anywhere in headquarter's numbers listed below.
this country or oversoos via various electronic Advisory Committee on Nuclear Waste systems, mduding on online search and (301)415-5024 retrieval capability and a bulletin board for selected meeting announcements, documents, Advisory Committee on Reactor Safeguards etc. For further information, telephom (301)415-5024 (202) 634-3273 or toll free (800) 397-4209; Internet e-mail to pdr@nrc. gov; telefox to The Commission (202) 634-3343;or write to the PDR, (301)415-1292 U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. NRC/ Department of Energy Meetings (800)841-0286
& NRC has also established local Public Information on NRC staff meetings open to Document Rooms (LPDRs) near the siM of each commercial nuclear power reactor, the pro- Public observation, induding those of the posed high-level waste repository, and certain Offices of Nudear Material Safety and fuel cycle facilities, h (PDR collections Safeguards, Nuclear Reactor Regulation, consist of publicly available documents about and Nuclear Regulatory Research, and the the facility, including hearing transcripts, regional offices, is announced on a toll-free safety evaluation reports, environmental telePh one recording at (800) 952 9674 and impact statements, and inspection and lic. on a toll-free electronic bulletin board at ensee event reports b power reactor and (800) 952-9676 or (800) 303-9672 (access high-level waste LPDRs also maintain a micro. through GATEWAY).
fiche file of most documents mode publidy Open Predec. .isional Enforcement Confer-available by the NRC since 1981, in addition ences re Is nnwnced n the toMee to those about the nearby nuclear fccility.
telephone recording and electrom,e bullet,in The agency makes the majority of board as are public Commission and its regulatory and technical publications fContinued) n - -.
1997 INFORMATION DIGEST xi
1 y;;yvgygggggy l For More Information (continued) i Advisory Committee meetings and Atomic a program to receive and respond to these Safety and licensing Board hearings that are types of inquiries. To help small entities published in the Federal Register. A daily obtain information quickly, the NRC has posting of upcoming open meetings is also established a toll-free telephone number at l available on the NRC World Wide Web at (800)368-5642.
www.nrc. gov /nrc/public/ meet.html.
To learn more about these and other sources The NRC is required to answer inquires from of public information about agency activities,
, snall entities concerning information on, send for a free copy of the booklet, " Citizen's advice about, and compliance with the Guide to U.S. Nuclear Regulatory Commis-statutes and regulations that affect them. The sion Information" (NUREG/BR-0010, Rev. 2),
NRC is expected to interpret and apply the at the following address: U.S. Nudear law, or regulations implementing the law, to Regulatory Commission, ATIN: Printing, specific sets of facts that are specified by the Graphics and Distribution Branch, small entity. The NRC is required to establish Washington, DC 20555-0001.
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Mission and Statutory Authority The mission of the U.S. Nudear Regulatory
- Uranium MillTailings Radiation Control Commission (NRC)is to regulate the Act of 1978, as amended l Nation's civilian use of byproduct, source, and special nuclear materials to ensure
- Nudear Non Proliferation Act adequate protection of public health and of 1978 safety, to promote the common defense and .
security, and to protect the environment.
- Low-level Radiocctive Waste Policy Act The NRC's scope of responsibility includes of 1980 regulation of commercial nuclear power plants; research, test, and training reactors;
- West Valley Demonstration Project Act fuel cycle facilities; medical academic, and of 1980 i industrial uses of nudear materials; and the transport, storage, and disposal of nudear
- Nudear Waste Policy Act of 1982 materials and wastes.
- Low-level Radioactive Waste Policy )
The NRC was created as an independent Amendments Act of 1985 agency by the Energy Reorganization Act of l 1974, which abolished the Atomic Energy
- Diplomatic Security and Anti Terrorism l Commission (AEC) and moved the AEC's Act of 1986 regulatory function to the NRC. This act, along with the Atomic Energy Act of 1954,
- NuclearWaste Policy Amendments Act as amended, provides the foundation for of 1987 regulation of the Nation's commercial nudear power industry.
- Solar, Wind, Waste and Geothermal Power Production incentives Act of 1990 NRC regulations are issued under the United !
States Code of federal Regulations (CFR)
- Energy Policy Act of 1992 Title 10, Chapter 1. Principal statutory l authorities that govern NRC's work are: The NRC and its licensees share a common l responsibility to protect public health and
- Atomic Energy Act of 1954, safety. Federal regulations and the NRC as amended regulatory program are important elements in the protection of the public. NRC licens-
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- Energy Reorganization Act ees, however, have the primary responsibility of 1974, as amended for the safe use of nudear materials.
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2 NUCLEAR REGULATORY COMMISSION t
NRC AS A REGULATORY AGENCY T M Wl M E!@
~
Principles of Good Regulation The NRC adheres to the following Principles must be a constant agency goal. NRC of Good Regulation: must establish means to evaluate and
! continually upgrade its regulatory capa-
- Independence - Nothing but the highest bilities. Regulatory activities should be possible standards of ethical performance consistent with the degree of risk reduction ,
and arofessionalism should influence they achieve. Where several effective regu ation. However, independence does alternatives are available, the option l not imply isolation. All available facts and which minimizes the use of resources opinions must be sought openly from should be ado 3ted. Regulatory decisions
! licensees and other interested members of should be mace without undue delay.
the public. The many and aossibly con-I flicting public interests invo ved must be
- Clarity - Regulations should he coherent, considered. Final decisions must be bcsed logical and 3ractical. There should be a on objective, unbiased assessments of all clear nexus aetween regulations and information, and must be documented with agency goals and objectives whether reasons explicitly stated. explicitly or implicitly stated. Agency positions should be readily understood
- Openness - Nuclear regulation is the and easily applied.
public's business, and it must be trans-acted publicly and candidly. The public
- Reliability - Regulations should be based must be informed about and have the on the best available knowledge from opportunity to participate in the regula- research and operational experience.
tory processes as required by law. Systems interactions, technological uncer-Cpen channels of communication must tainties, and the diversity of licensees and be maintained with Congress, other regulatory activities must all be taken into government agencies, licensees, and the account so that risks are maintained at an l public, as well as with the international acce stably low level. Once established, nuclear community. regu ation should be perceived to be reliable and not unjustifiably in a state of l
- Efficiency - The American taxpayer, the transition. Regulatory actions should l rate paying consumer, and licensees are always be fully consistent with written all entitled to the best possible manage- regulations and should be promptly, ment and administration of regulatory fairly, and decisively administered so as activities. The highest technical and to lend stability to the nuclear operational managerial competence is required, and and planning processes.
. .. ,e -ammeowu wn 1997 INFORMATION DIGEST 3 1
I l n aMWamE3m?n !
Major Activities The NRC fulfills its responsibilities through a
- Developing and implementing rules and system of licensing and regulatory activities regulations that govern licensed nuclear that include: activities l
l
- licensing the construction and operation
- Investigating nudear incidents and alle-of nuclear plants and other nuclear facili- gotions concerning any matter regulated I ties, such as nuclear fuel cycle facilities by the NRC and test and research reactors, and ,
1 overseeing their decommissioning
- Enforcing NRC regulations and the condi-tions of NRC licenses
- licensing the possession, use, processing, handling, and export of nudear material
- Conducting public hearings on matters of nudear and radiological safety, environ- ,
- licensing the siting, design, construction, mental concern, common defense and l l operation, and closure of low-level radio- security, and antitrust matters active waste disposal sites under NRC jurisdiction and the construction, opera-
- Developing effective working relation-tion, and dosure of the geologic reposi- ships with the States regarding reactor tory for high-level radioactive waste operations and the regulation of nudear material
- licensing the operators of nudear power and test and research reactors
- Maintaining the NRC incident Response Program, induding the NRC Operations e inspecting licensed facilities and activities Center
- Conducting the principal U.S. Govern- a Collecting, analyzing, and disseminating ment research program on light-water information about the operational safety reactor safety of commercial nuclear power reactors l and certain nonreactor activities
- Conducting research to provide indepen-dent expertise and information for mak-l ing timely regulatory judgments and for anticipating problems of potential safety
, significance I
i 4
l 4 NUCLEAR REGULATORY COMMISSION
NRC AS A REGULATORY AGENCY
.;wyggggga Organizations and Functions The NRC is headed by five Commissioners and developing technical regulations oppointed by the President and confirmed by and standards the Senate for 5 year terms. One of them is rational des,ignated by the President to be the Cha,ir-
- Analysis and Evaluation of O[dissemi-Data - Collects, analyzes, an man, serving as the pnna, pal executive officer nates information about the operational and official spokesperson of the Comm,ission, safety of commercial nuclear power The Executive Director for Operations carries reactors and certain nuclear material out the pohaes and deas, ions made by the activities, and manages the NRC's inci-Comm,ssion.
i The NRC s offices assoaated dent Response Program and the NRC's !
with Regulato:y Programs are:
TechnicalTraining Center
- NuclearReactorRegulation-Directsall
- Office of Enforcement - Directs all hcensin and inspection activities assoa-enforcement activities associated with ated wi the design, construction, and NRC licensees operation of nuclear power reactors and nonpower reactors Other major offices are:
- Nuclear Material Safety and Safeguards -
- Office of Investigations - Conducts investi- l Directs all licensing and ins section activities gations of allegations of wrongdoing by I associated with nuclear fue cycle facilities, NRC licensees uses of nuclear material, transport of
- Office of the Chief Financial Officer-nuclear material, safeguarding of nuclear Responsible for agency-wide financial material, management and disposal of low. ,
Pl anning, poh,cy, operat, ions and systems level and hich-level radioactive nudear waste, and iecontamination and decom-
- Officeof theChiefInformationOfficer-missioning of facilities and sites Responsible for the strategic use of infor- j m tion technology as a management tool j
- R ionalOffices-Conductinspection, cr ss spectrum of agency activities and en rcement, investigation, licensing,and emergen response programs for nuclear f r n gency-wide opproach to informa-reactors, el facilities, and materiallicens- ti n m n gement, cap, ital planning and Perfonnance4ased management of infor- j ees within regional boundaries that the headquarters offices originate
- II " Ch" l agementice serv? unctions cy, nd ini rm tion m i
- State Programs - Establishes and maintains I communication with State and local govem.
- Inspector General-i Prov. des the is- Comm. !
ments and administers the Agreement sion with an independent review and States Program. 9PPraisalof NRC pr ms and ro-tions to ensure the,ir e iveness, e i- ,
Offices associated with Regulatory Effectiveness ciency, and integrity l include: !
The Nuclear Regulatory Commission 1995 !
- Nuclear Regulatory Research - Prov. ides I Annual Report" (NUREG-1145, Volume 12) independent expertise and information for arovides additional information regarding malang timely regulatory judgments,
, 4RC offices and their functions. i antiapating problems of potential safety Figure 1 is an organization chart of the NRC. ;
significance, and resolving safety issues
_ =_m----
1997 INFORMATION DIGEST 5 I
i
.. : , , (:b ^l - ,
f k j Figure 1. U.S. Nuclear Regulatory Commission (NRC)
The Chairman l
The Commissioners lE i l e
q
! I57
. Com e on Atomic Sa%
Committee on
- and B rd Pane b,censinf j
Nuclear Waste ; gfords i
fi f Co ss n I ' b* Officeof the Executive Director
' ' *5 "5' Ad oion
! l l Assistant for Deputy Executive Director for Operations l Regulatory Effectiveness l
i
!4 l _
{
Office of Nuclear Office for Analysis and Office of Office of l
T ce of Nuclear Regulatory Reacbr
- Evaluation of Investigations Enforcement Research Regulohon atimal%
m **
a i
4
. Direct Supervision l
= = = - Coordination j .
- wwws . , j 6 NUCLEAR REGULATORY COMMISSION
NRC AS A REGULATORY AGENCY
.: . . ;segggggggggge ChiefInformation Chief Financial Officer Officer
- _ _ , _ Officeof the Inspector General Office of Information Officeof the Resources Controller Management Office of o((;c,o[
Congrosional Public Affairs Affairs Il i I Deputy Executive Director for Deputy Executive Director for l Regulatory Programs Management Services 1mummemmmmmmmm Office of t ,ffice f Office of Office of Material Safet SmallBusiness Officeof Nuclear and Safeguor s StPi e rograms I Administrah,on I I Penennel and Civil Rights Region i Region ll Region 111 Region IV Philadelphia Atlanta Chicoge .
Dollos I
.- - -- - .a.,. , ,. n ,, ,
1997 INFORMATION DIGEST 7
i P
w pg w wgggggggg t
NRC Locations
! Headquariers: Operations Center:
Rockville, Maryland Rockville, Maryland l (301)415-7000 (301)816-5100 The NRC maintains an Operations Center that provides a focal point for NRC communica-tions with its licensees, State agencies, and other Federal agencies concerning operating events in the commercial nuclear sector. The Operations Center is staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day by NRC operations officers.
i Regional Offices:
The NRC has four regional offices Region Ill located throughout the United States Lisle, Illinois (see Figure 2): (630)829-9500 Region I Region IV King of Prussia, Pennsylvania Arlington,lexos (610)337-5000 (817)860-8100 l Region Il RegionIVFieldOffice:
Atlanto, Georgia Walnut Creek, California (404)562-4400 (510)975-0200 l
Resident Sites: TechnicalTraining Center:
l Atleast two NRC residentinspectors Chattanooga, Tennessee
! who report to the appropriate regional (423)855-6500 office arelocated at each nudear power reactor site. Refer to Figure 15 for a map of the U.S. commercial nuclear power reactor sites.
I i
. - wm.e 8 NUCLEAR REGULATORY COMMISSION l
l
NRC AS A REGULATORY AGENCY
.' . JJ.;M42G?B3755%29 Figure 2. NRC Regions REGION IV REGION lll WA N NH MN A MT ND REGION I (ME OR WI ID SD (ie MI NY ;- MA WY IA i Ri
' NE lt IN g NV j [A NJ UT CO MO -
L_ VA g
K M NM AR a NC TN
- b. e e SC g MS Al GA REGION ll FL e RegionalOffice(4) m Technical Training Center (1)
A Field Office (1)
L1 Headquarters (1)
Note: Alaska and Hawaii are included in Region IV.
Source: Nuclear Regulatory Commission
....v,,-..,..,n.~.,.,,..+.- ....
1997 INFORMATION DIGEST 9
w?mmmm NRC Fiscal Year 1997 Resources Appropriation:
l The NRC was appropriated $476.8 million
- Reactor for Fiscal Year (FY) 1997. The NRC's FY
- Nuclear Materials and l
1997 personnel ceiling is 3,061 full-time equivalent (FTE) staff.
Nuclear Waste M n g mentand Support The NRC allocates funds and staff to the following programs (see Figure 3):
- InspectorGeneral(IG) l l
Civil Penalties:
The NRC's enforcement program supports significant violations to Severity level IV for the agency's overall safety mission in protect- those less serious. Civil penalties are con-
- ing the public and the environment. Consis- sidered for Severity level ill violations and tent with that purpose, enforcement action is are normally assessed for severity Level l used as a deterrent to emphasize the impor- and 11 violations and knowing and conscious tance of compliance with regulatory require- violations of the reporting requirements of ments, and to encourage prompt Section 206 of the Energy Reorganization l identification and prompt, comprehensive Act. The NRC imposes different correction of violations. The NRC enforce- levels of civil penalties based on a combino-ment program is governed by the NRC tion of the tya of licensed activity, the type Enforcement Policy, published as NUREG- of licensee, t 3e severity level of the violation, l
1600. Three primary enforcement sanctions and other criteria induding identification, are available: Notices of Violation; civil corrective action, and discretion.
penalties; and orders to modify, sus aend, or in FY 1996, approximately $3.0 million in revoke licenses. The NRC ranks vio ations civil penalties was paid. These civil penal-according to their level of severity. Severity ties are deposited in the U.S. Treasury and levels range from Severity level i for the most are not used by the NRC.
2 J
___.__..._,w_...+.#._;..._+wm.,,
l 10 NUCLEAR REGULATORY COMMISSION
i NRC AS A REGULATORY AGENCY
- 1;@RT&EWM
~
Figure 3. Distribution of NRC FY 1997 Budget Authority and Staff l (Dollarsin Millions) t' - "'
i
.i
. +A,# d. dn,af.vQ:nM 7 4 4A 4m t- ;fM- .f:ple "k .t T W :T J,.-i v. *
~ . 'J..!.9. uv v;. ,.
+ ~ r:. +q;. m.,;.'.; . ,s,
- c. . , . p
- m. w; ..: .
m y.. :4, . . ,. . ,. ,. .. .. . . . -
. .; m Total Authoritr
$476.8 Million i
- DOLLARS BY PROGRAM i
h i
,, W44
,_ gyj. s
, fi' y
- 7+<'.,.p.W. .;tg'{pj p ,,
.A,m..
. .gf' ).%f:n c, . -i' Qc ...t:.a.3 ,, ; ;.p;u;.g4.
- P
,}f{ (Tl:y.'W ' ;?. ,A$z ,, .Q ,
,JJ[. W, O!l,,b'[ ] d_M d+ D.:n f.. L'i.!Md .
INSPECTOR j GENERAL s.?.'6INQ.g;%gQE[ th i .. O # ' 4 *~.* *** A'.T - (43)
, y a:_ 3 3 :
. .. . 2,,. ;.. .
- / . v. . < - _. m" w,. ,e ;g ...
'2 -Typ:1 .,. : .
- 7,
- ;.5 ;Ag.g._'. S.;; pp 7Q$; , . .. .l'g p .;.
i f.
Q., ,
,a::c ; .;. . ,
.. . ., ... . ,a .
s l
I STAFF BY PROGRAM i
.t f I.
i k 9fW
- h %; 4 m% &y Ey;;M %y D aY'$w $(, n. Q .%.
9.f.p(h.hJ!&l1fWm..nNiA'L:
Mk..
y .p
'+ J: -
^M RESIDENTINSPECTORS
%.W .,4 gJ. ,g.K7cq:;.4 4 * ;* jy &jgy'w m. o.%,, (181) s,{g.c.,4.. g,s $:r. n.g:;t 4 W .
a 6%
8.. .Yp . . % c.A gf:
'hk . yff.Q,,. s . -kfhh Q74y.y Total Staff:
- Aldjg.g(h g%@#J A' 3,061 FTE 4
+
STAFF BY LOCATION i
- Note
- Percentages are rounded to the nearest whole number.
Source: Nuclear Regulatory Commission l
i i 1997 INFORMATION DIGEST 11
. 7.(p y:;;yy gggyggyp Table 1. NRC Budget Authority, FYs 1975-1997 (Dollars in Millions)
Fiscal Actual Fiscal Actual Year Dollars Year Dollars 1975 135 1987 401 1976 270 1988 393 1977 249 1989 420 1978 290 1990 439 1979 327 1991 465 l 1980 399 1992 513 1981 441 1993 540 1982 466 1994 535
- 1983 465 1995 524 1984 466 1996 473 1985 444 1997 477 1986 400 Figure 4. NRC Budget Authority, FYs 1975-1997 DO!LARS IN MILLIONS 600 1 T 500 3 4 j 7
I . O i
j j .
1 ll 3 ,?
4w k '4
? .
/ ?a e 9J 9 5
.t :. 6 t 7 ij j m g q
. jj y er @ 0
{
$ g$ i !.:
3m
) i y !l [ $ i q ii ) ;
, 7 g y1V ) ]0 ii i
a
? ; k 4 Iq i s U 4- > 3 2 200 i 4, y 4 $,
j{ j a j r j
3 a , 7 a *
( $ K pp l j s 4 5 : :. # w w .
': > c-
., %- i;j 3 100 g a b; M d 4 6 F '
4 9 3
- j, ,
}
0 1975 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 1997 FISCAL YEAR l
l Note: Dollars are rounded to the nearest million.
Source (Table 1 and Figure 4): Nudear Regulatory Commission
- =-wrnau.a.annm 12 NUCLEAR REGULATORY COMMISSION
NRC AS A REGULATORY AGENCY MF.MGESGMs Table 2. NRC Personnel Ceiling, FYs 19751997 Fiscal Year Staff Fiscal Year Staff 1975 2,006 1987 3,369 1976 2,339 1988 3,250 1977 2,529 1989 3,180 1978 2,723 1990 3,195 1979 2,888 1991 3,240 1980 3,066 1992 3,335 1981 3,300 1993 3,343 1982 3,325 1994 3,293 1983 3,303 1995 3,218 1984 3,416 1996 3,160 1985 3,491 1997 3,061 1986 3,491 Figure 5. NRC Personnel Ceiling, FYs 1975-1997 STAFF 4000 c c 3500
a
. . ?, - m 5 3000 k_ ) $ h f P 7
2500 1 R
i f
N i
q t
s !g e
- 4 i
h F
i e g
i
- d. 1 3
2 j d 0
N 0 j j f
?b f 5 N 0 L k h $ i ??
2000 a lA 3
- y
,3 p
?
y
( -
e s W ;u r g
- y e
d E
$ 3 fi
< e 3 j
s < :
j li 1500 ? j ! j j g } {3 f f, 4 4, f {
a l a j b >
4 2 a .-
j s-1000 j ll 4 g j q p / #
, i g 9 ll (
( i
? g, @
1500 jg" 1 3
a a
4 n
l (e
[;
h j
k
[
f f 1 S j d
J l] 3 4
j i
W l 1 e
a 3
1
% G
?
n
$]
a
- ;t
- h 3
y ?
4 i y o 6 0
l 1975 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 1997 FISCAL. YEAR l
Note (Table 2 and figure 5): FY 19751982 data reflect permanent full time positions, at end-of year j strength. FY 19831997 reflect full-time equivalents (FTE).
( Source (Table 2 and Figure 5): Nuclear Regulatory Commission 1997 INFORMATION DIGEST 13
1 1
. 39gggggy
- Figure 6. Sources of NRC FY 1997 Budget Authority l
,i 1
,, .gD;(' ypm..gqup *[.l.[:;ll'L'[.Q[ w,.., f% .
. ;;kl4?f*,;Q [ ',w ' L:l :' ? :' ;; J ; . . e , ': .k;:. 3:,[,.
~
f.^; f:l:: f : ; i.7. .;' '-
- . %l.L:)':; ql _ _
Y f ;,
s..
- y... .
r . . -
- 7. ... , g;g j [j ., ' i ' . ' f ; S; ,,. V r
.7LM NUCLEAR MATERIAL FEES i
.'lf.fh.
'f ' k:. .4 c ,~ - - w ~, n
~
$ E. . ji ! ($60.3)
- .c .
4 y;' . - . .
13%
- . -: .o . . ~
GENERAL FUND
' ~
. . . ($3.5)
(1%)
4 NUCLEAR WASTE FUND DOLLARS IN MILUONS ($11.0) n Total Authority:
$476.8 Million 4
l The Omnibus Bud et Reconciliation Act of 1990, as amended requires the NRC to recover l 100 percent of its udget authority, less appropriatians from tbe Nuclear Waste Fund, for FYs 1991-i 1998 by assessinc fees to its licensees. In FY 1997, the NRC budget authority to be recovered from fees is $462.3 milion. The fees assessed to the major classes of NRC licensees in FY 1997 are:
)
i Class of Licensee Range of Annual Fees
- Operating Power Reactor $2,972,000
- Fuel Facifity $647,000 to 4,000 Uranium Recovery Facility $22,300 to u ,oa0
! Transportation Approval $1,000 to $76,700 Materials User $490 to $23,500 i
i Note: Percentages are rounded to the nearest whole number.
Source: Nucloor Regulatory Commission
. _ . -~~ a--s>. n 14 NUCLEAR REGULATORY COMMISSION
--mm U.S. and Worldw'de Energy
-~n $Y A
% -.n- j;.f8addgg[ e ~-
%pagg igsms / g.,d.
epwa ghu a n.- u .i.pgh ~yf m 'I an s ~. ' y :1,,
! f ' f,
.~
h Aw$i
- BI
g ,a. {$y$nw$$g(Whid'EN u %e#(f.9f,1,y
,m,s ys3 "-
Y %,
ydifl;47 e R$ wxhn -
A ., .r .ypug'Q U;}a; g j$'a 5 ksasJgif
'It+k'[by~
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[',a6;d;fg,g g-
_ g ~w . . a jk s, d8 .
4 e f Q+ ~
d e
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i 1
l I
I I
l wwa-a - - .;m.-vr:.s.sevm...
O f M 3 r d F;Ty F I $ 2 6 E n
- U.S. Electricity Capability and Net Generation: Since 1975, nuclear electric generation has more than tripled and coal-fired generation U.S. electric generating capability totaled has almost c'aubled, while electricity gener-approximately 706 gigawatts in 1995. ated by all other sources has decreased by Nuclear energy accounted for approximately 26 percent (see Table 4 and Figure 9).
14 percent of this capability (see Figure 7).
Electricity from coal and nudear sources, U.S. net electric generation totaled approxi- which accounted for 57 percent of the U.S.
mately 2,994 thousand gigawatthours generating capability, produced 77 percent in 1995. Nuclear energy accounted for of the net electricity generated in 1995 approximately 22 percent of this generation (see Table 5 and Figure 10).
(see Figure 7).
Average Production Expenses: ,
in 1995,109 operating nudear reactors in !
32 States generated approximately one-fifth The production expense data presented i 2
of the Nation's electricity (see Table 3 and here include all nudear and coal-fired utility- I Figure 8). owned steam electric plants (see Table 6 and Figure 11).
- 6 States relied on nudear power for more )
than 50 percent of their electricity.
- In 1995, production expenses i averaged $19.23 per megawatthour
- 13 additional States relied on nuclear for nudear reactors and $18.75 per power for 25 to 50 percent of their megawatthour for coal fired plants.
electricity.
I
- , _ ~ - - , . _ . -
^^ '
$ k$ Y n' N 16 NUCLEAR REGULATORY COMMISSION
i l
U.S, AND WORLDWIDE ENERGY l
.... . . mgggggggggy l Figure 7. 1995 U.S. Electric Capability and Net Generation by Energy Source
.a
- y. j;p y w _ ,
> HYDROEECTRIC I PETROEUM - :' ,E & ?4 t 1 97) dp:
/5 lih ,' e I e - as % ._ %)
a 4
TotalCapabilitf:
706 Gigawatts CAPABETY
- i
- ~ - - -
,,, .. PETROEUM N ;
()
e" HYDROEECTRIC F (294) 10%
~
i e
i Total Generation":
(0) GENERATION 2,994 Thousand Gigawatthours 10%
l d
- Total value includes op aroximately 2 gigawatts of other ger<erating capability (geothermal, refuse,
- solar, wind, and wood?, which represents less than 1 percerit of total capability.
" Total value includes approximately 6 thousand gigawatthouis of generation by other energy sources (biomass fuels, wood, wind, photovoltaic, and sofor), which represents less than 1 percent of total
! generation.
Note: Net summer capability. Percentages are rounded to the nearest whols number.
Source: DOE /EIA Inventory of Power Plants in the United States 1995 (DOE /EIA-0095 (95)), Table 1 (page 19) and DOE /EIA Monthly Energy Review (DOE /EIA-0035 (96/11)), Table 7.1 (page 95) 1997 INFORMATION DIGEST 17
1-l7 J A. g s G g igjg g g E Table 3. 1995 Electric Generating Capability and Electricity Generated in Each State by Nuclear Power Percent Net Nuclear Percent Net Nuclear Stole Capability Generation State Capability Generation l Alabama 24 21 Missouri 7 12 Arizona 25 39 Nebraska 23 31 i Arkansas 18 31 New Hampshire 46 62 California 10 24 New Jersey 28 65 Connecticut 48 64 New York 15 23 Florida 11 21 North Carolina 23 38 Georgia 17 30 Ohio 7 12 l Illinois 38 54 Pennsylvania 27 39 lowo 6 10 South Carolina 38 62 Kansas 12 26 Tennessee 14 21 Louisiana 12 25 Texas 7 13 Maine 36 10 Vermont 46 79 Maryland 15 28 Virginia 24 46 Massachusetts 7 15 Washington 5 6 Michigan 18 26 Wisconsin 13 22 Minnesota 18 30 Others' 0 0 Mississippi 16 25
- There are 18 States with no nudear generating capability.
Note: Net summer capability. Capability is the percent of electricity the State is capable of producine with nuclear energy. Generation is the percent of all sources of electricity actually produced with nuc: ear energy. Percentages are rounded to the nearest whole number.
Source: DOE /EIA Inventory of Power Plants in the United States 1995 (DOE /EIA-0095 (95)), Table 17 (page 33) and DOE /EIA Electric Power Monthly (DOE /EIA 0226 (96/11)), Tablu 12 (page 24)
_ _.__ _m _ s c ,_ u .. , . .
18 NUCLEAR REGULATORY COMMISSION
1 U.S. AND WORLDWIDE ENERGY
.. ;. n.g;ygagsgggggy Figure 8. 1995 Net Electricity Generated in Each State by Nuclear Power i
! NH'
! MT i
ND
WY sp; CT NV NJ i IN DE MD CO KY l
i NM OK
(
I E More than 50%(6)
E 25% to 50%(13)
I
@ 1% to 24% (13)
C None(18)
)
Note: There are no commercial reactors in Alaska or Hawaii. Percentages are rounded to the nearest whole number.
Source: DOE /EIA Electric Power Monthly (DOE /EIA-0226 (96/11)), Table 12 (page 24) 1997 INFORMATION DIGEST 19 l
- .n v j g gggi g ygig Table 4. U.S. Net Electric Generation by Source,1975-1995 (Thousand Gigawatthours)
Year Cool Petroleum Gas Hydroelectn*c Nuclear 1975 853 289 300 300 173 1976 944 320 295 284 191 1977 985 358 306 220 251 1978 976 365 305 280 276 1979 1,075 304 329 280 255
. 1980 1,162 246 346 276 251 1981 1,203 206 346 261 273 1982 1,192 147 305 309 283 1983 1,259 144 274 332 294 1984 1,342 120 297 321 328 1985 1,402 100 292 281 384 1986 1,386 137 249 291 414 1987 1,464 118 273 250 455 4
1988 1,541 149 253 223 527 1989 1,554 158 267 265 529 1990 1,558 117 264 280 577
- 1991 1,549 111 264 276 613 1992 1.576 89 264 240 619 1993 1,639 100 259 265 610 1994 1,635 91 291 244 640 1995 1,653 61 307 294 673 Figure 9. U.S. Net Electric Generation by Source,1975-1995 THOUSAND GIGAWATTHOURS 1800 1600
,.. ___.. ~-~~*
1400 COAL. ,
1200 - < -
~ '
,,.<.T.'. .~
800 ......* ' ALL OTHER SOURCES
.......... .. ..... ,,.. -....... ._f NUCLEA 200 #
0 1975 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 1995 YEAR Source (Table 4 and figure 9): DOE /EIA Monthly Energy Review (DOE /EIA-0035 (96/11)),
Table 7.1 (page 95)
_ - - - mmov,--~. ,
20 '
NUCLEAR REGULATORY COMMISSION
} U.S. AND WORLDWIDE ENERGY x;: M BRE g;ggggy l Table 5. U.S. Electric Generating Capability by Source,1986-1995
' (Gigawatts)
Year Cool Petroleum Gas Hydroelectric Nuclear i 1986 290 78 117 89 85 i 1987 293 76 118 90 94 l 1988 295 77 116 90 95 1989 297 78 117 90 98 1990 300 77 120 91 100 1991 300 72 126 92 100 l
1992 301 72 127 93 99
- 1993 301 70 132 96 99 j 1994 301 70 134 96 99 l 1995 301 64 142 97 100 i Figure 10. U.S. Electric Generating Capability and Electricity i Generated by Source,1986-1995 l
l PERCENT PERCENT CAPABluTY BY SOURCE GENERATION BY SOURCE l 120 120 100 100 i
! 80 80 .
1 l
60 60 .
i D
40 40 $
4
. 20 20 I
0 0
. 1986 87 88 89 90 91 92 93 94 1995 1986 87 88 89 90 91 92 93 94 1995 YEAR YEAR l
. E OTHER O COAL 0 NUCLEAR E OTHER 52 COAL O NUCLEAR 4
Note (Table 5 and figure 10): Net summer capability. Percentages are rounded to the nearest i whole number, j Source (Table 5 and figure 10): DOE /EIA Inventory of Power Plants in the United States 1995 (DOE /
Table 7.1 (page 95)
. . . . ..... __..- .mmum _,,,
1997 INFORMATION DIGEST 21
l l
Table 6. U.S. Average Nuclear Reactor and Cool Fired Plant Production Expenses, 1986-1995 (Dollars per Megawatthour) !
Operation Total 1 and Production '
Year Maintenance Fuel Expenses Nuclear: I i 1986 12.84 7.56 20.40 j 1987 14.04 7.73 21.77 1988 14.19 7.89 22.08 1989 15.05 7.40 22.45 1 1990 14.65 7.24 21.89 I 1991 14.72 6.75 21.47 !
l 1992 15.35 6.24 21.59 1993 15.26 6.02 21.28 1994 14.01 6.02 20.03 l 1995 13.49 5.74 19.23 !
Cool-Fired: 1 1986 4.25 17.31 21.56 1987 4.14 16.45 20.59 l 1988 4.12 15.84 19.96 1989 4.07 15.70 19.77 l
! 1990 4.30 15.84 20.14 .
1991 4.39 15.85 20.24 I 1992 4.33 15.37 19.70 l
1993 4.32 15.31 19.63 :
1994 4.32 14.88 19.20 1 1995 4.24 14.51 18.75 Figure 11. U.S. Average Nuclear Reactor and Coal Fired Plant Production 1 Expenses,1986-1995 NUCLEAR COAL FIRED 40 DOLLARS PER MEGAWAlTHOUR 40 DOLLARS PER MEGAWATTHOUR ,
I t 30 30 ,
1
. 20 p ;: g p.
10 10 fj .] k- f] .
l 0 0 1986 87 88 89 90 91 92 93 94 1995 1986 87 88 89 90 91 92 93 94 1995 j YEAR YEAR ,
l ration and a Fuel ration and D Fuel 3 gintenance E gintenance j
Note (Table 6 and figure i l): Costs have not been adjusted to reflect inflation. l l Source (Table 6 and figure i l): Utility Data institute, Inc.,1995 Production Costs Operating Steam i
Electric Plants (UDI-2011-96) i 22 NUCLEAR REGULATORY COMMISSION 1
i U.S AND WORLDWIDE ENERGY s W R W[eiE S S U.S. Electricity Generated by Commercial Nuclear Power In 1996, net nudear-based electric genera-
- In 1996, Combustion Engineering (CE) l tion in the United States produced a total of reactors had the highest average capacity l
670 thousand gigawatthours (see Table 7 factors compared to those of the other l
! and Figure 12), three vendors. The 15 CE reactors had on average capacity factor of 81 percent.
In 1995, the overage U.S. net capacity factor The average capacity factors for the was 79 percent. It decreased to 77 percent other three vendors were the following:
in 1996. Since 1985, the average capacity 37 General Electric reactors -- 73 percent, factor has increased 14 percentage points 51 Westinghouse reactors - 79 percent, (see Table 7). and 7 Babcock and Wilcox(B&W) reactors -- 73 percent (see Table 8).
- Capacity factor is the ratio of electricity generated to the amount of energy that could have been generated (see Glossary).
- More than three quarters of the U.S.
commercial nuclear reactors operated above a capacity factor of 70 percent in 1996 (see Table 8).
I i
,;p, 7.,,yi___ --~--^e="%"-
., g J =
1997 INFORMATION DIGEST 23 l
. . ";y M e gggggi;gg p Table 7. U.S. Commercial Nuclear Power Reactor Average Capacity Factor and Net Generation,1975-1996 Number of Average Annvol Net Generation of Electricity ng Thousands of Percent of Year s CapPercent)
(ooty Fooor Giaowatthours Total U.S.
1975 51 67 167 8.7 1976 55 64 185 9.1 1977 63 64 240 11.3 1978 66 67 271 12.3 1979 66 61 252 11.2 1980 67 58 248 10.9 1981 70 61 268 11.7 1982 72 58 278 12.4 1983 74 58 280 12.1 l 1984 82 58 317 13.1 l
, 1985 89 63 371 15.0 1
- 1986 95 60 404 16.2 1987 102 62 446 17.3 1 1
1988 108 65 522 19.3 1989 109 63 528 19.0 1990 111 68 576 20.5 1991 111 71 613 21.7 l t
1992 110 71 620 22.2 1993 109 73 611 21.2 1994 109 75 640 22.1 1995 109 79 674 22.5 1996 110 77 670
' Data are not available.
Figure 12. Net Generation of U.S. Nuclear Electricity,1975-1996 THOUSAND GIGAWAITHOURS 700 600 500 400 300 -
200 100 0
1975 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 1996 YEAR Nota (Table 7 and Figure 12): Average annual capacity factor is based on not maximum dependable capacity. See Glossary for definition.
Source (Table 7 and Figure 12): Licensee data as compiled by the Nuclear Regulatory Commission
-,_.,n.n . n ,: ,
24 NUCLEAR REGULATORY COMMISSION
U.S, AND WORLDWIDE ENERGY WFMER l Table 8. U.S. Commercial Nuclear Power Reador Average Capacity Fador by Vendor and Reactor Type,1994-1996 Number of Percent of Operating Net Nuclear Capacity Factor Reactors Generated 1994 1995 1996 1994 1995 1996 Above 70 Percent , 75 92 84 79 91 87 50 to 70 Percent 23 9 15 18 7 10 l
Below 50 Percent 11 8 11 3 2 3 l
Total 109 109 110 100 100 100 l
Aver Number of Ca Percent of Operating F Net Nuclear Reactors (Percent) Generated 1994 1995 1996 1994 1995 1996 1994 1995 1996 Vendor:
Babcock &Wilcox 7 7 7 86 92 73 7 7 6 Combustion Engineering 15 15 15 80 72 81 15 13 15 General Electric 37 37 37 68 77 73 29 31 31 Westinghouse Electric 50 50 51 77 80 79 49 49 48 Total 109 109 110 100 100 100 ReactorType:
Boiling-Waler Reactor 37 37 37 68 77 73 29 31 31 __
Presst,rized-Water Reactor 72 ~72 73 79 80 79 71 69 69 l
Total 109 109 110 100 100 100 Note: Average capacity factor is based on net maximum dependable capacity. See Glossary for
- definition. Refer to Appendix A for the 1991,1992 1993,1994,1995, and 1996 average capacity factors for each reactor. Percentages are rounded to the nearest whole number.
Source: Licensee data as compiled by the Nuclear Regulatory Commission
., . _ _ naw 1997 INFORMATION DIGEST 25
l l l l l l m. . f waMErfigEtyg,a Worldwide Electricity Generated by Commercial Nuclear Power l In 1996,434 operatincj reactors in 33 coun- Of the countries cited here, reactors in Japan ;
tries had a maximum dependable capacity (80 percent), Germany (79 percent), and .
of 344,492 megawatts electric (net MWe). Sweden (79 percent) had the highest gross l l capccity factors in 1996. Reactors in the
- Refer to Appendix I for a world list of United States had the greatest gross genera-nuclear power reactors and Appendix J tion by over double the next highest pro- i for nuclear power units by reactor type, ducer, Japan (see Table 9).
worldwide. 1
- Refer to Appendix K for a list of the toa Major producers of nuclear electricity during 50 units by gross capacity factor, wor d-1995 were the United States and France. wide, and Appendix L for a list of the top ;
50 units by gross generation, worldwide.
- Approximatelv 31 percent of the world's net nuclear guierated electricity was pro- Over the past ten years, the average duced in the United States (see Figure 13). annual gross capacity factor has increased .
18 percentage points in the United States, !
- France produced approximately 16 4 percentage points in Japan, and l percent of the world's net nuclear gener- decreased 2 percentage points in Sweden ated electricity. The nuclear portion of its (see Table 10). I total domestic electricity generation was approximately 77 percent (see Figure 13).
i
. . . . ; . .. ,wwmsava.!: r 26 NUCLEAR REGULATORY COMMISSION
- 1 U.S. AND WORLDWIDE ENERGY c . #9y*T5Feg?gsg2
! Figure 13. 1995 Net Nuclear Electric Power as Percent of World Nuclear i and Total Domestic Electricity Generation PERCENT OF WORLD NUCLEAR GENERATION d
SWEDEN FORMER 3% U.S.S.R.
8%
i . GERMANY
.. - ff.9 N h hpff h ;N. 7%
l 3 j $ [:[g[ [ .'i 5 Y ['[ k [ [ Ns.J.,. -
CANADA ff p-ll+.iD-[
] . *l .? l f,;,
... .j.
- y3t . . . . ;- . , . .c .
, ...~...J...- i i .
- - 1 1 __
TotalWorld Nei Nuclear l .
i Electric Generation:
2,202 Thousand Gigawatthours PERCENT OF TOTAL DOMESTIC NET ELECTRICITY GENERATION 80 73 60 1 47%
f 42%
40 l
p 3 4
30%
s 29%
f e- ,
22% f 0
CANADA FRANCE GERMANY JAPAN SWEDEN UNITED FORMER STATES U.S.S.R Note: Data is preliminary. Percentages are rounded to the nearest whole number.
Source: DOE /EIA International Energy Annual 1995 (DOE /EIA-0219(95)), Various tables and DOE /
EIA Monthly Energy Review (DOE /ElA 0035 (96/11)) Table 7.1 (page 95).
....c.. .
=un_ _ n~
1997 INFORMATION DIGEST 27
- ..-l2 W gisyggggg Table 9. 1996 Commercial Nuclear Power Reactor Average Gross Capacity Factor and Gross Generation by Selected Country Number of Average Total Operating Number of Gross Gross Nuclear Reactors Operating
. lumber of Copacity Generation in Top 50 Reactors m Operating Factor (Thousand by Copacity Top 50 by Country Reactors (Percent) Gigawntthours) Factor Generation Canada 21 65 95 3 0 France 56 74 397 0 12 l
Germany 20 79 162 4 10 Jooan 51 80 293 6 4 Sweden 12 79 72 0 2 United States 110 75* 705 24 21 j
" " " " " l Former U.S.S.R.
Source: Exce ted from Nucleonics Week @ 1997 by McGraw-Hill, Inc. Reproduced by permission.
Further repr uction prohibited.
Table 10. Commercial Nuclear Power Reactor Average Gross Capacity Factor by Selected Country,1986-1996 Averoce Gross Annual Copacity Factor (Percent) l Country 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Canada 73 72 77 74 61 72 68 70 76 68 65 France 67 60 58 62 63 63 63 69 67 71 74 Germany 78 75 74 69 66 66 72 69 72 71 79 Japan 76 77 71 71 72 72 72 73 74 79 80 Sweden 81 77 77 74 75 85 67 62 76 73 79 United 57 57 64 62 66 69 69 71 73 77 75 States 1 60 62 65 63 68 71 71 73 75 79 77}*
Former U.S.S.R.
- For comparison, U.S. average gross capacity factor is used. The 1996 U.S. overage net capacity
- factor is 77 percent. Brockets {} in Table 10 denote average net capacity factor. See Glossary for definition.
l l " Data are not available.
Note (Table 9 and 10): Percentages are rounded to the nearest whole number.
Source: DOE /EIA Commercial Nudear Power 1991 (DOE /EIA-0438), Table 18 (page 40),
Nucleonics Week @ 1997 by McGraw-Hill, Inc., and licensee data as compiled by the Nuclear Regulatory Commission
. _ ,.ammunan 28 NUCl. EAR kEGULATORY COMMISSION
l j
i
) ... ; M % M ?B ERQ2b W i
i i Operating Nuclear i Reactors i
4 I
l l
I l
1 l
1 1
2 h
i I 1
. i 4 .
( ...~__,,_,,n,,,
A i
i 1
i
. g gmngggy l U.S. Commercial Nuclear Power Reactors l
There are currently 110 commercial nudear Principal Licensing and Inspection Activities:
power reactors licensed to operate in 32 States (see Figures 15-19):
- The NRC depends primarily on reactor and facility inspections as the basis for
- Joint owners of the Hoddam Neck plant its independent determination of licensee voted on December 4,1996, to perma- compliance with NRC regulations:
nently close the unit and begin the decommissioning process. - On average, approximately 4,100 inspection hours were expended l
- Refer to Appendices A D for a listing of at each operating reactor during currently operating, formerly operating, FY 1996 (see Figure 20).
and canceled U.S. commercial nudear power reactors.
- Approximately 14 separate license changes are requested per power reactor Diversity - Although there are many similari- each year:
ties, each reactor design con be considered unique. A typicallight water reactor is - More than 1,400 separate reviews shown in Figure 14: were completed by the NRC in FY 1996.
- 4 reactor vendors
- 48 licensees
- Approximately 5,200 reactor operators
- 80differentdesigns are licensed by the NRC:
- 72 sites
- Each operator is requalified before Experience - The 110 reactors licensed renewal of a 6 yearlicense.
to operate during 1996 have accumulated 1838 reactor years of experience
- Approximately 1,700 reactor event re-(see Table 11 and Figure 21). An addi- ports are assessed by the NRC annually.
tional 193 reactor years of experience have been accumulated by permanently shut-
- The NRC is overseeing the decommission-down reactors. ing of 15 nuclear power reactors. Refer to Appendix B for their decommissioning status.
. mesuwantwmmentsmmmpygcydy.F33) Cry A'Ln %
30 NUCLEAR REGULATORY COMMISSION
! OPERATING NUGEAR REACTORS l . .
- y pgggggggggy i
{ Figure 14. Typical Nuclear Reactor
[ How Nuclear Reactors Work
. In a typical commercialpressurized light-water reactor {l) the reactor core creates heat, {2) pressurized-l seter in the primary coolant loop carries the heat to the steam generator, and (3) the steam generator vaporizes the water in a secondary loop to drive the turbine which produces electricity. Boiling-water reactors are similar to pressurized-water reactors, but use the same loop to cool the reactor and to
- deliver steam to the turbine. The reactor's core is cooled by water which is force-circulated by l electrically powered pumps. Emergency cooling water is supplied by other pumps which can be l powered by on-site diesel generators. Other safety systems, such as the containment building air coolers, also needelectric power.
l l
- s.m i
- 4 h l i
}
{ . w #M^2Fd?@4/ g
^
i T
l I
i l
i l
Diesel
!. Generator
=
[.x :
.% w - i: . f. j _. . ,
i E Water-I Su
- Systems 1
i
- Source: Nudear Regulatory Commission l 1997 INFORMATION DIGEST 31 i
- ;qgygggggggm i
Figure 15. U.S. Commercial Nuclear Power Reactors l !
WA N-A ME MT 1 ND OR { MN ID SD A
AA i MA Wy " RI MI A IA A P $$
NV N- NE
' NJ((
Wy MDAA KS A A VAAA l
A s MO KY
'N u l
' NM A AR h SC MS AL AA TX LA A f A
AA A
A A
A 'fl A licensedtoOperate(110) l l
l l
l l Note: There are no commercial reactors in Alaska or Hawaii.
Source: Nuclear Regulatory Commission
- mama w,.m n: .,
32 NUCLEAR REGULATORY (.OMMISSION 1
I
\
1 OPERATING NUCLEAR REACTORS
?- .
. apyqggggh Figure 16. NRC Region 1 Commercial Nuclear Power Reactors I
< ME i
k l
A
! w NH i
3 A j AA A NY I Ad I i ~
AA g ,
PA NEW JERSEY M A Hope Creek 1 M A A Oyster Creek NJ AA A A Salem 1 and 2 1 A MD NEWYORK A James A. FitzPatrick DE A Ginna M l A Indian Point 2 and 3~
A Nine Mile Point 1 and 2 CONNECTICUT PENNSYLVANIA A Beaver Valley 1 and 2 A Haddam Neck A Millstone 1,2, and 3 A Limerick 1 and 2 A Peach Bottom 2 and 3 MAINE MASSACHUSETTS A Susquehanno 1 and 2 A Maine Yankee A Pilgrim 1 A Three MileIsland 1 MARYLAND NEW HAMPSHIRE VERMONT A CalvertCliffs 1 and 2 A Seabrook 1 A VermontYankee A Licensed to Operate (29)
Source: Nudear Regulatory Commission
=m ,, y.s.
1997 INFORMATION DIGEST 33 l
)
- ;.a.figgggggggggggy Figure 17. NRC Region ll Commercial Nuclear Power Reacters ALABAMA NORTH CAROLINA TENNESSEE A Browns Ferry 1,2, and 3 A Brunswick 1 and 2 A Sequoyah 1 and 2 A Joseph M. Farley 1 and 2 A McGuire 1 and 2 A Watts Bar 1 A Shea.on Harris 1 -
FLORIDA VIRGINIA A Crystal River 3 SOUTH CAROLINA A North Anna 1 and 2 A St. Lucie 1 and 2 A Catawba 1 and 2 A Surry 1 and 2 A Turkey Point 3 and 4 A Oconee 1,2, and 3 A H.B. Robinson 2 GEORGIA A Summer A Edwin I. Hatch 1 and 2 A Vogtle 1 and 2 wy AA
, MISSISSIPPI VA AA A Grand Gulf l' gy i
. s- NC TN h A
M A
ku A A
, A GA AA A
FL
{
A Licensed to Operate (34) AA AA
' Note: The NRC transferred regional oversight responsibility for the Grand Gulf 1 nudear reactor to its Region IV office effective October 1,1995.
Source: Nuclear Re5ulatory Commission
. ~ ..~ ~ . _ n a u a 34 NUCLEAR REGULATORY COMMISSION
OPERATING NUGEAR REACTORS
' W1IdfGE!DM Figure 18. NRC Region Ill Commercial Nuclear Power Reactors l lLLINOIS IOWA MINNESOTA A Braidwood 1 and 2 A DuaneArnold A Monticello A Byron 1 and 2 A Prorielsland1 and2 A Clinton MICHIGAN A Dresden 2 and 3 A Big Rock Point MISSOURI A la Salle County 1 and 2 A D.C. Cook 1 and 2 A Callaway*
A Quad Cities 1 and 2 A Fermi 2 A Zion 1 and 2 A Polisades OHIO A Davis-Besse A Perry 1 WISCONSIN k A Kewounee l A PointBeach 1 and 2 MN k
k A A I
WI AA M i t
1 MI k A U M
$ A l IA A g - -r g l M g M OH A IN ll g i
3 A
MO l A Ucensed to Operate (28)
' Note: The NRC transferred regional oversight responsibility for the Colloway nudear reactor to its l Region IV office effective October 1,1995.
i Source: Nudear Regulatory Commission
. . . . - . . . . m. , m . ---- mme n, 1997 INFORMATION DIGEST 35
.' ; ( N O i t E E 2 2 0 Figure 19. NRC Region IV Commercial Nuclear Power Reactors -
I
SD WY N
g '
NE A m A ,
CO \ l CA KS A I
A M NM OK AA AA .
.r - Tx ,
ARKANSAS AA A Arkansas Nudear 1 and 2 A A
ARIZONA KANSAS AA A Polo Verde 1,2,and 3 A Wolf Creek 1 CAUFORNIA LOUlstANA L A DiabloCanyon 1 and 2 A River Bend 1 A San Onofre 2 and ?
g A Waterford 3 A %& Pd 1 and 2 A South Texas Project I and 2 A Cooper WASHINGTON Calhoun A Licensed to Operate (19) A WashingtonNudear2
- Note
- The NRC transfered regional oversight responsibility for the Grand Gulf 1 (formerly Region ll) and Callaway (formerly Region Ill) nuclear reactors to its Region IV office effective October 1,1995.
There are no commeraal reactors in Alaska or Hawaii.
Source: Nuclear Regulatory Commission
. . . -=.mer
-wm 36 NUCLEAR REGULATORY COMMISSION l
l OPERATING NUCLEAR REACTORS
. . ' . . . . .: y , . . gtgggggggg Figure 20. FY 1996 NRC Inspection Effort at Operating Reactors NUMBER OF PLANTS 40 l
l l 35 3_1 29 30 J., i&
t
~
i~ .; h+
25 iT '?,
f~ [ gj ce .
. s 20 h kjj !
15 13 NR$
M M;.2 v 12 lA50 N' Mr'f 'thhh 10 N $fb s
t, :a 7 7
~
fh '
?!
f .Wn pg l 1 1 0
.1 i, :
_ $ Ish h '- $4, i $! S @$ Ny;d5
<2000 2000- 2500- 3500- 4500- 5500- 6500- 7500- 8500- >9500 2499 3499 4499 5499 6499 7499 8499 9499 HOURS OF INSPECTION EFFORT Source: Nuclear Regulatory Commission
, .....~ - ~ y m m o u _ ._.
1997 INFORMATION DIGEST 37
l
- H @ fM f E EDEI2:
Table 11. U.S. Commercial Nuclear Power Reactor Operating Licenses issued byYear ,
1 Number Total Number Total l of Number of of Number of Reactor Licenses Operating Reactor Licenses Operating Year Nome issued Licenses Year Nome issued Licenses j l
1%2 BigRockPoint 1 1 1974(Continued) 1%7 HaddomNeck 1 2 Oconee 3 1%9 Dresden2 4 6 Peach Bottom 3 Ginno PrairieIsland 1 Nine Mile Point 1 PrairieIsland 2 Oyster Creek ThreeMileIsland 1 1970 H. B. Robinson 2 3 9 197: Millstone 2 1 46 Millstone 1 19M BeaverValley1 7 53 Point Beach I drowns Ferry 3 1971 Dresden 3 2 11 Brunswick 1 Monticello Calvert Cliffs 2 1972 Palisades 6 17 Indian Point 3 i Pilgrim 1 Salem 1 l I
Quod Cities 1 St. Lucie 1 Quod Cities 2 1977 CrystalRiver3 4 57 Surry 1 Davis-Besse Turkey Point 3 D. C. Cook 2 1973 BrownsFerry1 14 31 Joseph M. Farley 1 Fort Calhoun 1978 ArkansasNuclear2 3 60 Indian Point 2 EdwinI. Hatch 2 Kewounee North Anno 1 MaineYankee 1980 North Anno 2 2 62 Oconee 1 Sequoyoh1 Oconee 2 1981 JosephM.Fadey2 4 66 Peach Bottom 2 McGuire 1 PointBeach 2 Salem 2 Surry2 Sequoph 2 Turkey Point 4 1982 La$olleCounty1 4 70 Vennont Yankee San Onofre 2 Zion 1 Summer Zion 2 Susquehanna 1 1974 ArkansasNuclear1 14 45 1983 McGuire2 3 73 Browns Ferry 2 San Onofre 3 Brunswick 2 St. Lucie 2 CalvertCliffs 1 1984 Col 6 79 Cooper Diablo 1 D.C. Cook 1 Grand Gul 1 Duane Arnold to Solle County 2 Edwin I. Hatch 1 Susquehanna 2 James A. FitzPatrick Washington Nudear 2 mz====ww.a-mm ,
38 NUCLEAR REGULATORY COMMISSION
s OPERATING NUGEAR REACTORS
< .; 1 L5 t - Q A M S $ i"$ M f:P g 3jg C {
Number Tolo! Number Total of Number of of Number of Reactor Ucenses Operating Reactor Licenses Operating Year Nome issued ucenses Year Name issued Licenses 1985 Byron 1 9 88 1987 (Continued)
Catawba 1 Shearon Harris 1 Diablo Canyon 2 Vogtle 1 Fermi 2 1988 Braidwood2 2 103 4
Limerick 1 South Texas Project 1 PaloVerde 1 1989 Limerick 2 3 106 i
River Bend 1 South Texas Project 2 Waterford 3 Vogtle 2 Wolf Creek 1 1990 ComanchePeak1 2 108
, 1986 Catawba 2 5 93 Secbrook1
- Hope Creek 1 1993 ComanchePeak2 1 109 4
Mi0sbne 3 1996 Watts Bar 1 1 110 PoloVerde 2 Note (Table 11 andFigure 22):
1987 Valby 2 8 101 Braidwood 1 Uded t re ct rs licensed to operate.
B on 2 Year is based on the date the initial full power dnton OPeroting license was issued.
NineMile Point 2 Source (Table 11 and Figure 22): Nuclear PaloVerde 3 Regulatory Commission Figure 21. U.S. Commercial Nuclear Power Reactor Operating licenses issued by Year NUMBER OF LICENSES ISSUED 16 14 14 14 12 10 i
- 9 c
8 8 7 6
}
'; l 6
i 6 5 S 5
~
4 I :
4 4 ;
4 3 i i 's 3 3 4 s 3
i / I 2 , 2 ' . 2 2 2 1 1 j ) 1 i '
l j1 1
@@ $ 3 l :G I ?
c B _
j'E ,9 6 @
9 1962 67 69 70 71 72 73 74 75 76 77 78 80 81 82 83 84 85 86 87 88 89 90 93 1996 YEAR
===, -waa m ew.=w 1997 INFORMATION DIGEST 39
4 2 N _m E--MJ..,+wa _. aaw. A =-E+6m.d*.J_A e_4a4e._m.-Aa- 5AaAA.g.A.+,.m+4_._A_..-Lw-w,_J.JL,a. ,4,e.g..,,JMA__ am. s e _49 %w.24a-M4ea.,-_4_a cesp_A._,d..h.m v..,m e,
' e
- 1 f ,
-<;.y %, *.@,'yQ;fk,g;4wygyg.;g',
.. ~ ' .
i t
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+
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,_.(4'./h ,- '.,4.m ' *,_ , m 40 NUCLEAR REGULATORY COMMISSION
I OPERATING NUCLEAR REACTORS
< s wggges 1
! Performance at U.S. Commercial Nuclear Power Reactors i Performance Indicator Program: Systematic Assessment of Licensee
. Performance: i The Perforraonce Indicator Pregram is a i single, coordinated, overall NRC program _ The Systematic Assessment of Licensee that provides an additional view of opera- Performance, or SALP, Program is on inte- ;
I i tional performance and enhances the NRC's grated NRC effort to collect and evoluote obility to recognize oreos of changing safety observations and data to assess and better
- performance of omroting plants. When understand the reasons for a licensee's
! viewed as a set, tie performance indicators performance. The purpose of the program is
[
2 (Pis) for a given plant provide additional to direct NRC attention and resources toward those areas that reflect weaknesses and that dato for determining performance trends, l- Pls focus attention on the need to assess and involve nudear safely. This involves a review
- understand underlying causes of identified of licensee performance over an extended changes by evaluating other available infor- period of time (normally about 18 months) in l
- motion (see Figure 22 and Appendix F). areas such as operations, engineering,
- maintenance, and plant support.
l The PI Program is used in conjunction with
. other tools, such as the results of routine and On the basis of the review, o rating is as-special inspections and the Systematic As- signed to reflect the quality of licensee per-l sessment of Licensee Performance (SALP), to formance within each area evaluated. The l
provide data to NRC monogers who decide SALP evaluations are discussed with the l
i whether any plant specific regulatory pro- licensee to communicate the results of the
[ grams need adjustment. The staff is evalu- evaluation. Those discussions are usually conducted in a public meeting. The NRC !
! oting the use of performance indicators to l provide more objective bases for judging continually reviews the SALP process to i whether a plant should be placed on or identify procedural changes or refinements
- deleted from the NRC Watch list. The main that con be made to improve on its intended l l objective of this effort is to supplement the purpose of clear and concise communication material that is currently being presented at to licensee management regarding the ,
1
< the Senior Monogement Meetings (SMM) to strengths and weaknesses of plant perfor-
! provide a more systematic process for evolu- mance. For the latest SALP rating by reac-I ating plant-specific performance indicators. tor, refer to NUREG 1214, " Historical Dato !
Pls have limitations and are subject to misin- Summary of the Systematic Assessment of
- terpretation. Therefore, caution is war- Licensee Performance."
. . ronted in the interpretation and use of the
} dato. The opplication of Pls for purposes i and in manners other than those stated
. above will be counter to the NRC objective j of operational safety.
, - . . _ . ,. s --,,mmmy ..
L 1997 INFORMATION DIGEST 41
_ . ._ . ~_ __ _ _ . _ _ _ . _ .
.: M J E T R @ E M yj g ;;,
Figure 22. NRC Performance Indicators; AnnualIndustry Averages,1985-1996*
AUTOMATIC SCRAMS WHILE CRmCAL SAFETY SYSTEM ACTUATIONS AVERAGE NUMBEROF REACTOR SCRAMS AVERAGE NUMBER OF ACTUATIONS 6 3 m
, y 5- ?- f n
$ 7 e
f o ,
4- ; J 2- -
t
- 3. d 9 % $ l 8 ,- 3
, a '
3-j n]gj4 $ 7 s@j)
,M )d A
?
M 9
$ m
-y y ,d n 9 2-t,e
--!" -)1.;.h 9 1- s q-4 -
3 3
'i -
3o y
). na 8E a 3 a j 7;;
~
a m "fi 5 ,f. &l 1
- 1 3 1;
' ^
di 4 4,
]
j 0 0 1985 86 87 88 89 90 91 92 93 94 95 1996 1985 86 87 88 89 90 91 92 93 94 95 1996 YEAR YEAR 1
1 SIGNIFICANT EVENTS SAFETY SYSTEM FAILURES" AVERAGE NUMBER OF SIGNIFICANT EVENTS AVERAGE NUMBER OF FAILURES 3 4 N .
. .S \ * \ .
\ \ N N N \ \
3 N -N -N -N -N -N -N .
Y \ \ \ \ \ \ \ \
2- \ \
- r N \ \ \ \ \
J . - \
7 \ \ \ \ \
i '; 2- r 4 -N\ 9 -
-? \ dU -\ *-\ -
p i 4 4 $ \ ~
\ \ \ \
+
L 4
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L N N N l- -
- j 7
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4 f
v j 2 f \ ., \ x N ;
.. y 3[ l 5, l- ( -j -j
, u
~ 1 -
,' ! ]
f -1 9 -
' 1 f ff 3)MM 2
0 t i
- t. r. A k
9 f I. 5 1 1985 86 87 88 89 90 91 92 93 94 95 1996 o\ 1985 86 87 88 89 90 91 92 93 94 95 1996 YEAR YEAR t
sammmwr :wwa wzu .m:w 42 NUCLEAR REGULATORY COMMISSION
OPERATING NUGEAR REACTORS 1 1
l
.t - .,- ' [5 .
4 EQUIPMENT-FORCED OUTAGES FORCED OUTAGE RATE PER 1000 CRITICAL HOURS I AVERAGE EQUIPMENT-FORCED OUTAGE RATE AVERAGE FORCED OUTAGE RATE (%)
12 2 10 -
8- -
6 1 2A Ih o 0 198586 87 88 89 90 91 92 93 94 95 1996 1985 86 87 88 89 90 91 92 93 94 95 1996 YEAR YEAR COLLECTIVE RADIATION EXPOSURE AVERAGE MAN-REM
- Calendar year values are used for 600 1985 through 1995. Fiscal year values are used beginning in 1996. Data for SUU )*
October 1,1995 through December 31,1995, are included in both calendar
! year 1995 and fiscal year 1996 values.
Refer to Appendix F for values, 400 5d -7 h 3 j j, " The hatched areas represent additional d to that resulted from reclassification of l
300 -
-( -
[ y y d d -! , sg safety system failures. !
200 j
$ $ j -f -g
$ d
-g
-"s;'f
)(j4 #7 1 Note: Data represent onnual industry avera es with plants in extended shutdown
\z V ]$ j h 6 Y
- ) exclu ed. Data are rounded for dis I from Purposes.These data may differ sli 100 - - - - - -
} -
P Previously published data as a res o N 7 j i -$ ! l $
$)-}J: O ]j j;
.t 9 j p d J refinements in data quality.
Source: Licensee data as compiled by the 198586 87 88 89 90 91 92 93 94 95 1996 YEAR Nuclear Regulatory Commission
. . . . . . . . ........_..._...;......~........,
1997 INFORMATION DIGEST 43
d g .. ', ,
Future U.S. Commercial Nuclear Power Reactor Licensing
- Reactor Aging and License Renewal
- In a separate rulemaking, the NRC revised the scope of environmental effects for license in 1996, 53 reactors were 20 years or older.
renew enhance 6e agen s environmen-This represented approximately 48 percent of rod i I review Process for reactor icense renewal.
the licensed reactors 38 percent o; net nuc
[ ear ucing generated dectricity Theapproximately final, revised rule became effective on Se (see Figure 23). ,;[tember 5,1996. The NRC has begun rts to develop regulatory guidance and in contrast, by the year 2000,61 reactors standard review plans f r license renewal. ;
will be 20 years or older. This r resents '
The current industry ap 3 roach is focused on
- approxima 6 percent of the icensed submitting,in lieu of a ormallicense renewal reactors pr ucing approximately 47 percent a pication, plant-specificorownersgroup of net nudear generated electricity, generic reports for NRC review and approval.
In 2000, the licensed nudear generating The NRC received five technical reports from i
capacity could begin to decrease as reactors Baltimore Gas and Electric (BG&E) Company begin to reach their 40 year terms, a limit for reviewin FY 1996. BG&E intends imposed by the Atomic Energy Act of 1954, to submit 29 additional technical reports as amended or are shut down for other rea- through FY 1997 and the BG&E program 4
sons (see Table 12 and Figures 24 and 25). could result in a license renewal application in FY 1997. The Nuclear Energy Institute is the Extending reactor operating licenses beyond lead industry group interacting with the NRC their current 40 year terms will provide on the license renewal rule im lementation viable approach for electric utilities to ensure guidance. The Babcock & Wicox Owners
- the adequacy of future electricity generating neric license
, capaaty that offers significant economic Group has formulated a ' bead to the subm renewal program that wi benefits when compared to the construct.ion tal of a renewal application. The Westing-f new reactors.
house, Babcock & Wilcox, and Boiling Water In December 1991, the NRC issued the rule Reactor Owners groups have submitted topi-and associated documentation that describe cal reports on aging management activities to what a licensee must be able to demonstrate the NRC to review. Duke Power Company for the NRC to make a determination that the also has begun submitting topical reports for plant can continue to be operated for up to its Oconee plants.
20 additional years beyond the expiration of The NRC is conducting research providing the its 40 yearlicense. The NRC issued an technical bases to ensure that critical reactor amenc ment to the license renewal rule that components, safety systems, and structures became effective on June 7,1995. The wil provide adequate reliability as reactors amendment to the rule is expected to provide age. Research results will be useful in assess-a a more stable and predictable regulatory ing safety implications of age-related degra-3rocess for license renewal by focusing the dation during the 40 year license and in
- ecense renewal 3rocess on the management supporting safety decisions associated with 1 of the adverse e fects of aging on certa,9 license renewal.
systems, structures, and components dunng the period of extended operation.
,. ~ - __w. ~w a , -
44 NUCLEAR REGULATORY COMMISSION
. OPERATING NUCLEAR REACTORS
'. w q m q gedg g g g g; Figure 23. U.S. Commercial Nuclear Power Reactors-Years of Operation WA -
( A A fg i M ID so wi j
^^ AA A
wy MI R1 4
% A ,, 5 4 PA M bAA NV - NE IA Ag -6y A\ OH !
wy MDAA i MO KY ^
N e NCh AZ OK AA A fl !
AA A NM A A l AA (- AR MS AA AL ,GA A
LA A'A A ,
TX 00 A g A
L y
YEARS OF NUMBER OF AVERAGE COMMERCIAL OPERATION REACTORS CAPACITY (MDC)
A 0-9 17 1106 A 10-19 40 1038 A 20-29 52 751 A Over 30 1 67 Note: There are no commercial reactors in Alaska or Hawaii. Calculated data os of 1996.
Source: Nudear Regulatory Commission
. ... - - . - w,em m . ,
1997 INFORMATION DIGEST 45
l l
1
. ' $lll,;.>,.lN?$$?$$?((
^
^
Table 12. U.S. Commercial Nuclear Power Reactor Operating Licenses-Expiration Date by Year Number Year Number Year 1 of Assuming of Assuming I Reactor Licenses Construction Reactor Licenses Construction :
Year Name Expired Recoplure* Year Name Expired Recopture' 2000 Big Rock Point 1 2006 Dresden 2 1 2014D.C.(Continued)k Coo 1 2007 Hoddam Neck" 2 Duane Arnold
. Palisades 2011 Edwin L Hatch 1
^
2008 MaineYankee 1 2012 James A. FitzPotrick !
2009 Ginna 3 Oconee 3 Nine Mile Point 1 Peach Bottom 3 O PrairieIsland 2 2010 H.ysterCreek B. Robinson 2 4 Three MileIsland 1 Millstone 1 201S Indian Point 3 2 Monticello Millstone 2 i Point Beach 1 2016 BeaverValley1 7 l 2011 Dresden 3 1 Browns Ferry 3 1 2012 Pilgrim 1 6 Brunswick 1 i Quod Cities 1 Calvert Cliffs 2 Quod Cities 2 Crystal River 3 l 2 Sury1 Solem 1 i
Turkey Point 3 St. Lucie 1
- Vermont Yankee 2017 Davis-Besse 3 2013 Browns Ferry 1 15 D. C. Cook 2 Fort Calhoun Joseph M. Farley 1 Indian Point 2 2018 ArkansasNuclear2 3 Kewounee Edwin 1. Hatch 2 1
, Oconee 1 North Anna 1 3
Oconee 2 2020 North Anno 2 3 l Peach Bottom 2 Salem 2 l Point Beach 2 Sequoyoh1 l PrairieIsland 1 2021 DiabloCanyon 1 4 l 1
San Onofre 2 2022 Joseph M. Farley 2 Son Onofre 3 2022 McGuire 2 Su 2 Sequoyah 2 Tur Point 4 2022 GrandGulf1 4 l Zion to Salle County 1 Zion 2 Summer 2014 ArkansasNudear1 13 Susquehanna 1 Browns Ferry 2 2023 La Solle Counk;2 4 l Brunswick 2 McGuire 2 i Calvert Cliffs 1 St. Lucie 2 Cooper Washington Nuclear 2 2024 Byron 1 7 Callaway
_ _ - a _ m r n n ..: -
46 NUCLEAR REGULATORY COMulSSION
1 OPERATING NUGEAR REACTORS c; x 4 g g g g g y g e:
Number Year Number Year i
of Assuming of Assuming Reoclor Licenses Construction Reodor Licenses Construction Year Nome Expired Recopture' Year Nome Expired Recopture'
. 2024 (Continued) 2027 (Continued)
! Catawba 1 FaloVerde 3
- Limerick 1 South Texas Project 1
' Vogtle 1 Palo Verde 1 i Susquehanno 2 2028 SouthTexasProjed2 1 Waterford 3 2029 Limerick 2 2 2025 DiabloCanyon2 6 Vogtle 2 Fermi 2 2030 ComanchePeak1 1 Millstone 3 2033 ComanchePeak2 1 Palo Verde 2 2035 WattsBar 1 River Bend 1 Wolf Creek 1
- Year assumes that the maximum number of years
' for construction recapture has been added to the 2026 Braidwood1 9 Byron 2 current expiration date. This column is limited to
, Catawba 2 reactors eligible for construction recapture. See
! Clinton Glossary for definition.
- Hope Creek 1 "Haddam Neckprematurely shutdown in December,1996 Nine Mile Point 2 Pgy, Note (Table 12 andFigure 24)
Limited to reactors licensed to operate.
i Shearon Harris 1
' Source (Table 12 andFigure 24): Nudear 2027 BeaverVal\ey2 5 Regulatory Commission Braidwood 2 i
> Figure 24. U.S. Commercial Nuclear Power Reactor Operating 1.icenses -
Expiration Date by Year Assuming Construction Recapture NUMBER OF UCENSES EXPIRED 20
! 20 '.
i i 15 13 13 s 10 11 7
7 7 ..
4 4 4 5
0 444ili!II:iiliiilll'lil 2000 06 07 09 10 11 12 13 14 15 16 17 18 20 21 22 23 24 25 2026-YEAR 35 1997 INFORMATION DIGEST 47
a 4
. ,7 _* , I .1, . I 4 . ( N 3 j Figure 25. U.S. Commercial Nuclear Power Reactor Generating Capacity, 1960 2060 i
i
- MAXIMUM DEPENDABLE CAPACITY (NET GIGAWAITS) i 120
~
100 -
l -
1 CURRENTLY LICENSED TO i OPERATE 75 7 (99.4 GWe) 4 l
i M -
j _
4 95 -.
i -
g
~
b
- 0 l 1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 YEAR l
I i E LicensedCapacity X Licensed Capacity - Extended 20 Years i
i l
}
4 t
i d
I Note: Data assume current expiration dates have been adjusted for construction recapture and
{ licenses extended 20 years. Reflects Haddam Neck prematurely shutting down in December,1996.
See Glossary for definition.
l i Source: Licensee data as compiled by the Nuclear Regulatory Commission i
mamuunamum n ava m um v s,
! 48 NUCLEAR REGULATORY COMMISSION
OPERATING NUGEAR REACTORS
. 3.guygggggy Future U.S. Commercial Nuclear Power Reactor Licensing (continued)
Standardization of Future Reacter Designs: The NRC issued final design approvals and expects to complete rulemaking certifying The NRC has revised its regulations to make the two evolutionary designs, the General the licensing process for future nudear power Electric Advanced Boiling-Water P.eactor reactors more stable and predictable. This (ABWR)and the ASEA Brown Boveri/
new licensing process provides for Early Site Combustion Engineering System 80+, in Permits, Certification of Standard Designs, Spring of 1997. There is also one advanced and Combined Licenses. The changes should light-water reactor design under NRC review substantially improve the entire licensing for design certification, the Westinghouse process, with the goal that future nudear Electric Corporation's advanced passive power plants will use standard reactor de- reactor (AP600). Activities associated with signs that are certified by the NRC and will resolving the remaining technical and policy be located at preapproved sites. Standard- items, issuing the final design approval, and ization can minimize excessive diversity in completing rulemaking for the design will reactor designs and can increase confidence continue through 1998. The AP600 employs in the safety, reliability, and availability of passive safety features.
future nuclear power reactors.
. . . . , _ , .,_n,,,,,,,, ,.
1997 INFORMATION DIGEST 49
ggggggymyy U.S. Nuclear Nonpower Reactors i Nuclear nonpower reactors are designed and
- Since 1958,72 licensed nonpower utilized for research, testing, and educational reactors have been decommissioned purposes, for examplo:
- McClellan Air Force Base in California l
- In the performance of research and applied for a nonpower reactor license testing in the areas of physics, chemistry, in October 1996.
biology, medicine, materials sciences, and related fields
- Refer to Appendix E for a listing of U.S. nuclear nonpower reactors with
- In educating people for nudear related operating licenses careers in the power industry, national defense, research, and education Principal Licensing and Inspection Activities: l l
, There are 43 nonpower reactors licensed
- Approximately 300 nonpower reactor to operate in 27 States (see Figure 26): operators arelicensed by the NRC:
i
- 4 nonpower reactors are being - Each operator is requalified before decommissioned renewal of a 6 year license
- 7 nonpower reactors have possession
- Approximately 40 nonpower reactor only licenses inspections are conducted annually 4
O i
i 50 NUCLEAR REGULATORY COMMISSION
. OPERATING NUGEAR REACTORS da MME&MW Figure 26. U.S. Nuclear Nonpower Reactor Sites i
WA -
MT ND I
VI A i g MN OR g g y
ID SD WI NY - A Mig A Wy _
A i AA p, g
! A \
ll gl UT CO A WV g MDAA i CA KS l MOA KY A
{N A NC i
l A TN AZ OK i A NM AR SC A GA MS Al l
TX LA A AAA A LicensedtoOperate(43)
Note: There are no nonpower reactors in Alaska or Hawnii.
Source: Nuclear Regulatory Commission
. . . . . . _ _ . _ _ . . . _ . _ . . . . . . , . , _ . ,,, y ,
1997 INFORMATION DIGEST 51
. xqmg7ggg;mg Nuclear Regulatory Research NRC's regulatory research program seeks to Over time, the NRC's research program has provide information necessary to resolve evolved as the regulated industry has ma-technical issues associated with nuclear tured, and that is reflected in the program's safety and regulation of NRC licensed reduction in size as earlier technical issues facilities. As such, the research program is have been resolved and corresponding both confirrnatory of existing safety margins regulations have been promulgated (tee and anticipatory of future concerns. The Figure 27). The current NRC research challenges and influences that govern program focuses on supporting the NRC's NRC's regulatory research program include: review of emerging technologies (e.g.,
changes in the practices and performance digital instrumentation and control systems),
of the regulatecl industry, increased eco- understanding and resolving nuclear plant nomic pressures on licensees, emergence of aging issues arising as a result of operating new safety issues as the industry continues experience, decommissic'ning licensed to mature, availability of new technologies, facilities, understanding the risks associated and public awareness and involvement in with nudear facilities, preparing for license the regulatory process. The NRC's research renewal applications, and understanding program is key to providing the capability recent safety issues regarding design basis to face these challenges. Accordingly, the accidents and postulated severe accidents NRC must have highly skilled independent that have been identified from the NRC's expertise and accurate information neces- review of advanced reactor designs.
sary to formulate sound technical solutions and make timely regulatory judgments.
t
_. .. - -m - m -,~mm~m 52 NUCLEAR REGULATORY COMMISSION
OPERATING NUCLEAR REACTORS
'. 4 W.CRUg2EygM
- Figure 27. Research BudgetTrends FY 1975-1997 l
l DOLLARS IN MILLIONS 250 200 9 9
)
" $ {i )p5 150 j l j j
?
4
)dIt 100 4 f f g? a m 3 i s
) 0{ 1 ?si i l 4
> : 4
~
l ,A !
{ s i?
d
. J j l 1 i { 1 j i 50 : j 4 <
l h 1 a l d h ti 3
g i k L )
g 1975 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 1997 FISCAL YEAR The NRC research program provides the independent expertise and information necessary for making timely regulatory judgements, anticipating problems of potential safety significance for which new or expanded knowledge can assist NRC in pursuing its mission, and develop-ing regulations and regulatory guides pertaining to Commission policy or technical require-ments. Over the years, the research program has been significantly reduced to reflect the changing environment and the maturing industry.
.,4
'" LT .e y ,8-' .>f 1997 INFORMATION DIGEST 53
,4ms .-m,- wa,.wd+ e- =,e--o - m-4-, JJ- e 4 444---d# h >-4 -m.--h upou ->45--' 4 -m %+d--+Ae--Ae ad--a **JJ ---ma.4+JeduA4aA 4J4we44 44-4J4-g = e- O Je're-eA--h-6-- 1 i
4 6 g 4
f 4
1 i
A l
r i
7 s
i i
i i,
4 1
- - - - - -_ u_a;a.m..wuw ,u,1.m. , . .
54 NUCLEAR REGULATORY COMMISSION
(
ll. ; ...;-)2:kE'LWiiM&iEE 3
$' I i Nuclear Material i 1 i
1 i
)
! . . Academic 4
Industrial J-
. . . . .,.1.. . . . . . , .,.g .,--
ggg.g-.; rug,u,,. yg;,s : u .g W
.J .Y hhhh f} fh U.S. Fuel Cycle Facilities The NRC licenses and inspects all commer-
- Gaseous Diffusion Enrichment Focilities:
cial nuclear fuel facilities involved in the
- U. S. Enn. hment c Corporat.ion processing and fabrication of uranium (Paducah, Kentucky) i ore into reactor fuel.
- U. S. Enrichment Corporation There are eight major facilities licensed to (Piketon, Ohio) operate in seven States (see Figure 28):
In J nu ry 1991, the NRC received on l
- Uranium Fuel Fabrication Facilities:
application to construct and operate the ABB Combustion Engineering Nation's first privately owned uranium (Hematite, Missouri) enrichment facility in Homer, Louisiano.
NRC's Safety Evaluation Report for the
~
c 0"*'. I Ebn. facility was published in January 1994, and (Wilmington, North Carolina)
NRC's Final Environmental Impact Statement
- Westinghouse Electric was published in August 1994. Hearings Columbia, South Carolina) were completed in 1995, and a final
- Nudear Fuel Services decisi n r m Q Atomic Safety ed L.icensin9 B rd 15 expected in 1997.
(Erwin, Tennessee)
In dditi n, NRC regulates 17 other facilities l
- Babcock & Wilcox Fuel Company that possess significant quantit,es of special i
J (Lynchburg, Virginia) '
nudear material (other than reactors) or
- Babcock & Wilcox Naval Nuclear process source material (other than uranium l
Fuel Division (Lynchburg, Virginia) recovery facilities).
- Siemens Nuclear Power Corporation NRC is also engaged in a cooperative effort l (Richland, Washington) with the Department of Energy on processing nd s lidific ti n f high-level radioactive
- Uranium Hexafluoride waste for long-term isolation. Since 1980, p, p,;;;g,*
the West Valley Demonstration Project Act
- Allied-SignalIncorporated has required NRC to oversee the protection (Metropolis, Illinois) of the public safety for the high-level waste vitrific ti n dem nstration project at the in addition, NRC regulates the two gaseous Western New York Nuclear Center, West diffusion uranium enrichment faciIities, which Valley, New York. Under a joint project are leased by the United States Ennchment between the Department of Energy and New Corporation from the Department of Energy.
York State Energy Research and Develop-NRC promulgated regulations for the ment Authority, the West Valley Demonstra-gaseous diffusion plants in 10 CFR Part 76 tion Project began converting li uid high-
, in September 1994. The two plants come leve waste into glass logs in July 1996.
under NRC regulation on March 3,1997.
In 1996, NRC also initiated a cooperative l
l
. . . .- : . . m__am_nn m 56 NUCLEAR REGULATORY COMMISSION
NUCLEAR MATERIAL SAFETY
-- x.ggggggygggy project with the Department of Energy's Tank Principal Licensing and Inspection Activities:
Waste Remediation System Privatization .
- NRC. issues approximately 120 new,
, Project in Hanford, Washington. Under a renew I, license amendments, and safety Memorandum of Understanding signed in 1
"8 " ' 5 "I'*5 ' b* CYC
- early 1997, NRC agreed to provide f cilit.ies annually,
, technical assistance to DOE's efforts for regulating the construction and operation of
- NRC routinely conducts safety inspec-the high-level waste solidification facility, tions of approximately 15 fuel cycle with the possibility that NRC may be colled facilities or sites.
on to license that facility during the second phase of the project.
i l
1997 INFORMATION DIGEST 57
l
.: ' 4, t,i
.. C j[1
.g ' ;' -
1 Figure 28. Major U.S. Fuel Cycle Facility Sites 1
! A )
WA _
- MT ND t VI !
l OR \' MN r \
( MA ID SD WI NY -
WY Mi RI
CA KS MO, KY *A
-N- A L N TN AZ NM OK AR e l b- Al GA k
- TX FL
- Uranium Fuel Fabrication Facility (7)
E Uranium Hexafluoride Production Facility (1)
- Uranium Enrichment Facility Site (1)
A Gaseous Diffusion Enrichment Facility (2) l l
Note: There are no fuel cycle facilities in Alaska and Hawaii.
Source: Nuclear Regulatory Commission
. , .~~ ~ _na_,ana.nn 58 NUCLEAR REGULATORY COMMISSION l
l
NUGEAR MATERIAL SAFETY g g;m g 73 y5y g g U.S. Material Licenses Approximately 21,600 licenses are issued Academic Used in universities, colleges,
- for medical, academic, and industrial uses of and other academic institutions in course nuclear material (see Table 13)
- workand esearch
- Approximately 5,900 licenses are Industrial - Used in such areas as radiogra-administered by the NRC. phy, gauging devices, gas chromatography, welllogging, and smoke detectors
- Approximately 15,700 licenses are administered by the 30 States that Principal Licensing and Inspection Activities:
participate in the NRC Agreement States Program. The State of Massachusetts
- NRC issues approximately 3,200 new, became an Agreement State in March renewal, or license amendments for l
1997. An Agreement State is one that materiallicenses annually.
has signed on agreement with the NRC allowing the State to regulate the use of
- NRC conducts approximately 1,700 radioactive material within that State health and safetyinspections ofits (see Figure 29). Other States that have nuclear material licensees annually.
applied for the Agreement States Program are Ohio, Pennsylvania and
- NRC implemented in 1996 the Materials Oklahoma. Licensing Business Process Redesign initiative to streamline the workflow for
! Medical- An estimated 8-9 million processing materials licensing actions diagnostic and therapeutic clinical 3roce- (see Figure 30).
dures using radioactive material, o which approximately 250,000 are therapeutic, are performed annually.
t 1
... ~ . . .
=.
1997 INFORMATION DIGEST 59
- f.ggVJtETsIGESM Table 13. U.S. Materiallicenses by State I
Nember of Licenses Number of Licenses Agreement Agreement State NRC States State NRC Stoies Alabama 19 401 Montana 84 0 Alasko 52 0 4 Nebraska 171 Arizona 20 285 Nevado 5 181 Arkansas 9 267 New Hampshiic 11 99 Califomia 61 2,100 l New Jersey 538 0 i
Colorado 28 388 New Mexico 22 240 i Connecticut 212 0 1,558 New York 51 Delaware 63 0 538 North Carolina 16 District of Columbio 52 0 North Dakoto 8 69 l Florida 24 1,144 oh;o
- 620 0 Georgia 17 500 Oklahomo 234 0 Hawaii 64 0 Oregon 10 268 Idaho 75 0 0 Pennsylvania 808 lilinois 57 789 Rhode island 2 83 Indiano 299 0 330 South Carolina 12 lowo 6 215 South Dakota 45 0 Konsos 18 322 Tennessee 25 563 Kentucky 15 403 2,043 1 Texas 60 louisiana 12 511 Utah 15 223 Moine 5 128 Vermont 37 0 Maryland 65 561 0
Virginia 388 Massachusetts 48 612 412 Washington 19 Michigan 522 0 0 West Virginia 199 Minnesota 172 0 0 Wisconsin 272 l Mississippi 10 320 89 0 Wyoming Missouri 301 0 0 Others' 161 l Total 5,961 15,724
- "Others" indudes territories such as Puerto Rico, Virgin Islands, Guam, and American Samoa.
Note: NRC data os of 04/14/97. Agreement States dato are latest available as of 12/96.
Source: Nuclear Regulatory Commission and a 01/96 report by the Texas Department of Health, Bureau of Radiation Control
,_ nwm-60 NUCLEAR REGULATORY COMMISSION
l NUCLEAR MATERIAL SAFETY 4 7E.gj;-q qggggggp;;q Figure 29. NRC Agreement States
'/,n
'b g- 4 NFN MT g,, w
~
g' r
VT 7:
l
, i ID SD 1
WI fik
$ rq
{
WY
- ~ ,
i g $Fltl '
($,,
RI d
i <
PA b.. .,
LNJ
,l l . OH, -y _9g f ;9 i i LMD l g
.=
. ((y .j i og ;'~
. . 's
) '.
+ . 2 c - y4 4, .
L. . .. . ,,g] a
- gg ' %;h",W __ '
sjR;
- W /,
- k. Ng$:$
kf[
ig hhli 1
es AgreementState(30)
(
,
- The State of Massachusetts became an Agreement State in March 1997.
Note: Data as of 3/97. Alaska and Hawaii are not Agreement States.
Source: Nuclear Regulatory Commission I ..s -1 . . .. . _,_ .xm-m m .,
1997 INFORMATION DIGEST 61
iis@6MJEMidIESO Agure 30. Business Process Redesign f
'Gos'Chromolograph ,
Gatekeear & } M^ M / ? '~'~f~~ff"'">; "
i Workfow 7 A EC 6 a computer-Assisted Manager p" ,,,,
s P
100% Initial l 1
hiConts & I 3
UCen5ees M.m, ;
-s Q.NRC Licaming ToolSet i ~ ^ rt y f
~
I i
km$fd5h yp andj p W $g i ns t
mmnwie. T we fjp. s y-m MNw i
v.
{
gg g hhg l{P'MT.T$NfNM?
~
[jCen56 Applications C il Technico! :A %
- 4. @ g,,, Review g ,,
- J. $ 1 (
- $x ,, , bA -
N a
{ M M .5Copeff f g g7 y j) if i
M Licen5ees 4
Applications for relatively simple actions go through a computer-assisted process. This process uses artificialintelligence-assisted scripts to hela reviewers rapidly determine if the applications conform with established NRC regulations anc licensing policies. Applications for more complex uses would be processed by trained technical reviewers, working either individually or in teams.
4 i
j j
4 4
.c. .,,.3
, ... ggggygggyg-gw4.p- i 62 NUCLEAR REGULATORY COMMISSION
NUGEAR MATERIAL SAFETY l
~ J.;%xdadmidgME U.S. Nudear Material Transportation and Safeguards The NRC reviews and licenses the design
- NRC reviews, evaluates, and certifies of containers used to transport radioactive approximately 100 new, renewal, or l materials; conducts transport-related safety amended container-design applications i inspections; quality assurance inspections for the transport of nuclear material of designers, fabricators, and suppliers of annually.
l approved transportation containers; and sateguards inspections of nuclear material
- NRC reviews and evaluates approxi-l licensees, mately 100 license applications for the l export of nuclear material from the United Both the NRC and the Department of Energy States annually.
! continue joint operation of a national database and information support system to
- NRC conducts comprehensive physical track movement of domesti: and foreign security and material control and nudear material under safeguards control. accounting license reviews and conducts i inspections at the major fuel fabrication Principal Licensing and Inspection Activities: facilities annually.
l l
- NRC examines transport related safety
- NRC inspects 10 to 12 dry storage and l during approximately 1,000 safety transport package vendors annually, inspections of fuel, reactor, and material
! licensees annually.
l l
l l
1
. . . . ~ . . . - . . mumammw .
1997 INFORMATION DIGEST 63
' y+%gggggggj
! International Nuclear Safety and Safeguards The NRC participates in a broad program of
- Under the Cooperative Threat Reduction intemational cooperation related to nudear (CTR) Program, NRC provides support to safetyand safeguards.
the Ukraine,regulatory and Kazakstanagencies in the deve in Russia, lop
- NRC has 33 arrangements / letters of and ment of material protection, control,d accounting (MPC&A) regulations an agreement signed organizations. These arrangements with regulatory /
MPC&A licensing and inspection
+
lettersof agreement: programs. NRC also provides this support to Russia under the Lisbon
- Ensure prompt notification of safety Initiative Program.
problems thof warrant action or
'"V'5II9 'I "
- NRC participatesin the programs of the International Atomic Energy Agency
- Provide for bilateral ration on (IAEA), and the Organization 1or nudear safety, safeg , waste Economic Cooperation and Development's management, and radiological Nudear Energy Agency concemecfwith i protection with:
i physical protection of nudear materials,
- - Argentina, Belgium, Brazil, Canada, reactor safety research and regulatory China, Czech Republic, Egypt, Finland, matters, radiation protection, risk France, Germany, Greece, Hungary, assessment, waste management, transpor-Indonesia, Israel, Italy, Japan, Kazak- tation, safeguards, standards, training, stan, Korea, Lithuania, Mexico, and technical assistance.
. Netherlands, Peru, Philippines, Russia, i
Slovak Republic, Slovenia, South Africa,
- NRC implements IAEA safeguards at Spain, Sweden, Switzerland, Taiwan, NRC-licensed nudear facilities in the U.S.
' and helps strengthen and maintain IAEA Ukraine, and the United Kingdom effectiveness worldwide.
- NRC is assisting Russia, Ukraine Armenia, Kazakstan and Central and
- NRC licenses imports and exports of
, Eastern European countries (Bulgaria, nudear facilities, equipment, material, Hungary, the Czech and Slovak Repub- and related commodities.
lics, and Lithuania) that use Soviet-designed reactors to improve nudear
- NRC is involved in approximately 55 joint international safety research agreements.
safety regulation. These assistance
- efforts are carried out primarily through Participants share the exchange of technical information, funding, technical i training, working group meetings, ,
exchange of specialists, and technical support, and results of specific iomt 4
information exchanges. Projects and programs.
. a4 's M" *, f.o j pm,ps Mg%%kW$$shk'f.W1 p .'/3 ',
M NUCLEAR REGULATORY COMMISSION
,MeAm. awwr.aaer emwa+=3 m44--en+ as a ww eMesa w4e p-**maus a
- 4h-==-sh.e,,AJ--$anJde,Ju-m1mm.--JmA38eh,eL.4 m deh444hN e Me- p 4.ww N mMum.ed.M -m M_e AA Ar.wJ_,.h.wg4.4._4A-4-e.a6SM44, 4J ds-s 44 Me 4 44 A Am A R A Ls.se. .& h 4 l l j . .
q9 g g pjg33 i
Radioactive l WaSie !
f' l
i 4 1 i
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,, ... c -.-ws-m u zseesw wa%n..s _.-esggggg .,3-t b
o s m ygggggsg U.S. Low-Level Radioactive Waste Disposal ,
1 Low-level waste disposal facilities must be
- Exclusion of waste generated outside licensed by either NRC or Agreement States a compact in accordance with health and safety
,
- System of milestones, incentives, and requirements. The facilities are to be penalties to ensure that States and designed, constructed, and operated to meet l compacts will be responsible for their safety standards. The operator of the facility own waste must also extens,ively chorocten,ze the site on 4
, which the facility is located and analyze how Active, Licensed Disposal Facilities: I the facility will perform for thousands of years
- Barnwell, South Carolina (access '
into the future. NRC,s rec 3uirements place authorized for alllow-levelwaste restrictions on the types or waste that can be generators except North Carolina) disposed csf. A new low-level waste d,isposal l facility, typical of those proposed in the east
- Hanford, Washington (restricted access I or midwest United States is shown in Fic,ure to only the Northwest and Rocky Mountain
- 31. Current low-level disposal uses sha low compacts) l land burial sites without concrete vaults.
- Clive, Utoh (restricted to only Class A A roximately 690 thousand cubic feet of low-activity, high-volume waste, e.g.,
low level radioactive waste was disposed of Sli9htly contaminated soil) l in 1995, a 20 percent decrease from the Other Disposal Focilities:
preceding year (see Figures 32 and 33).
Closed Sites:
- The NRC has developed a dossification system for low-level waste based on its
- Beatty, Nevada-closed 1993 l potential hazards, and has specified
- Sheffield, Illinois-dosed 1978 i
disposal and waste form requirements for
- Maxey Flats' Kentucky-dosed 1977
- each of Le three general dasses of waste
- A, B, and C. Class A waste contains
- West Valley, New York-dosed 1975 lower concentrations of radioactive l
4 material than Class C waste.
Disposal Facilities Licensed, l But not Operating: l The volume and radioactivity of waste vary I
- Ward Valley, California (never operated, from year to year based on the types and icensed in 1993, conditioned upon future quantities of waste shipped each year ownership of the site by the State; U.S. 1 (see F,igures 33 and 34). '
Department of Interior and Califomia are
, The low-level Radioactive Waste Policy negotiating land transfer) ,
' ~
Amendments Act(LLRWPAA) of 1985 Disposal Facilities Under License Review by authonzed:
the Agreement State Regulatory Authorities:
- Formation of regional compacts; nine
- Boyd County, Nebraska l l compacts now active. The Texas, Ma.ine, and Vermont compact has been intro-
- Hudspeth County, Texas j duced into Con ress for congressional
- Wake County, North Carolina consent (seeTo le 14 and Figure 35)
, .. - . ~ .
~ _-nm 66 NUCLEAR REGULATORY COMMISSION l
i l
1 RADIOACTIVE WASTE i > .
. . .;;~;pmmgt@yy Figure 31. Low-Level Waste Disposal Site 1
j
- 3 e
3.M
m-
- P s m.
1 g;fn. , , ,
j ff? yng,
. ppm lbwhh5 kN%gp? g ""
- x
- ' w.n h. pf;;'
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t .
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~
a.
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- t . Drainage -
h$ff.hi y 4 sy*,n -%, [ g
,w.,cg 3
w w4 y..p(. ;m a _ n
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a -
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t
- Canisters are stored j in specially designed l q- underground sites. W- W_-- - - -r _. A--- ,
3 ~% -
_-s _
, m . . .
. g g ... c n y ; %.; e E,
- s '-
j l
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o
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l 3@bc.3 . ..,
~4 l h ns tN@NN: N NN: db nlv h yM. j>g M.$.$
sI g
hW-!evel W0ste, i sealedin specialcasks j is shipped to the site 4
by truck.
1 4
1 i
1 j .
- . - ... , . . s ., m gggggg g g w g.gg:;g,,
1 1997 INFORMATION DIGEST 67 1
i . ._ -- - ----
d L .
- MWggEimyi8gg@
Figure 32. 1995 Volume of low-level Radioactive Waste Received at U.S. Disposal Facilities (Cubic Feet)
ACADEMIC l
MEDICAL (2K) 1%
i 4 SOURCE Total Amount Received:
690 Thousand Cubic Feet 33 g
=
r
-1 '. e h (17K) em o e p == 2x I@ [EN J
CLASS Note: Class A waste contains lower concentrations of radioactive material than Class C waste.
- Determination of the classification of waste, however, is a complex process. For more information, see 10 CFR Part 61. Volumes are rounded to the nearest thousand cubic feet and percentages are rounded to the nearest whole number.
Source: DOE 1995 State-by-State Assessment of low-level Radioactive Wastes Received at Commer-cial Disposal Sites (DOE /LLW- 237), (page A-1 and page A-2) m__ _u.___& u,-m u , ,
68 NUCLEAR REGULATORY COMMISSION
1
- RADIOACTIVE WASTE
.- .- hwygigaE?ATEtM f
Figure 33. Volume of low Level Waste Received at U.S. Disposal Facilities, 1984-1995 VOLUME (Thousands of Cubic Feet) 3000 2,681 l 2,619 2500 g f )
2000 1,805 1,842 1,743 1,626 1,428 l 1,369 1500 i!
l 1,143 .-
1000 i 859 792 0 a 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 YEAR i
i 1995 VOLUME BY DISPOSAL FAOllTY Note: Volumes are rounded to the nearest thousand cubic feet and percentages are rounded to the nearest whole number.
Source: DOE 1995 State-by-State Assessment of low-level Radioactive Wastes Received at Commer-l cial Disposal Sites (DOE /LLW-237), Table 2 (page 6)
.. _,m m , ,
- 1997 INFORMATION DIGEST 69 4
K, .
2 gggggggggg;;;;'
l Figure 34. Radioactivity of Low-level Waste Received at U.S. Disposal Facilities,1984-1995 l
RADIOACTMTY (Thousands of Curies) jg 1000 $
867 d 800 749 f 751
.w! h h 643 Fr 600 .
548 p.
270 260 g3 200 q.-
! ! M - 172 0 -
i e W ..
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 YEAR
)
1995 RADIOACTMTY BY DISPOSAL FACILITY l
l
. Note: Radioactivity is rounded to the nearest thousand curies and percentages are rounded to the
! nearest whole number.
f Source: DOE 1995 State-by-State Assessment of low-level Radioactive Wastes Received at Commer-cial Disposal Sites (DOE /LLW-237), Table 2 (page 6) 70 NUCLEAR REGULATORY COMMISSION
I RADIOACTIVE WASTE
- 62.%EMBEri!W l l
Table 14. U.S. Low 4evel Waste Compacts l Percent of TotalVolume Percent of TotalVolume ,
l of Low-levelWaste of Low LevelWaste Compact Disposed in 1995 Compact Disposed in 1995 Nodhwest 20% CentrolMidwest 8% l Alaska illinois" l
, Hawaii Kentucky Idoho lochian 6%
Montana De aware l Oregon Maryland Utah Pennsylvania" Washington
- West Virginia Wyoming Northeast 3%
Sethmstern 2% Connecticut" Anzona New Jersey" California" North Dakota Southeast 28%
South Dakota Alabama Florida Rocky Mountain 10%
Georgia Colorado Mississippi Nevada North Carolina" New Mexico Tennessee Midwest 2% Virginia Indiana Unaffiliated States 19%
lowa District of Columbia <0.1%
Mimsota Maine + 0.4%
Missmn Massachusetts" 1.6%
Wisconsin New Hampshire <0.1%
CentralInterstate 2% New York" 1.5%
Arkansas Puerto Rico 0%
Kansas Rhode Island <0.1%
- 12.6%
- Current Host State (2)
- Selected Host State (12)
+ Pro 3osed compact with Maine, Veron anc Texas (3)
Note: Percentages have been adjusted to reflect the withdrawal of South Carolina from the Southeast Compact in June 1995. Totals do not equal sum of components due to independent rounding.
Source: DOE 1995 State-by-State Assessment of low-level Radioactive Wastes Received at Commercial Disposal Sites (DOE /LLW-237), Table 1 (pages 3 and 4), and the Nudear Regulatory Commisssion
. . . . . . . , . ___ _ . na 1997 INFORMATION DIGEST 71
p ~ ' . , '_ ' _,.._ ). *
~
j Figure 35. U.S. Low-level Waste Compacts l l
8 NORTHWEST N WA
ID ,
i
[A WY n' NORTHEAST OH APPALACHIAN j j IN k ,
ut = g > m DE
- %DC ROCKY CENTRAL MOUNTAIN !NTERSTATE l
- CENTRAL NE Il NV
- MDWEST CO kN y3 KY SOuimSTERN m %
- hr _ ,
SOUTHEAST
,n NC CA SD ,
LAj
__ t f=.- OA AL AZ $ f
", FL a
(
- Active Disposal Site (2) e Disposal Site Under License Review (3) o Licensed Disposal Site - Operations Conditioned Note: Data os of September 1996.
on Site Ownership (Under Litigation) (1) Alaska and Hawaii belong to the Northwest O ApprovedCompact(9) Compact. Puerto Rico is on unaffiliated State.
Texas, Maine, and Vermont Compact D Unaffiliated State (11)
- awaiting Congressional consent.
i Source: Nuclear Regulatory Commission
,, . . mmamaw.srs.mwamm:.
72 NUCl. EAR REGULATORY COMMISSION
RADIOACTWE WASTE nmygggggg:
U.S. High-Level Radioactive Waste Disposal The Nuclear Waste Policy Act of 1982 and Approximately 30,000 metric tons of spent the Nudeor Waste Policy Amendments Act nudear fuel is stored at commercial nudear of 1987 specify a detailed approach for the power reactors os of 1995. By the year disposal of high-level radioactive waste with 2005, this amount is expected to increase to i'
the Department of Energy (DOE) having 52,000 metric tons (see Table 15):
operational responsibility and the NRC having regulatory responsibility for the - All of the operating nuclear power transportation, storage, and geologic reactors are storing used fuel under l disposalof thewaste. NRC license in spent fuel pools (see Figure 37).
- The disposal of high-level radioactive waste rec uires a determination of - In 1990, the NRC amended its
- acceptab e health and environmental regulations to authorize licensees to impacts over thousands of years, store spent fuel at reactor sites in storage casks approved by the NRC.
- Current plans call for the ultimate Seven cask designs have received disposal of the waste in solid form in a certificates of compliance os a result licensed deep, geologic structure, of this rule change (see Apaendix G).
Current operating indepenc ent spent
- The Amendments Act redirected DOE to fuel storage installation sites are investigate only one potential high-level shown on Figure 39.
waste repository at Yucca Mountain, Nevada. DOEis currentlyworkingona - Refer to Appendix H for a list of NRC viability assessment for 1998. (See Figurc Dry Spent Fuel Storage Licensees.
36 for o conceptual design of the Yucco
- Mountain storage plan.) - The NRC is also responsible for approving dual purpose (transporta-
- Ultimately, any high-level waste reposi- tion and interim storage) casks (see tory will require an NRC license. Figure 38).
4 i
e 4
- r- u-ge 1997 INFORMATION DIGEST 73
- - - - . . - - - . - - - . . - . - - - - _ _ - - - - - . . - ~ . -
i !
1 l
^
l
..; 3 3. g ;,3ggg g gg g g l Figure 36. The Yucca Mountain Storage Plan 4
i l Shippb, remo casks are and the
- inner tube with the i Wasle l5 in o IU steel, mu iloyered ~~~------
f Cub >5'[nPPed storage container.
lo the siteby huck i
ortrain. kW i ~# 4 N~ a.% Tunnel:25 feet
! A$
f7
\g;4 397^.. } I
- o '
I
, ,h:-Q;\ tdQ:UQ {M.3l' N a
- .?
c.?x l & w-;% A .m u'm.s ,
Mc9-@ww; y V ~IN mg%,;.,if,
%;1 .
- a %d;7&:;/c;- 3. gy 7h; ' ' ' '
l a
oe.pmv. v ,.cx. ;,s.t. , :o#g s
s JRampto knnels O' ;4 ;
, s.g . .n .. ~. ; o y ,
., e ,.
J i p f ': A .
j . :V W . % .i i sen E g@@ //, . . g&g&gggig.g: jun,g,Jj ' . i' i pig :/
gn p$ ,aa-3
%gI;.f Cross l
- lQ.3 .. k e
.n' ga.: ,
j :;L % ff , .[) ,
f ..
1 Containers are J An automated '
4;1 sbred a the oq ~ '
,7 -$
system sends tunnels, ei ron l sforoge confoiners their side,as shown l underground to
- here,or standing the tunnels.
uprightin holes.
i
- \
i l t
, 1
! I 1
i i
l.
i i Source: Department of Energy and the Nuclear Energy Institute
-muumrmoo<,um.-
- 74 NUCLEAR REGULATORY COMMISSION
i !
1 2' 1
\ .
RADIOACTIVE WASTE
.- . : 3 7.,g g g;4 g g g gggggg g 3 ;
l Figure 37. Nudear Fuel Storage Pool l
I e
i -
l l
l -
N$Ph&Q l O l
I a.
j i i l
l .
l i f,8 j
s.
t j.
k,ro,. f ,
.cs 7 l n
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- l llj
.; I l % g. DEI A:r ~$x; l $d 1 .. _n, -
& I I
j sW. g: < .
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'r
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y
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- [' ig } /
- , p ' Q' Nf*
Commerciallight-water nuclear reactors store spent fuel outside the primary containment in l
a steel-lined, seismically designed concrete pool. The spent fuelis cooled while in the spent l
! fuel storage pool by water that is force-circulated using electrically powered pumps. Makeup water to the pool is provided by other pumps that can be powered from an on-site emer-gency dieselgenerator. Support features, such as v,ater and radiation level detectors, are also provided. Spent fuelis stored in the spent fuel storage pool untilit con he transferred l on-site to a dy cask storage location or transported off-site to a high-luel radioactive waste j
! disposalsite.
i
(
l l t
4 1
i
)
I l Source. Department of Energy and the Nudear Energy Institute
_mm am .au,aw, a.an~ .- n .
l 4
! 1097 INFORMATION DIGEST 75
- ;. p ; Q g g g gg g y; Figure 38. Storage of High-Level Radioactive Waste At nuclear reactors across the country, high-level radioactive waste is kept on site, above ground, in systems basically similar to the me shown here. On-site storage is supposed to be temporary, however, and many plants have already reached capacity.
1 Nuclear reactors are powered by <@$$8i g l enriched uranium-235 fuel. Fission generates heat, which produces steam, :j "EW!4?t@g,;. Vlgh ,
which turns turbines to produce Q:"T . ihl iki? "% ,
electricity. A reactor rated at several dgpi y 4. .$r;M hundred megawatts may contain 100 fMe dM%
>(?%NAby J' $ %?i or more tons of fuel in the form of bullet- A Nh sized pellets loaded intolong rods.
A # 5 /.d$
&19% M$,h M
m e p %%m e- 1 C00 ont [ h-4 5 3
%;w g.N wm ja8 i g 2% www s,a %%Qf
- #s
%i .Y lb')*%
G 3
1t%
Pi Mng W 9{g& B 1 l
7" .
'agj ; gpp j y . . .
\
Fuel ) ._
assembly l
- a ..
~
After about six years, spent fuel assemblies-
+ 3;, 7av- . typically 14 feet long and containing nearly s%h nv;. ,
%sm 200 fuel rods--are removed from the reactor
%j .h 9 fMs@.! and allowed to cool in storage pools for a k! Sidi$$ .
in2%.y few years. At this point, the 900 pound
["N[Q9sl$
ggYg .
%@d[dh!@j?
E $j 7 assemblies contain only about one-fifth the original amount of U-235.
+i, m Ql % l@$
sn~an 3% ' sp$$ s f %- ;
,p I.
g g
i ) 3 76 NUCLEAR REGULATORY COMMISSION
a RADIOACTIVE WASTE
. .1;wrggjgggggg i
i i
i
! e i Once the spent fuel has cooled sundle of somewhat, it is loaded into special :used fuel !
i ' assemblies <
! canisters, each of which is designed to -
hold about two dozen assemblies. Water + --
4 l
and air are removed The canister is %h y ' e.>
filled with inert os, welded shut and $% i3 jim) 4 WWN9?, 0 rigorousi test for leaks. It may then f;7 be plac in a "cosk" for storage or Canisters "EI '87')4 Vd -
l transportation. [$4jjg d I
? .b :b i
.! %s j
n h i
i -
M 4 1 4
- - +sc I
i M i i
llq f h h ' g g W W The canisters con also be stored in above-
' ground concrete bunkers, each of which is about the size of a one-car garage.
Eventually they may be transported elsewhere for storage.
- - .A
- 9; ' '
l .,
+
+
. .. tz s
q.2
' a M
L3e-4 07 .
- f q y[ s ~n i 7
$ >a j &u .
i a
WeBusatrrmwmmasE#smatsu5aamhhacwthA u n 77 1997 INFORMATION DIGEST
.. + 7 . Wi;& A g g? Mig?E % g p % i" Table 15. Spent Nuclear Fuel Stored at U.S. Commercial Nuclear Power l
Reactors-Total Metric Tons by State State 1995 State 1995 Alabama 1,439 Mississippi 299 Arizona 465 Missouri 240 Arkansas 581 Nebraska 353 i California 1,319 New Hampshire 96 Colorado 15 New Jersey 1,187 Connecticut 1,254 New York 1,714 Florida 1,440 North Carolina 1,575 Georgia 1,019 Ohio 422 Illinois 4,292 Oregon 359 lowa 235 Pennsylvania 2,536 Kansas 226 South Carolina 1,789 Louisiana 390 Tennessee 415 Maine 433 Texas 361 1 1
Maryland 608 Vermont 366 l Massachusetts 429 Virginia 1,155 Michigan 1,260 Washington 219 1
Minnesota 648 Wisconsin 809 l Total 29,948 l
Note: Values include spent nuclear fuel stored at formerly operating reactors and exclude spent fuel stored at DOE facilities.
Source: Spent Fuel Discharges From U.S. Reactors (SR/CNEAF/96-01), February 1996
_ _. ._ _ __ a _ _ _ _v u._. ' . .a. . m : o. .
78 NUCLEAR REGULATORY COMMISSION
RADIOACTIVE WASTE
_ . z m - M N F d!# R E D M ai Figure 39. Operating Independent Spent Fuel Storage Installations i
WA -
{I MN N ( NY MA ID WI SD g WY #
MD CA MO KY N, NC 5 M M Ie M NM AA
~
Y, GA MS Al TX LA l
i A Site-SpecificLicense FL 9 GeneralLicense p !
(#) No.ofloadedCasks )
i ARKANSAS MICHIGAN SOUTH CAROUNA 8 Arkansas Nuclear 1,2 (2) S Palisades (13) A Oconee(34)
A H.B. Robinson (8)
COLORADO MINNESOTA A Fort St.Vrain(247) A PrairieIsland 1,2(7) VIRGINIA A Surry1,2(31)
ILUNOIS OHIO i
A GE Morris (Wet Storage) G Davis-Besse(3) WISCONSIN 9 PointBeach(2)
MARYLAND j A Calvert Cliffs 1,2 (14) j l
- Data as of February 12,1997 ;
Source: Nuclear Regulatory Commission
_..w~~wavnas =na ,
l 79 t 1997 INFORMATION DIGEST i
3.g;gggggy Decommissioning Decommissioning is the safe removal of a Other Sites and Failities:
facility from service and reduction of residual radioactivity to a level that permits release of Over the la.st 40 years, operations at the property for unrestricted use and licensed nuclear facilities have caused termination of the license (see Glossary). radiological contamination at a number of sites. This contamination must be reduced or Nuclear Power Reactors: stabilized in a timely and efficient manner to ensure protection of the public and the in July 1996, the NRC issued a revised rule environment before the sites can be released for power reactor decommissioning. The and the license terminated. The NRC's Site rule is intended to clarify the applicability of Decommissioning Management Plan lists 28 i
certain regulations to permanently shut clown sites that require special attention to resolve nuclear power reactors and to provide for decommissioning policy and regulatory public participation in the decommissioning issues, and to prompt timely decommission-process. The NRC is currently overseeing the ing at these sites (see Table 16). The list is decommissioning of 15 nudear power updated annually and published as NUREG-reactors. Refer to Appendix B for their 1444 and Supplement No.1.
decommissioning status.
4 4
i
,....,......<,i....,,....-l.
80 NUCLEAR REGULATORY COMMISSION
l l
RADIOACTIVE WASTE l
~
~: :.N.gfiggjgggg t .
. Table 16. Site Decommissioning Management Plan Site List l
- Company Location l
Advanced Medical Systems,Inc. Cleveland,OH Anne Arundel County /Curtis Bay Anne Arundel County, MD l Army, Department of, Jefferson Proving Ground Jefferson,IN Babcock & Wilcox Parks Township, PA l
BP Chemicals America,Inc, Lima, OH l Brooks & Perkins Detroit, MI l Brooks & Perkins Livonia, MI l Cabot Corporation Boyertown, PA Cabot Corporation Reading, PA Cabot Corporation Revere, PA j Chemetron Corporation, Bert Avenue Cleveland, OH Chemetron Corporation, Harvard Avenue Cleveland, OH
- Clevite Cleveland, OH i Dow Chemical Company Bay City and Midland,MI l
Elkem Metals, Inc. Marietta, OH l
Plainville, MA I Englehard Corporation Fansteel, Inc. Muskogee, OK Hartley and Hartley (Kawkawlin) Landfill Bay County, Mi
{
Heritage Minerals Lakehurst, NJ Horizons, Inc. Cleveland, OH Kaiser Aluminum Tulsa, OK i Kerr McGee Cimarron, OK Kerr McGee Cushing,OK Lake City Army Ammunition Plant (formerly Remington Arms Company) Independence, MO Minnesota Mining and Manufacturing Co. (3M) Pine County, MN Molycorp,Inc. Washington, PA Molycorp,Inc. York, PA Northeast Ohio Regional Sewer District / Southerly Plant - Cleveland, OH
~
- Nuclear Metals,Inc. Concord, MA Permograin Products Media, PA Pesses Comany, METCOA Site Pulaski, PA RMITitanium Company Ashtabula,OH (Continue <
-- _ _ _ - m__.w.:,a w .a u. w .
81
- 1997 INFORMATION DIGEST
- - . _ ~ . .
i
.,,,E/
. /,$ ' '
, Company Location Safety Light Corporation Bloomsburg, PA Schott Glass Technologies Duryea, PA Sequoyah Fuels Corporation Gore, OK Shieldalloy Metallurgical Corporation Cambridge, OH Shieldalloy Metallurgical Corporation Newfield, NJ Watertown Arsenal / Mall Watertown, MA Watertown GSA Watertown, MA Westinghouse Electric Corporation Waltz Mill, PA Whittaker Corporation Greenville, PA Wyman-Gordon Company North Grafton, MA Source: Nuclear Regulatory Commission
= m ._,,,mmm,. . ,.
82 NUCLEAR REGULATORY COMMISSION
k-m eumm_=n~mmame.* a s-s.a wea p a ss-r_,,mm-o_awm.
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s' J ;'
Appendices !
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s
- - - - , _ e . - , . . , - . .. . - _ , _ _ .,,.e ,- _. _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_, e a .,#..
.- 4 .e
- J-_m___m ---, M am.- a--+-A A- 4.6-- .a Jm-n +A*& %e --l*a A - - - - * -h b**+-"d-' -4M**4%4ML -- -- ^^ - h-^ -,
. ,- . g- ,
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84 NUCLEAR REGULATORY COMMISSION
- aaw;;ggggy Abbreviations Used in Appendices ACECOWEN
- Belgian Consortium KWU: KraftwerkUnion,Siemens AG with Westinghouse LIC. TYPE: License Type AE: Archited-Engineer CP: Construction Permit
' AECL- Atomic Energy of Canada, Ltd. OL-FP: Operating License-FullPower AEE: Atomenertoexport OL-LP: Operating License-Low Power AEP: American Electric Power MDC: Maximum Dependable AGN: . Aerojet-GeneralNucleonics Capacity Net Bums & Roe MHl: Mitsubishi HeavyIndustries, Ltd.
B&R:
B&W: Babcock &Wilcox MWe: Megawatts Electrimi BALD: Baldwin Associates MWt: Megawatts Thermal BECH: Bechtel NIAG: Niagara Mohawk Power BRRT: Brown & Root Corporation Boiling-Water Reactor NPF: Nuclear Power Facility BWR:
Combustion Engineering NSP:
COMB:
NSSS:
Northem States Power Company &
Nuclear Steam System Supplier COMM. OP.: Date of CommercialOperation CONTYPE: ContainmentType Desi Ty3e i DRYAMB: D , AmbientPressure 1: GE DRYSUB: D Subatmospheric 2: GE 2 ;
GE 3 i HTG: H -Temperature Gas-Cooled 3:
ICECND: Wet, Ice Condenser 4: GE 4 LMFB Liguid Metal Fast Breeder 5: GEType 5 MARK 1: Wet, MarkI 6: GEType 6 i MARK 2: Wet, Mark 11 2LP: Westin house Two-Loop MARK 3: Wet, Mark 111 3LP: Westin houseThree-loop l Organic Cooled & Moderated 4LP: Westin house Four-loop l OCM:
PTHW. CE: Com tion Engineering l SCE:
Pressure Sodium Coole Tube'd, FastHeavyWater CE80: CE Str., .ird Design i SCGM: Sodium Cooled, Graphite Moderated LLP: B&Wloweredloop Date of Construction Permit issuance RLP: B&W Raised loo 3 CPiSSUED:
Construction Permit Power Reactor OLISSUED: Date of Latest Ful Power ,
CPPR: l Commonwealth Edison Company Operating License CWE:
Critical Assembly PG&E: Pacific Gas & Electric Company CX:
PSE: Pioneer Services & Engineenng DANl: Danielinternational Duke & Bechtel PUBS: Public Service Electric & Gas DBDB:
DER: Design Electric Rating Company Demonstration Power Reactor PWR: Pressurized-Water Reactor DPR:
Duke Power Company R: Research DUKE:
Ebasco S&L- Sorgent & Lundy EBSO:
Expiration Date of Operating license S&W: Stone & Webster EXP.DATE:
Fromatome SBEC: Southern Services & Bechtel FRAM:
SSI: Southem Servicesincorporated FLUR: Fluor Pioneer TNPG: The Nuclear Power Group G&H: Gibbs & Hill Gas-Cooled Reactor TOSH: Toshiba GCR:
General Electric TR: Test Reactor GE:
TVA- Tennessee Valley Authority GHDR: Gibbs & Hill & Durham & Richardson UE&C: United Engineers & Constructors GIL- Gilbert Associates (HR: UniversolTraining Reactor GPC: Georgia Power Company Hitoc,i WDCO: Westinghouse Development HIT:
Pressurized Heavy-Water Reactor Corporation HWR:
WELT: Westinghouse Electric JONES: J. A. Jones KAIS: Kaiser Engineers
-,,_ _.m u .. .
85 1997 INFORMATION DIGEST
A ndix A nagmzggg&pg; U.S. Commercial Nuclear Power Reactors 1991 1996*
Unit Con Type CP issued Average i Operating Utility NSSS OLissued License Copacity location NRC AE Licensed Net Comm. Op Type & Factors Docket Number Region Constructor MWt MDC Exp. Date Number (Percent)
Arkansas Nuclear 1 IV PWR-DRYAMB 2568 0836 12/06/1968 OL-FP 89.3 Enter Operations,Inc. B&W LLP 05/21/1974 DPR 51 79.3 6 MI of Russellville, AR BECH 12/19/1974 83.7 050-00313 BECH 05/20/2014 98.3 81.6 85.6 Arkansas Nuclear 2 IV PWR-DRYAMB 2815 0858 12/06/1972 OL-FP 81.4 Entergy Operations,inc. COMB CE 09/01/1978 NPF-6 73.0 6 M WNW of Russellville, AR BECH 03/26/1980 97.7 050-00368 BECH 07/17/2018 89.5 75.6 93.7 Beaver Voll 1 1 PWR-DRYSUB 2652 0810 06/26/1970 OL-FP 52.2 Duquesne htCo. WEST 3LP 07/02/1976 DPR-66 88.5 l 17 M Wof less, PA S&W 10/01/1976 61.4 1 050-00334 S&W 01/29/2016 77.6 76.7 1 80.0 '
Beaver Volley 2 i PWR DRYSUB 2652 0820 05/03/1974 OL-FP 94.1 Duquesne Light Co. WEST 3LP 08/14/1987 NPF-73 78.4 17 M W of McCandless, PA S&W 11/17/1987 72.4 050-00412 S&W 05/27/2027 97.8 84.'1 66.2 Big Rock Point lll BWR-DRYAMB 0240 0067 05/31/1960 OL FP 83.8 Consumers Power Co. GE 1 05/01/1964 DPR-6 46.1 4 M NE of Charlevoix, M BECH 03/29/1963 72.6 0504)l55 BECH 05/31/2000 69.9 88.0 62.1 Braidwood l lli PWR DRYAMB 3411 1120 12/31/1975 OL FP 50.8 Commonwealtf EdisonCo. WEST ALP 07/02/1987 NPF 72 72.7 24 M SSW o' Joilet,IL S&L 07/29/1988 88.6 050-00456 CWE 10/17/2026 75.3 67.2 70.5 Braidwood 2 Ill PWR-DRYAMB 3411 1120 12/31/1975 OL-FP 66.6 Commonwealth Edison Co. WEST 4LP 05/20/1988 NPF-77 89.0 24 M SSW of Joilet,il S&L 10/17/1988 74.9 050-00457 CWE 12/18/2027 67.6 97.2 81.3 Browns Ferry 1 11 BWR-MARKl 3293 0 05/10/1967 OL-FP 0.0 Tennessee Volley Authority GE 4 12/20/1973 DPR-33 0.0 10 M NW of Decatur, At TVA 08/01/1974 0.0 050-00259 TVA 12/20/2013 0.0 0.0 0.0 j o- --
,-mam--w-r e j
86 NUCLEAR REGULATORY COMMISSION l
\
Appendix A, U.S. Commercial Nuclear Power ReoClors (Continued)
, .- , .- . ( f J.7 ;a / T 1 7 g M Q )
1991 1996*
Con Type CP issued A Unit NS$$ OLissued License Copoc Operahng Utility NRC AE Ucensed Net Comm. Op Type & Factors Locchon n~Let F4 R@ Constructor MWt MDC Exp. Date Number (Percent)
Browns F 2 11 BWR-MARK 1 3293 1065 05/10/1967 OL-FP 40.3 Tennessee Authority GE 4 08/02/1974 DPR-52 89.7 10 MI NW of Decatur, Af. TVA 03/01/1975 61.9 050-00260 1VA 06/28/2014 78.7 98.6 86.0 Browns Ferry 3 11 BWR MARK 1 3293 1065 07/31/1968 OL FP 0.0 Tennessee Valley Authority GE 4 08/18/1976 DPR 68 0.0 10 M1 NW of Decotur, AL TVA 03/01/1977 0.0 050 00296 TVA 07/02/2016 0.0 70.4 94.1 il BWR-MARK 1 2558 0767 02/07/1970 OL-FP 65.4
- Brunswick 1 Carolino Power & Light Co. GE 4 1I/12/1976 DPR 71 27.1 UE&C 03/l8/1977 -1.0 2 MI N of Southport, NC BRRT 09/08/2016 88.6 050 @ 325 85.9 84.7 Brunswick 2 11 BWR-MARK 1 2436 0754 02/07/1970 OL-FP 55.1 Carolino Power & Light Co. GE 4 12/27/1974 DPR-62 19.0 UE&C 11/03/1975 60.2 2 MI N of Southport, NC BRRT 12/27/2014 72.8 050-00324 94.1 78.3 til PWR DRYAMB 3411 1105 12/31/1975 OL FP 65.2 Byron 1 WEST ALP 02/14/1985 NPF 37 92.6 Commonwealth Edison Co.
17MISWof Rockford,IL S&L 09/16/1985 76.0 CWE 10/31/2024 76.7 050-00454 79.5 70.6 lil PWR-DRYAMB 3411 1105 12/31/1975 OL-FP 90.6 Byron 2 WEST 4LP 01/30/1987 NPF-66 72.0 Commonwechh Edison Co.
17 MI SW of Rockford,il S&L 08/21/1987 78.8 CWE 11/06/2026 98.2 050 @ 455 84.5 80.6 Collowoy IV PWR-DRYAMB 3565 1125 04/16/1976 OL-FP 101.3 4
WEST 4LP 10/18/1984 NPF.30 81.9 Union Efectric Co.
10 MI SE of Fuhon, MO BECH 12/19/1984 85.5 DANI 10/18/2024 102.4 050-00483 83.7 90.0 I PWR-DRYAMB 2700 0835 07/07/1969 OL-FP 75.6 Calvert Cliffs 1 COMB CE 07/31/1974 DPR 53 56.8 Bahimore Gas & Electric Co.
BECH 05/08/1975 101.1 40 MI S of AnnopcSs, MD BECH 07/31/2014 64 3 050-00317 96.1 65.8
_ _ ,_ K #"Y 1997 INFORMATION DIGEST 87
a
' . / 8 199ii996-Unit Con Type CPIssued Average OperWing Utility NSSS OLissued ucense Capacity location NRC AE Ucensed Net Conan. Op Type & Fociars Docket Number Region Constructor MWt MDC Exp. Dale Number Penent)
CalveriCliffs 2 I PWR DRYAMB 2700 0840 07/07/1969 OL-FP 50.3 Baltimore Gas & Electric Co. COMB CF 11/30/1976 DPR 69 90.9 40 MI S of Annapolis, MD BECH 04/01/1977 68.6 050-00318 BECH 08/31/2016 89.8 80.3 98.2 Cctwba 1 11 PWR-ICECND 3411 1129 08/07/1975 OL FP 67.4 Duke Power Co. WEST 4LP 01/17/1985 NPF-35 70.9 6 MI NNW of Rock Hill, SC DUKE 06/29/1985 76.6 050-00413 DUKE 12/06/2024 98.9 88.2 63.6 Catawba 2 Il PWRTECND 3411 1129 08/07/1975 OL-FP 73.5 Duke Power Co. WEST ALP 05/15/1986 NPF 52 93.5 6 MI NNW of Rock Hill, SC DUKE 08/19/1986 82.5 050-00414 DUKE 02/24/2026 77.6 80.3 93.1 Clinton 111 BWR-MARK 3 2894 0930 02/24/1976 OL FP 74.2 lilinois Power Co. GE 6 04/17/1987 NPF-62 60.4 6 MI E of Clinton,IL S&L 11/24/1987 72.2 050-00461 BALD 09/29/2026 91.0 75.0 4
65.0 Comanche Peak 1 N PWR DRYAMB 3411 1150 12/19/1974 OL FP 53.2 Texas Utilities Electric Co. WEST 4LP 04/17/1990 NPF-87 68.8 4 MI N of Glen Rose, TX G&H 08/13/1990 71.0 050-00445 BRRT 02/08/2030 93.0 77.5 76.8 Comanche Peak 2 N PWR DRYAMB 3411 1150 12/19/1974 OL-FP -
Texas Utilities Electric Co. WEST 4LP 04/06/1993 NPF-89 -
4 MI N of Glen Rose, TX BECH 08/03/1993 82.8 050 @ 446 BRRT 02/02/2033 52.2
- 91.0 73.0 Cooper IV BWR MARKl 2381 0764 06/04/1968 OL-FP 71.8 Nebraska Public Power District GE 4 01/18/1974 DPR 46 92.8 23 MI S of Nebraska City, NE B&R 07/01/1974 55.5 050 00298 B&R 01/18/2014 33.3 61.7 94.5 Crystal River 3 ll PWR-DRYAMB 2544 0818 09/25/1968 OL-FP 75.9 Florido Power Corp. B&W LLP 01/28/1977 DPR-72 73.5 7 MI NW of Crystal River, FL Gil 03/13/1977 84.5 050 @ 302 JONES 12/03/2016 82.9 101.0 33.6
-mm--,,w mm n 88 NUCLEAR REGULATORY COMMISSION
Appendix A. U.S. Commercial. Nuclear Power Reactors (Continued) a .
Wgggggggy i,9 u ,96-Unit ConType CP issued Average Operahng Utility NS$5 OLissued license Capacity Locahon NRC AE Licensed Net Comm. Op Type & Factors Docliet Number Region Constructor MWt MDC Exp. Date Number (Percent)
Davis Besse ill PWR-DRYAMB 2772 0873 03/24/1971 OL-FP 76.3 Toledo Edison Co. B&W LLP 04/22/1977 NPF 3 99.3 21 MI ESE of Toledo,OH BECH 07/31/1978 79.2 050-00346 BECH 04/22/2017 84.0 100.5 84.3 D. C. Cook 1 Ill PWRICECND 3250 1000 03/25/1969 OL-FP 83.2 Indiano/ Michigan Power Co. WEST ALP 10/25/1974 DPR-58 55.7 11 MI S of Benton Harbor, MI AEP 08/28/1975 100.0 050-00315 AEP 10/25/2014 65.7 61.6 95.3 D. C. Cook 2 Ill PWR lCECND 3411 1060 03/25/1969 OL FP 85.7 1 Indiano/ Michigan Power Co. WEST ALP 12/23/1977 DPR 74 14.9 11 MI S of Benton Harbor, MI AEP 07/01/1978 81.3 050 00316 AEP 12/23/2017 38.0 92.6 86.2 on 1 IV PWR DRYAMB 3338 1073 04/23/1968 OL FP 78.3 Diablo Pacific Gas Cany& Electric Co. WEST 4LP 11/02/1984 DPR-80 79.0
. 12 MIWSWof Son Luis PG&E 05/07/1985 96.0 Obispo,CA PG&E 09/22/2021 78.4 050-00275 79.2 93.2 on 2 IV PWR-DRYAM8 3411 1087 12/09/1970 OL FP 81.0 Diablo Cany& Electric Co.
Pacific Gas WEST ALP 08/26/1985 DPR-82 96.9 12 MIWSWof Son Luis PG&E 03/13/1986 81.8 Obispo,CA PG&E 04/26/2025 82.9 050-00323 92.6 83.1 Dresden 2 Ill BWR-MARK 1 2527 0772 01/10/1966 OL FP 43.9 Commonwealth Edison Co. GE 3 02/20/1991 DPR 19 55.4 9 MI E of Morris,il S&L 06/09/1970 45.0 05040237 UE&C 01/10/2006 60.2 27.5 31.4 Dresden 3 Ill BWR MARK 1 2527 0773 10/14/1966 OL-FP 37.9 Commonwealth Edison Co. GE 3 03/02/1971 DPR 25 23.5 j 9 MI E of Morris,IL S&L 11/16/1971 73.3 -
i 050-00249 UE&C 01/12/2011 24.0 51.2 43.4 Duane Arnold 111 BWR MARK 1 1658 0520 06/22/1970 OL-FP 91.9 Inc. GE 4 02/22/1974 DPR-49 73.7 IES 8 MINW Utilities,f o Cedar Rapids,IA BECH 02/01/1975 71.7 !
050-00331 BECH 02/21/2014 91.1 l 82.8 l 86.2 i (Continued) 1997 INFORMATION DIGEST 89
/.l?(4 & & $$ D0[?,
1991 1996' Unit Con Type CP issued Average Operahng Utility NSSS OLissued License Copacity locahon NRC AE Ucensed Net Comm. Op Type & Factors Docket Number Region Constructor MWt MDC Exp. Date Numlmr (Percent)
Edwin L Hatch 1 ll BWR MARK 1 2558 0805 09/30/1969 OL FP 72.4 Southern Nudear Operating Co. GE 4 10/13/1974 DPR 57 94.6 11 M N of Boxley, GA BECH 12/31/1975 76.7 050-00321 GPC 08/06/2014 84.8 99.6 80.7 Edwin I. Hatch 2 11 BWR MARKI 2558 0809 12/27/1972 OL FP 73.8 Southern Nudear Operating Co. GE 4 06/13/1978 NPF 5 69.8 11 M N of Baxley, GA BECH 09/05/1979 75.4 050-00366 GPC 06/13/2018 78.7 75.0 98.8 Fermi 2 Ill BWR-MARKI 3430 0876 09/26/1972 OL FP 66.7 Detroit Edison Co. GE 4 07/15/1985 NPF-43 79.0 25 M NE of Tolede, OH S&L 01/23/1988 87.2 050-00341 DANI 03/20/2025 0.0 66.9 62.3 Fort Colhoun IV PWR-DRYAMB 1500 0478 06/07/1968 OL FP 77.6 Omaho Public Power District COMB CE 08/09/1973 DPR 40 60.4 19 M N of Omaha, NE GHDR 09/26/1973 74.1 050 00285 GHDR 08/09/2013 98.4 80.4 74.5 Ginna i PWR-DRYAMB 1520 0470 04/25/1966 OL-FP 84.6 Rochester Gas & Electric Corp. WEST 2LP 12/10/1984 DPR 18 84.4 20 MI NE of Rochester, NY Gil 07/01/1970 85.0 050-00244 BECH 09/18/2009 81.9 88.4 70.2 Grand Gulf 1 IV BWR-MARK 3 3833 1179 09/04/1974 OL-FP 91.1 Entergy Operations,Inc. GE 6 11/01/1984 NPF-29 81.4 25 Mi S of Vicksburg, MS BECH 07/01/1985 78.9 050-00416 BECH 06/16/2022 96.0 79.2 89.3 Haddam Neck" i PWR-DRYAMB 1825 0560 05/26/1964 OL FP 74.9 CT Yankee Atomic Power Co. WEST 4LP 12/27/1974 DPR 61 78.9 13 M E of Meriden, CT S&W 01/01/1968 76.2 05000213 5&W 06/29/2007 77.4 74.5 56.2 H. B. Robinson 2 11 PWR DRYAMS 2300 0683 04/13/1967 OL-FP 80.0 Carolina Power & Light Co. WEST 3tP 09/23/1970 DPR 23 67.7 l 26 MI from Florence, SC EBSO 03/07/1971 70.0 t 050-00261 EBSO 07/31/2010 77.7 86.1 91.0
)
-=mmeum,awazunmsw l
90 NUCLEAR REGULATORY COMMISSION
]
j Appendix A, U1 Commercial Nuclear Power Reactors (Continued)
WdSMEBERM I 1
l l
1991 1996* l Unit Con Type CP issued Average i Operating thility NSSS OLissued License Capority i
& I location NRC AE Licensed Not Comm.Op T Factors Docket Number Region Constructor MWt MDC Exp. Date (Percent)
Hope Creek 1 i BWR-MARK 1 3293 1031 11/04/1974 OL-FP 81.9 Public Service Electric & Gas Co. GE 4 07/25/1986 NPF57 77.9 18 M SE of Wilmington, DE BECH 12/20/1986 97.7 050-00354 BECH 04/11/2026 78.9 l 78.2 74.6 Indian Point 2 i PWR-DRYAMB 3071 0951 10/14/1966 OL FP 47.5 Consolidated Edison Co. WEST 4LP 09/28/1973 DPR 26 95.7 24 M N of New York City, NY UE&C 08/01/1974 72.0 ,
050-00247 WDCO 09/28/2013 92.8 4
59.3 94.9 i
Indian Point 3 i PWR-DRYAMB 3025 0965 08/13/1969 OL-FP 86.4 '
Power Authority of the State WEST 4LP 04/05/1976 DPR 64 56.2 of New York UE&C 08/30/1976 14.1 24 M N of New York City,NY WDCO 12/15/2015 0.0 050-00286 17.4 69.3 James A. FitzPatrick I BWR MARK 1 2536 0762 05/20/1970 OL FP 49.4 1 Power Authority of the State GE 4 10/17/1974 DPR-59 0.0 of New York S&W 07/28/1975 69.5 8 M NE of Oswego, NY S&W 10/17/2014 73.4 050-00333 70.7 78.6 Joseph M. Farley 1 ll PWR DRYAMB 2652 0812 08/16/1972 OL FP 75.9 )
Southern Nuclear Operating Co. WEST 3LP 06/25/1977 NPF-2 79.2 18 M SE of Dothon, AL SSI 12/01/1977 96.6 050-00348 DANI 06/25/2017 85.2 l 80.7 l 100.1 l 1
Joseph M. Farley 2 ll PWR-DRYAMB 2652 0822 08/16/1972 OL-FP 93.4 Southern Nuclear Operating Co. WEST 3LP 03/31/1981 NPF-8 74.7 18 MI SE of Dothon, AL SSI 07/30/1981 72.7 050-00364 BECH 03/31/2021 99.3 70.7 79.5 Kewounee ill PWR-DRYAMB 1650 0511 08/06/1968 OL-FP B2.7 Wisconsin Public Service Corp. WEST 2LP 12/21/1973 DPR 43 87.7 27 M E of Green Boy,WI PSE 06/16/1974 85.3 050-00305 PSE 12/21/2013 88.5 84.7 70.6 til BWR MARK 2 3323 1036 09/10/1973 OL FP 75.2 to Solle Couny 1 Comcs,wedo. Edison Co. GE 5 08/13/1982 NPF 11 70.9 11 M SE of Ottawa,IL S&L 01/01/1984 79.3 050 4)373 CWE 05/17/2022 54.2 92.2 36.3 (Continued)
- c. - - . ,__,nn~
1997 INFORMATION DIGEST 91
. . j y ,f 1 % $ f g g?g y p 1991 1996' Unit Con Type CPissued Average Operahng Utility NSSS OLlssued License Capacity l locahon NRC AE Licensed Not Comm. Op Type & Fodors l Docket Number Region Construdor MWt MDC Exp. Dole Nuenber (Pment) I lo Solle County 2 111 BWR MARK 2 3323 1036 09/10/1973 OL FP 96.0 Commonwealth Edison Co. GE 5 03/23/1984 NPF 18 63.5 11 Ml SE of Ottowo,il S&L 10/19/1984 64.4 050-00374 CWE 12/16/2023 92.9 l 65.8 62.0 ,
Limerick 1 l BWR MARK 2 3458 1105 06/19/1974 OL FP 88.0 j Philodelphia Electric Co. GE 4 08/08/1985 NPF 39 67.2 1 21 MINW of Philadelphia,PA BECH 02/01/1986 94.6 050-00352 BECH !0/26/2024 85.0 88.2 84.2 i
Limerick 2 I BWR-MARK 2 3458 1115 06/19/1974 OL-FP 77.3 l Philadelphia Electric Co. GE 4 08/25/1989 NPF-85 91.6 l 21 MINWof Philadelphia,PA BECH 01/08/1990 80.8 050 00353 BECH 06/22/2029 92.7 86.2 91.9 l l'
Moine Yankee 1 PWR-DRYAMB 2700 0860 10/21/1968 OL-FP 85.1 Moine.Yonkee Alomic Power Co. COMB CE 06/29/1973 DPR 36 70.9 ,
10 Ml N of Bath, ME S&W 12/28/1972 76.2 050-00309 S&W 10/21/2008 88.0 2.6 67.0 McGuire 1 11 PWR-ICECND 3411 1129 02/23/1973 OL-FP 69.2 Duke Power Co. WEST 4LP 07/08/1981 NPF 9 75.5 17 Mi S of Charlotte, NC DUKE 12/01/1981 55.8 050-00369 DUKE 06/12/2021 69.5 89.6 86.3 McGuire 2 11 PWR-ICECND 3411 1129 02/23/1973 OL FP 96.2 Duke Power Co. WEST 4LP 05/27/1983 NPF 17 68.4 7 Ml S of Charlotte, NC DUKE 03/01/1984 6'.8 50-00370 DUKE 03/03/2023 91 9..,
73.2 Millstone 1 1 BWR-MARK 1 2011 0641 05/19/1966 OL FP 30.6 Northeast Nuclear Energy Co. GE 3 10/31/1986 DPR-21 62.9 3.2 MlWSW of New London, CT EBSO 03/01/1971 93.9 050-00245 EBSO 10/06/2010 58.5 1 77.6 j
-0.5 ;
Millstone 2 I PWR DRYAMB 2700 0871 12/11/1970 OL-FP 52.2 l Northeast Nuclear Energy Co. COMB CE 09/26/1975 DPR 65 35.3 .
3.2 MI WSW of New London, CT BECH 12/26/1975 82.3 050-00336 BECH 07/31/2015 47.8 l 35.5 :
13.4
)
1 92 NUCLEAR REGULATORY COMMISSION i
i
)
Appendix A. U.S. CommerCiol Nuclear Power Reactors (Continued)
. .. 1< 9..IllM >@$$[5$3@iM5
~
i,9i.i,96-Unit Con Type CPissued Average Operaling Utility NSSS OL issued License Copacity 4
Locahon NRC AE licensed Not Comm. Op Type & Factors Docket Numlwr Region Constructor MWt MDC Exp. Dole Number M Millstone 3 I PWR-DRYSUB 3411 1137 08/09/1974 OL-FP 28.5 Northeast Nuclear Energy Co. WEST 4LP 01/31/1986 NPF-49 65.8 3.2 MI WSW of New London, CT S&W 04/23/1986 65.1 050-00423 S&W 11/25/2025 94.5 80.2 24.3 Monticello !!! BWR-MARK 1 1670 0544 06/19/1967 OL-FP 76.6 Northern Siates Power Co. GE 3 01/09/1981 DPR 22 94.6 30 MI NW of Minneapolis, MN BECH 06/30/1971 82.3 050-00263 BECH 09/08/2010 84.3 101.3 81.6 Nine Mile Point 1 I BWR-MARK 1 1850 0565 04/12/1965 OL-FP 71.9 Niagoro Mohawk Power Corp. GE 2 12/26/1974 DPR-63 54.2 6 M NE of Oswego, NY NIAG 12/01/1969 88.0 050-00220 S&W 08/22/2009 99.4 87.0
, 94.2
, Nine Mile Point 2 I BWR-MARK 2 3467 1105 06/24/1974 OL-FP 68.6 Niagoro Mohawk Power Corp. GE 5 07/02/1987 NPF 69 54.5 l I
6 MI NE of Oswego, NY S&W 03/11/1988 82.6 050-00410 S&W 10/31/2026 96.0 78.1 89.6 Nerth Anno 1 11 PWR-DRYSUB 2893 0893 02/19/1971 OL FP 70.5 j VirDi nia Electric & Power Co. WEST 3LP 04/01/1978 NPF 4 70.6 40MiNWof Richmond,VA S&W 06/06/1978 73.1 050 00338 S&W 04/01/2018 86.2 99.8 88.5
- North Anno 2 11 PWR-DRYSUB 2893 0897 02/19/1971 OL-FP 96.5 Virginia Electric & Power Co. WEST 3tP 08/21/1980 NPF-7 79.2 i 40MINWof Richmond,VA S&W 12/14/1980 78.3 l 4 050-00339 S&W 08/21/2020 96.4
77.2 77.7 Oconee 1 11 PWR DRYAMB 2568 0846 11/06/1967 OL FP 81.2 Duke Power Co. B&W LLP 02/06/1973 DPR-38 84.5 30 MI W of Greenville, SC DBDB 07/15/1973 88.0 050-00269 DUKE 02/06/2013 82.1 85.8 74.8 Oconee 2 11 PWR DRYAMB 2568 0846 11/06/1967 OL-FP 100.2 Duke Power Co. B&W LLP 10/06/1973 DPR-47 80.0 i 30 MIW of Greenville, SC DBDB 09/09/1974 84.1 050-00270 DUKE 10/06/2013 83.0 94.1 59.4 l (Continued) 1997 INFORMATION DIGEST 93
~
. ;/((%.}jf } QQQi]Q Qf' I
1991 1996*
Unit Con Type CP issued Average Operahng Utility NSSS OLissued License Capacity j location NRC AE bcensed Net Comm. Op Type & Factors l Docket Number Region Consin,ctor MWt MDC Exp. Date Number (Percent) I Oconee 3 11 PWR-DRYAMB 2568 0846 11/06/1967 OL FP 75.4 Duke Power Co. B&W LLP 07/19/1974 DPR 55 73.3 30 M W of Greenville, SC DBDB 12/16/1974 99.8 050-00287 DUKE 07/19/2014 76.5 87.3 ,
73.3 J
Oyster Creek I BWR-MARKl 1930 0619 12/15/1964 OL-FP 54.7 GPU Nuclear Corp GE 2 07/02/1991 DPR 16 84.5 l
9 M S of Toms River, NJ B&R 12/01/1969 87.3 050-00219 B&R 12/1'.'2009 67.8 95.8 79.8 Polisades lli PWR-DRYAMB 2530 0730 03/14/1967 OL-FP 76.2 Consumers Power Co. COMB CE 02/21/1991 DPR-20 75.9 5 Mi S of South Haven, MI BECH 12/31/1971 55.4 050-00255 BECH 03/14/2007 70.6 76.0 82.9 PoloVerde 1 IV PWR-DRYAMB 3800 1227 05/25/1976 OL FP 87.1 Arizona Public Service Co. COMB CE80 06/01/1985 NPF 41 66.4 36 M W of Phoenix, AZ
)
BECH 01/28/1986 70.3 '
050-00528 BECH 12/31/2024 91.4 79.3 80.8 PoloVerde 2 IV PWR-DRYAMB 3876 1227 05/25/1976 OL-FP 77.3 Arizona Public Service Co. COMB CE80 04/24/1986 NPF 51 94.4 36 M W of Phoenix, AZ BECH 09/19/1986 47.9 050-00529 BECH 12/09/2025 61.5 84.4 86.7 Polo Verde 3 IV PWR-DRYAMB 3876 1230 05/25/1976 OL-FP 70.3 Arizona Public Service Co. COMB CE80 11/25/1987 NPF 74 78.2 36 M W of Phoenix, AZ BECH 01/08/1988 87.8 050 00530 BECH 03/25/2027 63.8 87.1 !
99.9 ;
Peach Bottom 2 i BWR MARK 1 3458 1093 01/31/1968 OL-FP 54.8 PECO Energy Co. GE 4 12/14/1973 DPR-44 61.2 l 17.9 MI $ o'flancaster, PA BECH 07/05/1974 83.4 I 050-00277 08/08/2013 77.8 BECH 97.8
)
79.8 Peach Bottorn 3 I BWR-MARK 1 3458 1093 01/31/1968 OL-FP 56.1 4 PECO Energy Co. GE 4 07/02/1974 DPR-56 79.0 l 17.9 M S of Lancaster, PA BECH 12/23/1974 69.6 050-00278 BECH 07/02/2014 97.8 78.0 98.2
, w w x v w c w n , ,.
?d NUCLEAR REGULATORY COMMISSION
Appendix'A. U.S. CommerCiol Nuclear Power ReoCtors (Continued)
- MMSMLEMGMA m i m 6-Unit Con Type CP issued Average Operonng thility NSSS OL issued License Copacity locahon NRC AE Licensed Net Comm. Op Type & Factors Docket Number Region Constructor MWt MDC Exp. Date Number (Percent)
Perry i Ill BWR MARK 3 3579 1160 05/03/1977 OL-FP 87.9 Cleveland Electric illuminating Co. GE 6 11/13/1986 NPF 58 70.0 7 MI NE of Painesville, OH Gil 11/18/1987 38.9 050-00440 KAIS 03/18/2026 45.0 89.2 73.1 Pilgrim 1 I BWR-MARK 1 1998 0670 08/26/1968 OL FP 58.4 Boston Edison Co. GE 3 09/15/1972 DPP-35 80.6 4 Mt SE of Plymouth, MA BECH 12/01/1972 74.0 050 00293 BECH 06/08/2012 65.2 76.4 90.5 Point Beach 1 Ill PWR-DRYAMB 1519 0485 07/19/1967 OL-FP 85.4 Wisconsin Electric Power Co. WEST 2LP 10/05/1970 DPR 24 84.6 13 M NNW of Monitowoc,WI BECH 12/21/1970 89.5 050-00266 BECH 10/05/2010 91.9 89.3 97.7
. Point Beach 2 lil PWR-DRYAMB 1519 0485 07/25/1968 OL FP 86.8 Wisconsin Electric Power Co. WEST 2LP 03/08/1973 DPR 27 86.1 13 MI NNW of Monitowoc, WI BECH 10/01/1972 90.5 050-00301 BECH 03/08/2013 88.3 79.7 69.2 PrairieIsland 1 Ill PWR-DRYAMB 1650 0513 06/25/1968 OL FP 90.4 Northem States Power Co. WEST 2LP 04/05/1974 DPR 42 79.1 28 Ml SE of Minneapolis, MN FLUR 12/16/1973 98.9 050 00282 NSP 08/09/2013 82.7 100.6 83.0 Prairie Island 2 I;l PWo, DRYAMB 1650 0512 06/25/1968 OL-FP 102.3 Northern States Power Co. WEST 2LP 10/29/1974 DPR 60 73.3 28 MI SE of Minneapolis, MN FLUR 12/21/1974 85.0 050-00306 NSP 10/29/2014 101.5 88.5 99.7 Quod Gties 1 Ill BWR-MARK 1 2511 0769 02/15/1967 OL-FP 52.5 Commonwealth Edison Co. GE 3 12/14/1972 DPR 29 61.7 20 MI NE of Moline,il S&L 02/18/1973 74.9 050-00254 UE&C 12/14/2012 24.8 87.4 39.7 Ouod Cities 2 Ill BWR-MARK 1 2511 0769 02/15/1967 OL FP 78.5 Commonwealth Edison Co. GE 3 12/14/1972 DPR 30 57.7 20 MI NE of Moline,il S&L 03/10/1973 46.2 050-00265 UE&C 12/14/2012 59.6 37.1 69.1 (Continued) 1997 INFORMATION DIGEST 95
.-. _ ~- .
'. ^
!M$1&N5?k$'
1991 1996*
Unit Con Type CP issued Average Opemhng Utility NSSS OLissued license Capacity location NRC AE Licensed Net Comm.Op Type & Fachrs Declwt Nomint Region Constructor MWt MDC Exp. Date Number (Percent)
River Bend 1 N BWR MARK 3 2894 0936 03/25/1977 OL FP 81.6 Entergy Operations,Inc GE 6 11/20/1985 NPF 47 33.6 24 M NNW of Baton Rouge, LA S&W 06/16/1986 64.1 050-00458 S&W 08/29/2025 59.6 96.7 83.4 Salem i I PWR DRYAMB 3411 1106 09/25/1968 OL-FP 70.3 Public Service Electric & Gas Co. WEST 4LP 12/01/1976 DPR 70 54.5 18 M S d Wilmington, DE PUBS 06/30/1977 60.5 4 050-00272 UE&C 08/13/2016 59.3 26.0 0.0 Salem 2 i PWR DRYAMB 3411 1106 09/25/1968 OL FP 79.1 Public Service Electric & Gas Co. WEST 4LP 05/20/1981 DPR-75 48.6 18 M S d Wilmington, DE PUBS 10/13/1981 57.2 050 00311 UE&C 04/18/2020 57.8 20.8 0.0
, Son Ondre 2 IV PWR-DRYAMB 3390 1070 10/18/1973 OL FP 61.5 Southern Califomic Edison Co. COMB CE 09/07/1982 NPF 10 93.6 4
& San Diego Gas & Electric Co. BECH 08/08/1983 81.6 4 Mi SE of Son Clemente,CA BECH 10/18/2013 99.3 050 00361 69.1 91.0 San Onofre 3 IV PWR-DRYAMB 3390 1080 10/18/1973 OL-FP 91.9 Southem California Edisor.Co. COMB CE 09/16/1983 NPF 15 72.0 i
& Son Diego Gas & Electic Co. BECH 04/01/1984 75.2 l 4 Mi SE of San demente, CA BECH 10/18/2013 97.0 050-00362 79.3
,' 93.2 Seabrook 1 1 PWR DRYAMB 3411 1158 07/07/1976 OL FP 67.6 North Allontic Energy WEST 4LP 03/15/1990 NPF 86 77.9 Service Corp. UE&C 08/19/1990 89.8 13 M S d Porthsmouth, NH UE&C 10/17/2026 61.6 050-00443 83.1 i 96.8 i e l Sequoyoh1 11 PWR-lCECND 3411 1117 05/27/1970 OL-FP 73.9 Tennessee Valley Authority WEST ALP 09/17/1980 DPR 77 84.8 9.5 M NE d Chattanooga, TN TVA 07/01/1981 12.6 050-00327 TVA 09/17/2020 62.7 70.1 94.7
, Sequoyoh 2 11 PWR ICECND 3411 1117 05/27/1970 OL-FP 94.8 Tennessee Volley Authority WEST ALP 09/15/1981 DPR 79 73.8 9.5 M NE d Chattanooga,TN TVA 06/01/1982 21.0 050 @ 328 TVA 09/15/2021 60.2 91.7 78.3
. . .-:.- ammmwumn c:, ~
96 NUCLEAR REGULATORY COMMISSION
Appendix A. U.S. Commercial Nuclear Power ReoCtors (Continued)
. - eggregggggg 1991 1996' Unit - Con Type CP issued Avemge Opwohng thility NSSS otissued license Copacity locahon NRC AE Licensed Net Comm. Op Type & Fodors Docket Number Region Construdor MWt MDC Exp. Date Number (Percent)
Sheoron Harris 1 11 PWR DRYAMB 2775 0860 01/27/1978 OL-FP 78.6 Carolino Power & Light Co. WEST 3LP 01/12/1987 NPF 63 71.6 20 MI SWof Raleigh, NC EBSO 05/02/1987 99.9 050-00400 DANI 10/24/2026 80.4 79.2 93.6 South Texas Pro ect 1 IV PWR DRYAMB 3800 1251 12/22/1975 OL-FP 65.8
, Houston Light & Power Co. WEST 4LP 03/22/1988 NPF-76 66.1 12 MlSSW Boy City, TX BECH 08/25/1988 6.1 050-00498 EBSO 08/20/2027 75.3 4 84.9 93.1 South Texas Pro ect 2 IV PWR-DRYAMB 3800 1251 12/22/1975 OL FP 66.2 Houston ligh & Power Co. WEST 4LP 03/28/1989 NPF 80 94.1 12 MiSSW City, TX BECH 06/19/1989 6.3 050-00499 EBSO 12/15/2028 54.7 90.6 95.2 d
St. Lucie 1 ll PWR-DRYAMB 2700 0839 07/01/1970 OL FP 78.8 Florida Power & Light Co. COMB CE 03/01/1976 DPR 67 96.9 12 MI SE of Ft. Pierce, FL EBSO 12/21/1976 73.9 4 050-00335 EBSO 03/01/2016 84.1 74.9 70.9 St. Lucie 2 11 PWR-DRYAMB 2700 0839 05/02/1977 OL FP 101.1 Florida Power & Light Co. COMB CE 06/10/1983 NPF 16 73.7 ,
64.1 l 12 Mi SE of Ft. Pierce, FL EBSO 08/08/1983 i
050 00389 EBSO 04/06/2023 76.3 71.9 94.8 l l
Summer 11 PWR-DRYAMB 2900 0945 03/21/1973 OL FP 68.9 i South Carolino Electric & Gas Co. WEST 3tP 11/12/1982 NPF 12 96.7 1 26 M! NW of Columbio, SC Gil 01/01/1984 78.7 050-00395 DANI 08/06/2022 57.3 97.5 88.0 ll PWR-DRYSUB 2546 0801 06/25/1968 OL-FP 96.3 Surry 1 ,
Virginia Electric & Power Co. WEST 3tP 05/25/1972 DPR 32 76.1 17MI NW of Newport News,VA S&W 12/22/1972 91.1 050-00280 S&W 05/25/2012 71.4 83.6 101.4 11 PWR-DRYSUB 2546 0801 06/25/1968 OL-FP 58.3 Surry 2 Virginio Electric & Power Co. WEST 3LP 01/29/1973 DPR 37 93.7 17 MI NW ol Newport News, VA S&W 05/01/1973 66.4 050-00281 S&W 01/29/2013 91.5 80.1 86.4 (Continued) 1997 INFORMATION DIGEST 97
.Lik k lgM Q & $
1991 1996' Unit Con Type CP issued Average Operahng thility NSSS OL 15 sued License Copacity locahon NRC AE Ucensed Net Comm. Op Type & Factors Docket Nunker Region Constructor MWt MDC Exp. Date Number (Percent)
Susquehanno1 I BWR MARK 2 3441 1090 11/02/1973 OL FP 96.8 d
Pennsylvania Power & Light Co. GE 4 11/12/1982 NPF-14 70.0 7 M NE of Berwick, PA BECH 06/08/1983 57.0 050-00387 BECH 07/17/2022 92.4 78.8 81.0 Susquehanno 2 l BWR MARK 2 3441 1094 11/02/1973 OL-FP 76.9 Pennsylvania Power & Light Co. GE 4 06/27/1984 NPF 22 78.3 7 M NE of Berwick, PA BECH 02/12/1985 91.2
- 050-00388 BECH 03/23/2024 72.8 85.5 95.0 Three MileIsland 1 I PWR DRYAMB 2568 0786 05/18/1968 OL-FP 80.1 GPU Nuclear Corp. B&W LLP 04/19/1974 DPR 50 100.5 10 MI SE of Harrisburg, PA GIL 09/02/1974 86.6 050-00289 UE&C 04/19/2014 95.7 92.8 102.8 Turkey Point 3 11 PWR-DRYAMB 2300 0693 04/27/1967 OL FP 22.5 Florida Power & Light Co. WEST 3tP 07/19/1972 DPR-31 58.4 1 25 M S of Miami, FL BECH 12/14/1972 97.0 050-00250 BECH 07/19/2012 84.4 l 89.5 97.3 Turkey Point 4 11 PWR-DRYAMB 2300 0693 04/27/1967 OL-FP 13.7 Florida Power & Light Co. WEST 3LP 04/10/1973 DPR 41 79.3 25 M S of Miami, FL BECH 09/07/1973 81.4 050-00251 BECH 04/10/2013 83.0 ,
99.5 87.7 Vermont Yankee l BWR MARK 1 1593 0510 12/11/1967 OL FP 93.1 VT YankeeNuclearPowerCorp. GE 4 02/28/1973 DPR 28 84.4 ,
5 M S of Brottleboro, VT EBSO 11/30/1972 76.4 i 050-00271 EBSO 03/21/2012 97.8 l 86.7 l 84.8 I Vogtle 1 Il PWR-DRYAMB 3565 1162 06/28/1974 OL-FP 77.8 Southern Nudear Operating Co. WEST 4LP 03/16/1987 NPF-68 96.7 26 M SE of Augusta, GA SBEC 06/01/1987 85.7 050-00424 GPC 01/16/2027 86.1 98.1 79.8 Vogtle 2 11 PWR DRYAMB 3565 1162 06/28/1974 OL-FP 92.6 Southern Nuclear Operating Co. WEST 4LP 03/31/1989 NPF-81 79.7 26 M SE of Augusta, GA SBEC 05/20/1989 87.1 050-00425 GPC 02/09/2029 91.2 90.0 88.5
-- _---n_.,mmmwww 98 NUCLEAR REGULATORY COMMISSION
Appendix A. U.S. Commercial Nuclear Power ReoCtors (Continued) l
- ps,kygggij l l
199M996- 1 Unit Con Type CP Issued Average Operating Utility NSSS OLissued ucense Copacity locahon NRC AE Licensed Net Comm. Op Type & Factors Docket Number Region Constructor MWt MDC Exp. Date Numinr (Percent)
- Washington Nuclear 2 IV BWR-MARK 2 3486 1107 03/19/1973 OL-FP 44.3 Washington Public Power GE 5 04/13/1984 NPF-21 59.7 Supply Systern B&R 12/13/19B4 75.0 12 M NW of Richland, WA BECH 12/20/2023 70.8 050-00397 72.5 57.1 Waterford 3 IV PWR DRYAMB 3390 1104 11/14/1974 OL-FP 77.3
. Entergy Operations,Inc. COMB CE 03/16/1985 NPF-38 80.7 20 M W of New Orleans, LA EBSO 09/24/1985 97.0 050-00382 EBSO 12/18/2024 84.2 82.4 94.5 Watts Bar 1 Il PWR-ICECND 3411 1117 01/23/1973 OL -
Tennessee VaHey Authority WEST 4LP 02/07/1996 NPF-90 -
10 Ml S of Spnng City,TN IVA 05/27/1996 -
050 00390 TVA 11/09/2035 -
j
- 89.1
', Wolf Creek I IV PWR DRYAMB 3565 1163 05/31/1977 OL-FP 58.9 I Wolf Creek Nuclear Operating WEST 4LP 06/04/1985 NPF-42 85.5 Corp. BECH 09/03/1985 79.6 1 3.5 M NE of Burlington, KS DANI 03/11/2025 84.7 050-00482 98.7 80.2 Zion 1 111 PWR DRYAMB 3250 1040 12/26/1968 OL-FP 46.8 Commonwealth Edison Co. WEST 4LP 10/19/1973 DPR 39 45.0 40 M N of Chicago,IL S&L 12/31/1973 77.1 050-00295 CWE 04/06/2013 45.5 71.0 l 80.2 ;
i Zion 2 Ill PWR-DRYAMB 3250 1040 12/26/1968 OL-FP 56.3 Commonwechh Edison Co. WEST 4LP 11/14/1973 DPR 48 58.7 40 M N of Chicago,IL S&L 09/17/1974 58.1 050-00304 CWE 11/14/2013 67.5 65.0 61.5
- Note: Average capacity factors are listed in year order starting with 1991. The 1998 Information i Digest will drop 1991 average capacity factor and only show 6 years of data.
"Haddam Neck prematurely shut down in December 1996.
Source: Nuclear Regulatory Commission and licensee data as compiled by the Nuclear Regulatory Commission.
.m --mmm 1997 INFORMATION DIGEST 99
Appendix B m c.+:; g gggga g; l
U.S. Commercial Nuclear Power Reactors Formerly Licensed To Operate Decommissionina .
Unit Con Type OLissued Alternative Selected I
- location MWt Shutdown Current Status !
i Bonus
- BWR 04/02/1964 ENTOMB Punto Higuera, PR 50 06/01/1968 ENTOMB CVTR " PTHW 11/27/1962 SAFSTOR Parr, SC 65 01/01/1967 SAFSTOR Dresden 1 BWR 09/28/1959 SAFSTOR Morris, IL 700 10/31/1978 SAFSTOR Elk River
- BWR 11/06/1962 DECON i Elk River, MN 58 02/01/1968 DECON Completed
- Fermi 1 SCF 05/10/1963 SAFSTOR Lognono Beach, MI 200 09/22/1972 SAFSTOR
]
Fort St. Vrain HIG 12/21/1973 DECON i Platteville, CO 842 08/18/1989 DECON in Progress i BWR GE VBWR 08/31/1957 SAFSTOR Pleasanton,CA 50 12/09/1963 SAFSTOR
]
. Hollam
- SCGM 01/02/1962 ENTOMB Hollom, NE 256 09/01/1964 ENTOMB l
l Humboldt Boy 3 BWR 08/28/1962 SAFSTOR Eureka, CA 200 07/02/1976 SAFSTOR Indian Point 1 PWR 03/26/1962 SAFSTOR Buchanan, NY 615 10/31/1974 SAFSTOR La Crosse BWR 07/03/1967 SAFSTOR Genoa,WI 165 04/30/1987 SAFSTOR Pathfinder BWR 03/12/1964 SAFSTOR Sioux Falls, SD 190 09/16/1967 DECON Completed Peach Bottom 1 HTG 01/24/1966 SAFSTOR Peach Bottom, PA 115 10/31/1974 SAFSTOR Piquo
- OCM 08/23/1962 ENTOMB Piquo, OH 46 01/01/1966 ENTOMB
.: u 100 NUCLEAR REGULATORY COMMISSION
Appendix B. U.S. Commercial Nucieor Power Reactors Formerly Ucensed to Operole (Continued)
. .. (.3gLWQggffggy Decommissionpi Unit Con Type OLissued ^' .4.a Seieded location MWt Shut Down Current Slotus Rancho Seco PWR 08/16/1974 SAFSTOR '
l Herald, CA 2772 06/07/1989 SAFSTOR(1)
San Onofre 1 PWR 03/27/1967 SAFSTOR San Clemente, CA 1347 11/30/1992 (2) l Shippingport
- PWR N/A DECON j Shippingport, PA 236 1982 DECON Completed I Shoreham BWR 04/21/1989 DECON Wading River, NY 2436 06/28/1989 DECON Co :pleted i Three MileIsland 2 PWR 02/08/1978 (3)
Londonderry Township, PA 2770 03/28/1979 Trojan PWR 11/21/1975 DECON Portland, OR 3411 11/09/1992 DECON in Progress Yankee-Rowe PWR 12/24/1963 'DECON Franklin County, MA 0600 10/01/1991 DECON in Progress L
l l
l l
- AEC/ DOE owned; not regulated by NRC.
" Holds byproduct license from State of South Carolina.
Notes: See Glossary for definitions of decommissioning alternatives.
(1) Dismantlement of radioactive contaminated secondary system piping and components is ongoing.
(2) The licensee plans to maintain the facility in SAFSTOR until Units 2 and 3 permanently cease operation, at which time all units are planned to be decommissioned.
(3) Three Mile Island 2 has been placed in a monitored storage mode until Unit 1 permanently ceases operation, at which time both units are planned to be decommissioned.
Source: DOE Integrated Data Base for 1990; U.S. Spent Fuel and Radioactive Waste, inventories, Projections, and Characteristics (DOE /RW-0006, Rev. 6), and Nuclear Regulatory Commission 1997 INFORMATION DIGEST 101
ndix C Canceled U.S. Commercial Nuclear Power Reactors !
i Conceled Unit Con Type Date Utility MWe per Unit Status '
Allens Creek 1 BWR 1982 Houston Ughting & Power Company 1150 Under CP Review i Allens Creek 2 BWR 1976 l
{ Houston Ughting & Power Company 1150 Under CP Review Atlanta 1 & 2 I PWR 1978 Public Service Ekm:tric & Gas Company 1150 Under CP Review Bailly BWR 1981 ,
Northern Indiano Public Service Company 645 With CP l
! Barton 1 & 2 BWR 1977 '
Alabama Power & Ught 1159 Under CP Review Barten 3 & 4 BWR 1975 Alabama Power & Ught 1159 Under CP Review Bellefonte 1&2 PWR (1) l Tennessee Valley Authority 1235 With CP Black Fox 1 & 2 BWR 1982 Public Service Company of Oklaborna 1150 Under CP Review i l
Blue Hills 1 & 2 PWR 1978 i Gulf States Utilities Company 918 Under CP Review Calloway 2 PWR 1981 Union EIectric Company 1150 With CP Cherokee 1 PWR 1983 Duke Power Company 1280 With CP Cherokee 2 & 3 PWR 1982 Duke Power Company 1280 With CP Clinch River LMFB 1983 Project Management Corp.; DOE;TVA 350 Under CP Review Clinton 2 BWR 1983 Illinois Power Company 933 With CP Davis-Besse 2 & 3 PWR 1981 ,
Toledo Edison Company 906 Under CP Review Douglas Point 1 & 2 BWR 1977 Potomac Electric Power Company 1146 Under CP Review
..m . . . .. maummmmm, 102 NUCLEAR REGULATORY COMMISSION
't Appendix C. C nceled U.S. Commercial Nuclear Power Reactors (Continued)
^
- l -[.%kJM@%
~
Conceled Unit Con Type Date
- Utility MWe per Unit Status 4
Erie 1 & 2 PWR 1980 Ohio Edison Company 1260 Under CP Review Forked River 1 PWR 1980 Jersey CentroIPower & Light Company 1070 With CP Fort Calhoun 2 PWR 1977 Omaha Public Power District 1136 Under CP Review Fulton I & 2 HIG 1975 Philadelphia Electric Company 1160 Under CP Review GrandGulf 2 BWR 1990 l
- Entergy Operations, Incorporated 1250 With CP l
Greene County PWR 1980 Power Authority of the State of NY 1191 Under CP Review Greenwood 2 & 3 PWR 1980 Detroit Edison Company 1200 Under CP Review 4
Hartsville Al & A2 BWR 1984 Tennessee Valley Authority 1233 With CP Hartsville B1 & B2 BWR 198' Tennessee Valley Authority 1233 With CP
! Haven 2 (formerly Koshkonong 2) PWR 1978 Wisconsin Electric Power Company 900 Under CP Review Hope Creek 2 BWR 1981
, Public Service Electric & Gas Company 1067 With CP Jamesport 1 & 2 PWR 1980 tong Island Ughting Company 1150 With CP Marble Hill 1 & 2 PWR 1985
' With CP Public Service ofIndiano 1130 l Midland 1 PWR 1986 Consumers Power Company 492 With CP l Midland 2 PWR 1986 Consumers Power Company 818 With CP i
Montague 1 & 2 BWR 1980 Northeast Nuclear Energy Company 1150 Under CP Review (Continued) 1997 INFORMATION DIGEST 103
[ .%.,%g Aff*TRQQ[Q Conceled Unit Con Type Date Utility MWe per Unit Stolus New England i & 2 PWR 1979 New England Power Company 1194 Under CP Review New Haven 1 & 2 PWR 1980 New York State Electric & Gas Corporation 1250 Under CP Review North Anna 3 PWR 1982 Virginia Electric & Power Company 907 With CP Nodh Anna 4 PWR 1980 Virginia Electric & Power Company 907 With CP
~
North Coast 1 PWR 1978 Puerto Rico Water Resources Authority 583 Under CP Review Polo Verde 4 & 5 PWR 1979 Arizona Public Service Company 1270 Under CP Review Pebble Springs 1 & 2 PWR 1982 Portland General Electric Company 1260 Under CP Review Perkins 1,2, & 3 PWR 1982 Duke Power Company 1280 Under CP Review Perry 2 BWR 1994 Cleveland Electric illuminating Co. 1205 Under CP Review Phipps Bend 1 & 2 BWR 1982 Tennessee Valley Authority 1220 With CP Pilgrim 2 PWR 1981 Boston Edison Company 1180 Under CP Review Pilgrim 3 PWR 1974 Boston Edison Company 1180 Under CP Review Quanicassee 1 & 2 PWR 1974 Consumers Power Company 1150 Under CPlieview River Bend 2 BWR 1984 Gulf States Utilities Company 934 With CP Seabrook 2 PWR 1988 Public Service Co. of New Hampshire 1198 With CP Shearon Horris 2 PWR 1983 Carolina Power & Ught Company 900 With CP Sheoron Harris 3 & 4 PWR 1981 l Carolino Power & Ught Company 900 With CP l
- , .. ,_,,mmom : ,
104 NUCLEAR REGULATORY COMMISSION
l 1
Appendix C, Canceled U1 Commercial Nuclear Power Reactors (Continued)
. 9dAqEZ55253;i j Conceled Unit Con Type Dale Utilhy MWe per Unit Status
, 1 Skogit/Honford 1 & 2 PWR 1983
. Puget Sound Power & Light Company 1277 Under CP Review Sterling PWR 1980 Rochester Gas & Electric Corporation 1150 With CP Summit 1 & 2 HTG 1975 !
Delmarvo Power & Light Company 1200 Under CP Review
. Sundesert 1 & 2 PWR 1978
- Son Diego Gas & Electric Company 974 Under CP Review Surry 3 & 4 PWR 1977 Virginia Electric & Power Company 882 With CP Tyrone1 FWR 1981 Northern States Power Company 1150 Under CP Review Tyrone 2 PWR 1974 Northern States Power Company 1150 With CP a Vogtle 3 & 4 PWR 1974 l Georgio Power Company 1113 With CP l 1
Washington Nuclear 1 PWR 1995 i Washington Public Power Supply System 1266 With CP l l
Washington Nuclear 3 PWR 1995 Washington Public Power Supply System 1242 With CP
, l Washington Nuclear 4 PWR 1982 Washington Public Power Supply System 1218 With CP Washington Nuclear 5 MR 1982 Washington Public Power Supply System 1242 With CP Watts Bor 2 PNR (1)
Tennessee Volley Authority 1165 With CP Yellow Creek 1 & 2 BWR 1984 Tennessee Volley Authority 1285 With CP Zimmer 1 BWR 1984 CincinnatiGas & Electric Company 810 With CP Note: Concelation is defined as public announcement of cancellation or written notification to NRC.
Only docketed applications are indicated.
(1) Bellefonte 1 and 2 and Watts Bar 2 have not been formally cancelled; however TVA has stopped construction and is presently evaluating options (e.g. cancellation or conversion).
Source: DOE /EIA Commercial Nuclear Power 1991 (DOE /EIA-0438 (91)), Appendix E (page 105) and Nuclear Regulatory Commission
--___m m om w nnu:ggugpyx,prp 1997 INFORMATION DIGEST 105
) Appendix D
. +neggggy U.S. Commercial Nuclear Power Reactors by Licensee Utility Unit Arizona Public Service Company Polo Verde 1,2, & 3 Baltimore Gas & Electric Company Calvert Cliffs 1 & 2 Boston Edison Company Pilgrim 1 Carolina Power & Light Company Brunswick 1 & 2 Carolina Power & Light Company H. B. Robinson 2 Carolina Power & Light Company Shearon Harris 1 Cleveland Electric illuminating Company Perry 1 Commonwealth Edison Company Braidwood 1 & 2 Commonwealth Edison Company Byron 1 & 2 Commonwealth Edison Company Dresden 2 & 3 Commonwealth Edison Company lo Salle County 1 & 2 Commonwealth Edison Company Quod Cities 1 & 2 Commonwealth Edison Company Zion 1 & 2 CT Yankee Atomic Power Company Hoddam Neck Consolidated Edison Company indian Point 2 Consumers Power Company Big Rock Point Consumers Power Company Polisades Detroit Edison Company Fermi 2 Duke Power Company Catawba 1 & 2 Duke Power Company McGuire 1 & 2 Duke Power Company Oconee 1,2, & 3 Duquesne Light Company Beaver Valley 1 & 2 Entergy Operations, Incorporated Arkansas Nuclear 1 & 2 Entergy Operations, Incorporated Grand Gulf 1 Entergy Operations, Incorporated River Bend 1 Entergy Operations, Incorporated Waterford 3 Florida Power & Light Company St. Lucie 1 & 2 Florida Power & Light Company Turkey Point 3 & 4 Florida Power Corporation Crystal River 3 GPU Nuclear Corporation Oyster Creek GPU Nuclear Corporation Three MileIsland 1 Houston Lighting & Power Company South Texas Project 1 & 2 IES Uiilities, incorporated Duane Artold Illinois Power Company Clinton Indiana / Michigan Power Company D. C. Cook 1 & 2 Maine Yankee Atomic Power Company Maine Yankee
..~-~..,_._nn.
106 NUCLEAR REGULATORY COMMISSION
I Appendix D. U,S, Commercial Nuclear Power Reactors by Licensee (Continued) iMMBE&2RE \
Utility Unit Nebraska Public Power District Cooper Niagara Mohawk Power Corporation Nine Mile Point 1 & 2 Seabrook1 North Atlantic Energy Service Corporation l Northeast Nuclear Energy Company Millstone 1,2, & 3 j l
Northern States Power Company Monticello Northern States Power Company Prairieidand 1 & 2 l Omaho Public Power District Fort Calhoun Pacific Gas & Electric Company Diablo Canycn 1 & 2 PECO Energy Company Peach Bottom 2 & 3 Pennslyvania Power & Light Company Susquehanna 1 & 2 Philadelphio Electric Company Limerick 1 & 2 Power Authority of the State of New York Indian Point 3 Power Authority of the State of New York James A. FitzPotrick Public Service Electric & Gas Company Hope Creek 1 Public Service Electric & Gas Company Salem 1 & 2 Rochester Gas & Electric Corporation Ginna South Carolino Electric & Gas Company Summer Southern California Edison Co. &
Son Diego Gas & Electric Company San Onofre 2 & 3 Southern Nuclear Operating Company Joseph M. Forley 1 & 2 Southern Nudear Operating Company Edwin I. Hatch I & 2 Southern Nuclear Operating Company Vogtle 1 & 2 Tennessee Valley Authority Browns Ferry 1,2, & 3 Tennessee Valley Authority Sequoyah 1 & 2 Tennessee Valley Authority Watts Bar 1 Texas Utilities Electric Company Comanche Peak 1 & 2 Toledo Edison Company Davis-Besse Union Electric Company Colloway VIYankee Nuclear Power Corporation Vermont Yankee Virginio Electric & Power Company North Anno 1 & 2 Virginia Electric & Power Company Surry 1 & 2 Washington Public Power Supply System Washington Nuclear 2 Wisconsin Electric Power Company Point Beach 1 & 2 Wisconsin Public Service Company Kewounee Wolf Creek Nuclear Operating Corporation Wolf Creek 1 Source: Nuclear Regulatory Commission
..,.., , _ ,mm, .,
1997 INFORMATION DIGEST 107
] 1 -
Is -I U.S. Nuclear Nonpower Reactors Licensee Reactor T License Type License location OLiss Docket Number Number Aerotest a (indus) OL R-98 San Ramon, CA Trig 07 /02/1965 50-228 Armed Forces Radiobiology a OL R-84 Research Institute Trig 06 /26/1962 50-170 Bethesda, MD Cornell University Zero Power OL R 89 Ithoco, NY 12/11/1962 50-97 Cornell University o Mark 11 OL R 80 Ithaca, NY Trig 01 /11/1962 50-157 Dow Chemical Company a OL R-108 Midland,MI Trig 07 /03/1967 50-264 General Atomics Mark l o Marki OL R-38 San Diego, CA Trig 05 /03/1958 50-89 General Electric Company Nuclear Test OL R 33 Pleasanton, CA 10/31/1957 50-73 Georgia Institute of Water OL R 97 Technology Heavy 12/29 /1964 50 160 Atlanta, GA idaho Stcte University AGN-201 #103 OL R 110 Pocatello, C 10/11/1967 50-284 lowa State University onaut OL R-59 Ames, IA Arg/16/1959 10 50-116 Kansas State University a OL R-88 Manhattan, KS Trig 10 /16/1962 50-188 Manhattan College Tank OL R-94 Bronx, NY 03/24/1964 50-199 Massachusetts Institute of HWR Reflected OL R-37 Technology 06/09/1958 50-20 Cambridge, MA NationalInstitute of Nuclear Test OL TR-5 Standards & Technology 06/30/1970 50-184 Gaithersburg, MD
. . , , . . - , . . m_,_,un n_ ~ ,
108 NUCLEAR REGULATORY COMMISSION
Appendix E. U.S. Nuclear Nonpower Reactors (Continued)
?MM$5 MEW d
gjcensee Reactor T License Type Lkense Loconon OLiss Docket Number Numtwr 4
North Carolina State Pulstar OL R 120 University 08/25/1972 50-297 Raleigh, NC 1
Ohio State University Pool OL R-75 l
Columbus, OH 02/24/1961 50-150 Oregon State University Trigo Mark 11 OL R-106 Corvallis, OR 03/07/1967 50-243 o OL R-2 Pennsylvania State University University Park, PA Trig 07 /08/1955 50 5 Purdue University Lockheed OL R-87 West Lafayette,IN 08/16/1962 50 182 Reed College o MarkI OL R il2 Portland,OR Trig 07 /02/1968 50-288 Rensselaer Polytechnic Critical Assembly OL CX 22 Institute 07/03/1964 50-225 Troy, NY RhodeIsland Atomic Energy GE Pool OL R-95 Commission 07/21/1964 50-193 Narragansett, RI State University of New York Pulstar OL R-77 03/24/1961 50-57 (Buffalo)
Buffalo, NY Texas A&M University AGN 20lM #106 OL R 23 College Station,TX 08/26/1957 50 59 Texas A&M University a OL R-128 College Station,TX Trig 12 /07/1961 50-128 U.S. Geological Survey o Marki OL R-ll3 Denver, CO Trig 02 /24/1969 50 274 o Marki OL R-52 University of Arizona Tucson, AZ Trig 12 /05/1958 50-113 o MarkI OL R-116 University of California /
trvine Trig 11 /24/1969 50-326 fryine, CA onaut OL R 56 University of Florida Gainesville, FL Arg/21/1959 05 50-83 (Continued
- -numeawaa m sm waww a m ..
109 1997 INFORMATION DIGEST
- yyiXMTTQQ7ljff
^
Licensee Reactor Type License Type License location OLissued' Docket Ndmber Number Universit Triga OL R 115 Urbana,y il ofIllinois 07/22/1969 50-151 University of Lowell GE Pool OL R-125 Lowell, MA 12/24/1974 50 223 University of Maryland a OL R-70 College Park, MD Trig 10 /14/1960 50-166 University of Michigan Pool OL R 28 Ann Arbor, M1 09/13/1957 50-2 I
University of Missouri /Rollo Pool OL R 79 Rolla, MO 11/21/1961 50-123 University of Missouri / Tank OL R 103 Columbia 10/11/1966 50-186 Columbia, MO University of New Mexico AGN 201M #112 OL R 102
, Albuquerque, NM 09/17/1966 50-252 Univeesity of Texas a Mark ll OL R 92 Austin, TX Trig 01 /17/1992 50-602 University of Utah /Trigo Trigo Mark i OL R-126
- Salt Lake City, UT 09/30/1975 50-407 University of Virginia Pool OL R-66 Charlottesville,VA 06/27/1960 50-62 University of Wisconsin a OL R 74 Madison, WI Trig 11 /23/1960 50-156 Veterans Administration a OL R-57 Omaha, NE Trig 06 /26/1959 50 131 Washing ton State University Triga OL R-76 Pullman, WA 03/06/1961 50-27 Worcester PolytechnicInstitute GE OL R-61 Worcester, MA 12/16/1959 50-134 i Note
- Limited to nonpower reactors licensed to operate.
Source: Nuclear Regulatory Commission s- . .. . o . m .,, _ m . m m , _ < ,
110 NUCLEAR REGULATORY COMMISSION
w m ma NRC Performance Indicators: Annual Industry Averages
- 1988 1989 1990 1985 1986 1987 Indicolor 2.26 1.85 1.63 5.28 4.50 3.60 Automatic Scrams 1.23 1.31 1.00 2.09 1.51 2.74 Safety System Actuations 0.88 0.77 0.46 2.38 1.66 0.85 Significant Events 2.35/ 2.41/ 2.03/
2.30 2.27 1.65/
Safety System Failures 0.98" 1.07" 1.68" 1.66" 7.95 9.92 7.20 11.00 11.00 95.4 Forced Outage Rate 0.45 0.45 0.39 0.90 1.11 0.59 Equipment Forced Outage Rote 388.00 332.00 336.00 577.00 501.00 410.00 CollectiveRadiation Exposure 1994 1995 1996 1991 1992 1993 Indicator 1.04 0.95 0.80 1.52 1.43 1.13 Automatic Scrams 0.52 0.47 0.39 1.00 0.78 0.79 Safety System Actuations 0.21 0.12 0.07 0.28 0.30 0.26 Significant Events 1.13/ 0.95/ 1.40/
1.76/ 1.98/ 1.63/
Safety System Failures 0.92" 1.05" 1.50 "
1.64" 1.56" 1.67 "
9.17 5.88 7.50 8.95 7.55 8.58 Forced Outage Rate 0.24 0.26 0.24 0.36 0.30 0.24 Equipment Forced Outage Rate 203.00 199.00 178.00 255.00 267.00 243.00 Collective Radiation Exposure
' Calendar year values are being shown for 1985 through 1995. Fiscal year v beginning in 1996. Data for October 1,1995 through December 31,199 calendar year 1995 and fiscal year 1996 values.
" These numbers represent additional data that resulted from reclassification of safet system failures.
Source: Licensee data os compiled by the Nuclear Regulatory Commission.
111 1997 INFORMATION DIGEST
pdixG NRC-Approved Dry Spent Fuel Storage Designs !
Stomge Certdicate of l Design Compliance Design Copacity Apprmml Appreml l Vendor (AsseA) Date Dole I GeneralNuclear MetalCask 21 PWR 09/30/1985 08/17/1990 3 Systems, incorporated CASTORV/21 Vectra Technologies, Concrete Module 7PWR 03/28/1986 Incorporated NUHOMS-7 Westinghouse MetalCask 24 PWR 09/30/1987 08/17/1990 Electric MC-10 FosterWheeler Energy Concrete Vault 83 PWR or 03/22/1988 Applications, ModularVault 150 BWR
. Incorporated Dry Store NACInternational MetalCask 26 PWR 03/29/1988 08/17/1990 '
NAC S/T
. NACIntemational MetalCask 28 Canisters 09/29/1988
' 08/17/1990 NAC-C28 S/T (fuelrods l from 56 PWR assemblies)
Vectro Technologies, Concrete Module 24 PWR 04/21/1989 Incorporated NUHOMS-24P Transnuclear, MetalCask 24 PWR 07/05/1989 11/04/1993 Incorporated TN 24 NACIntemational MetalCask 28 PWR 02/01/1990 NAC-128/ST Pacific Sierra VentilatedCask 24 PWR 03/29/1991 05/07/1993 Nuclear Assoc:ates VSC-24 Vectra Technologies, Concreb Module 24 PWR N/A 01/23/1995 Incorporated Standardized 52 BWR NUHOMS-24P NUHOMS-52B NACIntemational NAC-STC 26 PWR 07/18/95 Note: PWR - Pressurized-Water Reactor; BWR - Boiling Water Reactor Source: Nuclear Regulatory Commission 112 NUCLEAR REGULATORY COMMISSION
Appendix H .
l ll . . ..
NRC Dry Spent Fuel Storage Licensees Reactor Name Date Storage
. Utility issued Vendor Model j Surry 1,2 General Nuclear MetalCask I Virginia Electric & 07/02/1986 Systems, CASTORV/21 Power Company Incorporated H. B. Robinson 2 Vectro Technologies, Concrete Module Carolino Power & 08/13/1986 incorporated NUHOMS-7 4 i
l Ught Company 1
Oconee 1,2,3 Vectro Technologies, Concrete Module i Duke Power Company 01/29/1990 Incorporated NUHOMS-24P 1
Fort St.Vrain FosterWheeler ModularVault Public Service 11/04/1991 Energy Applications, Dry Store Company of Colorado incorproted Calvert Cliffs 1,2 Vectro Technologies, Concrete Module Baltimore Gas & 11/25/1992 incorporated NUHOMS-24P Electric Company 1
Polisades UnderGeneral Pacific Sierra Ventilated Cask Consumer Power Ucense Nuclear VSC-24 Company Associates PrairieIsland 1,2 10/19/1993 Transnuclear, MetalCask
- TN-40 Northern States Incorporated Power Company Point Beach Under General Pacific Sierra Ventilated Concrete Wisconsin Electric Ucense Nuclear VSC-24 and Power Company Associates Davis-Besse UnderGeneral VECTRATechologies Concrete Module Toledo Edison Ucense incorporated NUHOMS-24P Company
- Application Received Source: Nuclear Regulatory Commission 113 1997 INFORMATION DIGEST
1 wmsywsn World List of Nuclear Power Reactors Under Construction in Operation or on Order Total Number Number Number Country of Units Net MWe of Units Net MWe of Units Net MWe Argentina 2 935 1 692 3 1,627 l
Armenia 1 400 0 0 1 400 l Belgium 7 5,527 0 0 7 5,527 Brazil 1 626 2 2,458 3 3,084 Bulgaria 6 3,420 0 0 6 3,420 Canada 22 15,439 0 0 22 15,439 China 3 2,100 6 4,57C 9 6,670 i Cuba 0 0 2 834 2 834 Czech Republic 4 1,632 2 1,780 6 3,412 Finland 4 2,310 0 0 4 2,310 France 55 57,373 5 6,410 60 63,783 i Germany 20 22,237 0 0 20 22,237 Hungary 4 1,729 0 0 4 1,729 India 10 1,695 6 1,748 16 3,443 Japan 51 40,970 6. 6,027 57 46,997 Kazakstan 1 135 0 0 1 135 Korea 11 9,120 9 7,650 20 16,770 Lithuania 2 2,760 0 0 2 2,760 Mexico 2 1,308 0 0 2 1,308 Netherlands 2 507 0 0 2 507 Pakistan 1 125 1 300 2 425 Romania 1 706 4 2,480 5 3,186 Russia 26 19,849 4 3,375 30 23,224 Slovakia 4 1,632 4 1,664 8 3,296 Slov3nia 1 620 0 0 1 620 South Africa 2 1,840 0 0 2 1,840 Spain 9 7,188 0 0 9 7,188 Sweden 12 10,075 0 0 12 10,075 Switzerland 5 3,072 0 0 5 3,072 Taiwan, China 6 4,884 2 2,700 8 7,584 Ukraine 14 12,095 6 5,700 20 17,795 United Kingdom 35 12,728 0 0 35 12,728 United States 110 99,455 0 0 110 99.455 Total 434 344,492 60 48,388 494 392,880 Note: Operable, under construction, or on order (30 MWe and over) as of 12/31/96.
Source: Excerpted from Nuclear News o March 1997. Reproduced by permission. Further reproduc-tion prohibited. U.S. data compiled by the Nuclear Regulatory Commission from licensee data.
. . . ~ ,_na,,m ng ,.-
114 NUCLEAR REGULATORY COMMISSION
1 A ndix J Nuclear Power Units by Reactor Type, Worldwide In Operation Total Number Number Reactor Type of Units Net MWe of Units Net MWe l
Pressurized light-water reactors 250 220,077 283 249,915 95 77,626 101 84,601 Boilinglight-water reactors 4
Gas cooled reactors, all varieties 35 11,699 35 11,699 I Heavy-water reactors, all varieties 36 19,377 52 27,647
" 15 14,785 16 15,710 Graphite-moderated light-water reactors i 7 3,308
- Liquid metal fast-breeder reactors 3 928 r
Total 434 344,492 494 392,880 (
i i !
i 4
l i
1 i
Note: Operable, under construction, or on order (30 MWe and over) as of 12/31/96.
Source: Excerated from Nuclear News o March 1997 . Reproduced by i
tion prohibited . U.S. dato compiled by the Nuclear ion from licensee Regulatory data. Commi 115 1997 INFORMATION DIGEST
mvmAwuze Top 50 Reactors by Capacity Factor, Worldwide 1996 Gross 1996 Capacity Gross Reactor Factor Generation Country Unit Type Vendor (Percent)
(MWh)
Japan Fukushima 11-2 BWR Hitachi 100.00 9,662,253 Japan Ohi-3 PWR MHI 99.99 10,363,680 U.S. Surry-1 PWR West. 99.40 7,395,635 South Korea Kori-3 PWR West. 99.10 8,269,639 Spain Asco-1 PWR West. 99.04 8,238,860 U.S. Hatch-2 BWR GE 98.75 7,321,204
, U.S. Palo Verde-3 PWR CE 98.61 11,320,800 U.S. Three MileIsland-1 PWR B&W 98.17 7,511,072 U.S. Farley-1 PWR West. 98.12 7,524,424 Japan Ohi-2 PWR West. 98.07 10,121,935 Japan Sendai-2 PWR MHI 98.05 7,665,260 U.S. Seabrook PWR West. 97.68 10,244,636 U.S. Calvert Cliffs 2 PWR CE 97.65 7,547,886 Japan Takahama-2 PWR MHI 97.39 7,066,047 South Korea Ulchin-2 PWR From. 96.65 8,065,354 L U.S. Prarie Island 2 PWR West. 96.24 4,733,980 l^ Canada Darlington-3 PHWR AECL 96.16 7,897,856 South Korea Yonggwang 2 PWR West. 95.67 7,983,882 Finland Olkiluoto-1 BWR ABB 95.46 6,163,389 U.S. Peach Bonom-3 BWR GE 95.27 9,699,000 Japan Kashiwazaki-2 BWR Toshiba 95.25 9,203,910 U.S. St. Lucie-2 PWR CE 95.23 7,377,830 i
U.S. Susc vehanna-2 BWR GE 95.13 9,459,366 Finland Olki voto-2 BWR ABB 95.07 6,137,716
- Germany Neckar-2 PWR Siemens 94.69 11,353,400 Argentina Embalse PHWR AECL 94.58 5,383,704 U.S. South Texas-2 PWR West. 94.55 10,920,900 U.S. Turkey Point 3 PWR West. 94.31 6,031,012
, U.S. San Onofre-3 PWR CE 94.16 9,321,741 Canada Gentilly-2 PHWR AECL 94.13 5,581,186 Taiwan Moons'nan-1 PWR West. 94.12 7,869,004 U.S. Browns Ferry-3 BWR GE 93.58 9,025,810 Switzerland Goesgen PWR KWU 93.58 8,384,538 U.S. Cooper BWR GE 93.24 6,560,518 Finland Loviisa 2 PWR AEE 93.20 3,806,724 Germany Obrigheim PWR KWU 93.10 2,919,590 Germany Emsland PWR Siemens 93.02 11,136,652 U.S. Sequoyah-1 PWR West. 92.64 9,626,795 U.S. South Texas-1 PWR West. 92.46 10,680,540
=am:.-- =mamme a w 116 NUCLEAR REGULATORY COMMISSION
- Appendix K. Top 50 Reactors by Capacity Factor, Worldwide (Continued)
. ; %AMSES 1
1996 Gross 1996 Capooty Gross Reador Fodor Generchon Country Unit Type Vendor (Percent) (MWh)
U.S. Diablo Canyon-1 PWR West. 92.46 9,226,200 f Conodo Bruce-8 PHWR AECL 92.14 7,405,610 4
U.S. Waterford 3 PWR CE 92.10 9,3'z7,910 U.S. Cotowbo-2 PWR West. 92.06 9,744,266 Belgium Doel-1 PWR ACEC. 91.91 3,326,100 i Spain Almoraz-2 PWR West. 91.84 7,502,180 I U.S. Indian Point 2 PWR West. 91.79 8,127,281 1 Germany Philippsburg-2 PWR Siemens 91.72 11,472,475 Spain Cofrentes BWR GE 91.66 7,970,685 U.S. Pilgrim BWR GE 91.54 5,530,209 Hungary Paks-1 PWR AEE 91.38 3,692,256 l
l l
l l
1 i
l l
I l
I l
i l
Source: Excerpted from Nucleonics Week @ 1997 by McGraw Hill, Inc. Reproduced by permission. Further reproduction prohibited. l
.an- n a n ue,n.u .
117 1997 INFORMATION DIGEST
Appendix L Top 50 Reactors by Generation, Worldwide 1996 1996 Gross Gross Capacity Reactor Generation Fodor Country Unit Type Vendor (MWh) (Percent)
Germany Philippsburg-2 PWR Siemens 11,472,475 91.72 Germany Neckar-2 PWR Siemens 11,353,400 94.69 U.S. Polo Verde-3 PWR CE 11,320,800 98.61 Germany Emsland PWR Siemens 11,136,652 93.02 Germany Grohnde PWR Siemens 11,134,588 88.64 Germany Brokdorf PWR Siemens 11,124,556 90.79 U.S. South Texas-2 PWR West. 10,920,900 94.55 Germany Isar-2 PWR Siemens 10,879,849 87.23 U.S. South Texas 1 PWR West. 10,680,540 92.46 Germany Unterweser PWR Siemens 10,432,002 87.97 Japan Ohi-3 PWR MHI 10,363,680 99.99 U.S. Seabrook PWR West. 10,244,636 97.68 France Penly 2 PWR From. 10,175,597 83.82 Japan Ohi-2 PWR West. 10,121,935 98.07 Germany Grafenrheinfeld PWR Siemens 10,058,372 85.14 France Cattenom-1 PWR From. 10,013,668 84.76 Germany Gundremmingen-C BWR Siemens 9,988,213 84.61 France Penly-1 PWR From. 9,917.797 81.70 Germany Gundremmingen-B BWR Siemens 9,864,867 83.56 U.S. Polo Verde-2 PWR CE 9,853,400 85.83 France Flamanville-2 PWR Fram. 9,798,691 82.94 U.S. Catawbo-2 PWR West. 9,744,266 92.06 U.S. Peach Bottom-3 BWR GE 9,699,000 95.27 Japan Fukushimo 11-2 BWR Hitachi 9,662,253 100.00 U.S. Sequoyah-1 PWR West. 9,626,795 92.64 U.S. Grand Gulf-1 BWR GE 9,602,740 83.71 France Cattenom-2 PWR From. 9,539,041 81.71 U.S. Vogtle-2 PWR West. 9,465,396 88.11 U.S. Susquehanna-2 BWR GE 9,459,366 95.13 France Golfech-2 PWR From. 9,431,304 78.77 France Cottenom-4 PWR From. 9,364,868 78.28 U.S. Colloway PWR West. 9,338,062 89.18 U.S. Waterford-3 PWR CE 9,327,910 92.10 U.S. San Onofre-3 PWR CE 9,321,741 94.16 U.S. Limerick-2 BWR GE 9,312,400 91.16
_ - _.n a-2..-wa=.a.m;a= =
118 NUCl. EAR REGULATORY COMMISSION
1 Appendix L Top 50 Readors by Generation, Worldwide (Continued) i i /.jpFfqfgg 4
1996 1996 Gross Gross Copacity !
Reactor Generation Factor !
Country Unit Type Vendor hlWh) (Percent) l 1
9,273,650 77.46 l France Golfech-1 PWR From.
U.S. Polo Verde-1 PWR CE 9,243,200 80.51 U.S. Dici' Canyon-1 PWR West. 9,226,200 92.46 Koshiwozaki-2 BWR Toshibo 9,203,910 95.25
i Sweden Forsmark-3 BWR ABB 9,139,667 86.7)
U.S. Browns Ferry-3 BWR GE 9,025,810 93.58 France Flamanville-1 PWR From. 8,992,200 76.11 U.S. Son Onofre-2 PWR CE 8,980,893 90.72 I McGuire-1 PWR West. 8,914,839 82.85 l U.S.
Sizewell B-1 PWR West. 8,885,406 81.37 4 Britain Sweden Oskarshamn-3 BWR ABB 8,880,508 83.90 France Nogent-2 PWR From. 8,874,623 75.96 8,797,302 74.46 :
France Poluel 2 PWR From.
France St. Albon 2 PWR From. 8,717,252 73.62 i
l l
i 4
i Source: Excerpted from Necleonics Week @ 1997 by McGraw Hill, Inc. Reproduced i by permission. Further reproduction prohibited.
- -- a w u : n.u.
1997 INFORMATION DIGEST I19
. .. - ._- - . __=_ . -- -.
A ndix M Quick Reference Metric Conversion Tables J
SPACE ANDTIME From Inch- To Metric Multiply Quantity Pound Units Units By length mi(statute) km 1.609 347 yd m *0.914 4
~ h(int) m *0.304 8 in cm *2.54 Area mi2 km2
' 2.589 998 ocre m2 4 046.873 yd2 m2 0.836 127 4 h2 m2 0,092 903 04 in2 cm 2 6.451 6 Volume acre foot m 3 1 233.489 yd3 m3 0.764 554 9 ft3 m3 0.028 316 85 ft3 L 28.316 85 gallon L 3.785 412 floz mL 29.573 53 in3 cm3 16.387 06 Velocity mi/h km/h 1.609 347 ft/s m/s '0.304 8 Acceleration ft/s2 m/s2 *0.304 8 NUCLEAR REACTION and 10NIZING RADIATION From inch- To Metric Multiply Quantity Pound Units Units By Activity (of a curie (Ci) '37,000.0 MBcl radionuclide) dpm Bq (scquerel) 0.016 667 Absorbed rod Gy(gray) *0.01 dose rod cGy *1.0 Dose rem *0.01 Sv(sievert) equivalent rem mSv '10.0 mrem mSv *0.01 mrem pSv *10.0 Exposure (X and roentgen (R) C/kg (coulomb) 0.000 258 comma rays)
- Exociconversion factors
. . . , . ~
_ _ . a_amra.riman 120 NUCLEAR REGULATORY COMMISSION
Appendix M. Quick Reference Metric Conversion Tchles (Continued)
.qgeggigggga HEAT From inch- To Metric Multiply
- Quantity Pound Units Units By Thermodynamic *F *K "K = (*F + 459.67)/1.8 temperature Celsius *F C "C = ( F-32)/1.8 temperature Linear expansion *F-1 *K-1 or *C-1 *1.8 coefficient 2
Thermal (Btu
- in)/(ft
- h * *F) W/(m * *C) 0.144 227 9 conductivity 2 2 Coefficient of Btu / (ft . h . *F) W/(m . *C) 5.678 263 heat transfer Heat capacity Blu/*F U/*C 1.899 108 Specific heat Btu /(lb a *F) U/(kg **C) *4.186 8 capacity Entropy Blu/*F U/*C 1.899 108 Specific entropy Btu /(Ib * *F) U/(kg
- C) *4.186 8 Specificinternal Blu/lb U/kg *2.326 energy MECHANICS 4
From Inch- To Metric Multiply Quantity Pound Units Units By I *0.907 184 74 Mass ton (short) t (metric ton) i (weight) lb(ovdp) kg *0.453 592 37 Moment of man Ib a ft kg*m 0.138 255 Density ton (short)/yd3 t/m3 1.186 553 lb/ft3 kg/m3 16.018 46 Concentration Ib/ gal g/L 119.826 4 (mass)
Momentum Ib a ft/s kg em/s 0.138 255 2
l Angular Ib + ft2 /s kgem/s 0.042 140 11 4
momentum Moment of Ib + ft2 kg*m2 0.042 140 11 Inertia Force kip (kifopound) kN(kilonewton) 4.448 222 lbf N (newton) 4.448 222 5 "N""
- Exact conversion factors
< :... . ., u.aan, ann 1997 INFORMATION DIGEST 121
Twyfgyfgj MECHANICS (Continued)
From inch- To Metric Multiply Quantity Pound Units Units By Moment of Force, Ibf a ft N*m 1.355 818 torque Ibfain N*m 0.122 984 8 Pressure atm (std) kPa (kilopascal) *101.325 bar kPa '100.0 lbf/in 2(formerlypsi) kPa 6.894 757 inHg (32 F) kPa 3.386 38 ftH O (391*F) kPa 2.988 98 in O (60*F) kPa 0.248 84 mm g (0 C) kPa 0.133 322 Stress kip /in2(formerlyksi) MPa 6.894 757 lbf/in 2(formerly psi) MPa 0.006 894 757 4
lbf/in 2(formerlypsi) kPa 6.894 757 lbf/ft2 kPa 0.047 880 26 Energy, kwh MJ '3.6 i
work col g )(joule) *4.184
- Btu kJ 1.055 056 1
~
ft
- Ibf J 1.355 818 ,
therm (US) MJ 105.480 4 i Power kW Btu /s 1.055 056 hp (electric) kW '0.746 Btu /h W 0.293 071 1 To convert from metric units to inch pound units, divide the metric unit by the conversion factor.
' Exact conversion factors Note: The information contained in this table is intended to familiarize NRC personnel with commonly used SI units and provide a c uick reference to aid in the understanding of documents containing SI units. l The conversion factors provic ed have not been approved as NRC guidelines for development of licensing actions, regulations or policy.
Source: Federal Standard 376A (May 5,1983), Preferred Metric Units for General Use by the Federal Government; and International Commission of Radiation Units and Measurements, ICRU Repod 33 !
(1980), Radiation Quantities and Unit
. , . . m_u,wc.-
122 NUCLEAR REGULATORY COMMISSION l
i
'_' . W M &'T g M ]
Glossary AGREEMENT STATE: A State that has signed an agreement with the NRC allowing the State to regulate the use of radioactive material within that State.
BOILING-WATER REACTOR (BWR): A nudear reactor in which water, used as both coolant and moderator, is allowed to boil in the core.
CAPABILITY: The maximum load that a generating station can carry under specified conditions for a given period of time without exceeding approved limits of temperature and stress. Net summer capability is used in the digest. Measured in watts except as noted otherwise.
CAPACITY FACTOR (Gross): The ratio of the gross electricity generated, for the period of time considered, to the energy that could have been generated at continuous full power operation during the same perioc.
CAPACITY FACTOR (Net): The ratio of the net electricity generated, for the period of time considered, to the energy that could have been generated at continuous full power operation during the some perioc.
CASK: A heavily shielded container used to store and/or ship radioactive materials. Lead and steel are common materials used in the manufacture of casks.
COMPACT: A group of two or more States formed to dispose of low-level radioactive waste on a regional basis. Forty-two States have formed nine compacts.
CONSTRUCTION RECAPTURE: The maximum number of years that could be added to the license expiration date to recover the period from the construction permit to the date when the operating license was granted. A licensee is required to submit on application for such a change.
CONTAMINATION: The deposition of unwanted radioactive material on the surfaces of structures, creas, objects, or personnel.
DECOMMISSION: The process of safely removing a facility from service followed by reducing residual radioactivity to a level that permits the release of he property for unrestricted use.
DECON: A method of decommissioning in which the equipment, structures, and portions of a facility and site containing radioactive contaminants are removed or decontaminated to a level that permits the property to be released for unrestricted use shortly after cessation of operations.
(Continued) 1997 INFORMATION DIGEST 123
d& MEDQ}$lijE DECONTAMINATION: The reduction or removal of contaminated radioactive material from a structure, crea, object, or person.
ENTOMB: A method of decommissioning in which radioactive contaminants are encased in a structurally long-lived material, such as concrete. The entombment structure is appropriately maintained, and continued surveillance is carried out until the radioactivity decays to a level 4 permitting unrestricted release of the property.
1 FISCAL YEAR: The 12 month period, from October 1 through September 30, used by the Federal Government in budget formulation and execution. The fiscal year is designated by the calendar year in which it ends.
FUEL CYCLE: The series of steps involved in supplying fuel for nuclear power reactors.
FULL-TIME EQUIVALENT: A measurement equal to one' staff person working a full-time work schedule for 1 year.
GENERATION (Gross): The total amount of elec:ric energy produced by a generating station as measured at the generator terminals. Measu ed in watthours except as noted otherwise.
GENERATION (Net): The gross amount of electric energy produced less the electric energy consumed at a generating station for station use. Measured in watthours except as noted otherwise.
GIGAWATT: One billion watts.
GIGAWATTHOUR: One billion watthours.
HIGH-LEVEL WASTE: High-level radioactive waste (HLW) means (1) irradiated (spent) reactor fuel; (2) liquid waste resulting from the operation of the first cycle solvent extraction system, and the concentrated wastes from subsequent extraction cycles, in a facility for reprocessing irradiated reactor fuel; and (3) solids into which such liquid wastes have been converted.
HLW is primarily in the form of spent fuel discharged from commercial nudear power reactors it also includes some reprocessed HLW from defense activities, and a small quantity of reprocessed commercial HLW.
LOW LEVEL WASTE: Low-level radioactive waste (LLW) is a general term for a wide range of wastes. Industries; hospitals and medical, educational, or research institutions; private or povernment laboratories; and nudear fuel cyde facilities (e.g., nudear power reactors and fuel fabrication plants) using radioactive materials generate low-level wastes as part of their normal operations. These wastes are generated in many physical and chemical forms and levels of contamination.
~- _,_m 124 NUCLEAR REGULATORY COMMISSION
, Glossary (Continued)
' . ; . 9%pqqqggggg MAXIMUM DEPENDABLE CAPACITY (Gross): Dependable main-unit gross capacity, winter or i
summer, whichever is smaller. The dependable capacity varies Muse the unit efficiency varies during the year due to temperature variations in cooling water. It is the gross electrical output as measured at the output terminals of the turbine generator during the most restrictive seasonal conditions (usually summer). Measured in watts except as noted otherwise.
j MAXIMUM DEPENDABLE CAPACITY (Net): Gross maximum dependable capacity less the normal station service loads. Measured in watts except as noted otherwise.
. MEGAWATT (MW): One million watts.
i MEGAWATTHOUR (MWh): One million watthours.
[ METRIC TON: Approximately 2,200 pounds.
NET SUMMER CAPABluTY: The steady hourly output that generating equipment is expected to supply to system load exclusive of auxiliary power, as demonstrated by tests at the time of summer peak demand. Measured in watts except as noted otherwise.
NONPOWER REACTOR: Reactors used for research, training, and test purposes, and for the production of radioisotopes for medical and industrial uses.
POSSESSION ONLY UCENSE: A form of license that allows possession but not operation.
PRESSURIZED WATER REACTOR (PWR): A nudear reactor in which heat is transferred from the core to a heat exchanger via water kept under high pressure without boiling the water.
PRODUCTION EXPENSE: Production expenses are a component of generation expenses that includes costs associated with operation, mainterience, and fuel.
RADIOACTIVITY: The rate at which radioactive material emits radiation. Measured in units of becquerels or disintegrations per second.
SAFSTOR: A method of decommissioning in which the nuclear facility is placed and main-toined in such condition that the nuclear facility con be safely stored and subsequently decontaminated (deferred decontamination) to levels that permit release for unrestricted use.
SPENT NUCLEAR FUEL: Fuel that has been removed from a nudear reactor because it can no longer sustain power production for economic or other reasons.
(Continued)
- _-.-.w.n 1997 INFORMATION DIGEST 125
. IrJ 4%;@ h T3 2fBBP M ?
URANIUM FUEL FABRICATION FACIUTY: A facility that (1) manufactures reactor fuel l containing uranium for any of the following (i) preparation of fuel materials;(ii) formation of iv) recovery of fuel materials scrap material; into desired and (v) storage associated with shapes; (iii)orapplication such operations; (2) con of protective cladd development activities.
URANIUM HEXAFLUORIDE PRODUCTION FACluTY: A facility that receives natural uranium in the form of ore concentrate; enriches it, either by iffusion or gas centrifuge methods; and converts it into uranium hexafluoride. gaseous c VIABILITY ASSESSMENT: A DOE decisionmaking process to judge the prospects for geologic i disposal of high-level radioactive wastes at Yucca Mountain based on (1) specific design work I on the critical elements of the repository and waste package, (2) a total system performance l i
ossessment that will describe the probable behavior of the repository, (3) a plan and cost estimate for the work required to complete a license application, and (4) an estimate of the costs to construct and operate the repository.
WATT: The electrical unit of power. The rate of energy transfer equivalent to 1 ompere flowing under a pressure of I volt at unity power factor.
WATTHOUR: An electrical energy unit of measure equal to 1 watt of power supplied to, or i taken from, an electrical circuit steadily for I hour.
WHEELING SERVICE: The movement of electricity from one system to another over transmis-sion facilities of intervening systems. Whealing service contracts can be established between two or more systems.
_ _ __- an-mn~w-126 NUCLEAR REGULATORY COMMISSION
l
^.'.
.. N.,.'
- ..D tQ a.;c a c m
- i. l&ky u4 '. ' {w{ffa,s,.m&??&[nfa l
- 1. REPORT gOaM saa u.e NUCLEAR REGULATORY COMheSSON g NReu nea, OfR .. ana Aasene n on, ,
3201. 3m BIBLIOGRAPHIC DATA SHEET *** N aar 3 asse mewwuono en v. r sei NUREG-1350
- a. ruta ANo samta
- 3. DATE REPURT PUGU640 Nuclear Regulatory Commission m y )
Information Digest gg,y 1997 l 1997 Edition l 4 FN OR ORANT NUheER ,
I
.. -cam .. rm O, RE, T hl. Garver, et al. Mnual
- 7. PEROD COVERED tenclueeve Desee) e et=
=mne Omen.u ORoAreJ.ATON ame ee:
- NAME a eenw cice, previse Are ADDALSS name ans memnstR MC.
ame Pe. m Dnstesan. Omoe w Repon, u.S. Demeer Regwawy Cerwrunhan, sw es.n Division of Budget and Analysis OfDee of the Chief Financial Omcer U.S. N uclear Regulatory Comminaion
%shington, DC 20555-0001 Ah AM ADDRE
- 8. SPONSORIN,G u s. ewe Re QRGANIZ,ATaON uin carnrNu
- N.co,4.na m)emne nees. e SS (W MC, tyee 'Same se above*; H emmector, prevene id4G Osweeson, effese er Reglen, Same as 8, above.
)
- 60. Nf MtNT AHY NOTES
- 10. A88TMCT (200 wores er hess)
He Nuclear Regulatory Commission Information Digest (digest) provides a summary of information about the U.S.
Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, NRC licensed activities, and general information on domestic and worldwide nuclear energy. elie digest, published annually, is a compilation of nuclear-and NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1996, with exceptions noted. Information on generating capac-ity and average capacity factor for operating U.S. commercial nuclear power reactors is obtained from monthly oper-atmg reports that are submitted directly to the NRC by the licensee. This information is reviewed by the NRC for consistency only and no independent vandation and/or verification is performed.
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UNITED STATES FiRST CLASS Mall NUCLEAR REGULATORY COMMISSION POSTAGE AND FEES PAID WASHINGTON, DC 20555-0001 USNRC
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OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 9
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