ML20216H814
| ML20216H814 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 06/19/1987 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20216H801 | List: |
| References | |
| NUDOCS 8707010589 | |
| Download: ML20216H814 (93) | |
Text
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l Westinghouse Electric Corporation-Nuclear Service Integration Division Pittsburgh, Pennsylvania (15230) ,
Application for Modification of Facility License R-119, Docket 50-87 to a " Possession Only" Facility License Section I General Information l
This application is to amend the Westinghouse Nuclear Training Reactor (NTR) Facility license to a " Possession Only" license.
In accordance with the requirements and format of.10 CFR 50.33, the following information is submitted:
(a) Name of Applicanti ,
Westinghouse Electric Corporation .
.(b) Address of Applicant: ;
Principal Business Address:
3 Gateway Center Pittsburgh, Pennsylvania (15230).
O I-l Ol81N
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' B707010589 870619 .
PDR- ADOCK 05000087 .l P PDR
c3 Mailing Address for all Correspondence Pertaining to License:
Westinghouse Electric Corporation l
Nuclear Energy Systems
{
P.O. Box 355 Pittsburgh, Pennsylvania (15230)
Attn: A. Joseph Nardi, Manager NES License Administration Physical Location of Licensed Facility:
Westinghouse Nuclear Training Center 505 Shiloh Blvd.
f Zion, Illinois (60099) t'] (c) Description of Business or Occupation of Applicant:
%./
See Westinghouse Electric Corporation Letter
" Corporate Information for Licenses" Dated December 2,1979, A.J. Nardi to Mr. John G.
Davis and Mr. Harold R. Denton (d)(3)(i) State of Incorporation:
See Westinghouse Electric Corporation Letter
" Corporate Information for Licenses" l
Dated December 2, 1979, A.J. Nardi to Mr. John G. l l
Davis and Mr. Harold R. Denton !
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) (3)(ii) Corporate Officials- l See Westinghouse Electric Corporation Letter j
" Corporate Information for Licenses" 1
Dated December 2,1979, A.J. Nardi to Mr. John G.
l l
Davis and Mr. Harold R. Denton (e) This application is for amendment of Facility License R-119, a class 104 License originally issued January 28, 1972 and renewed November 27, 1984 as amendment No. 8 until January 28, 2002. This amendment to a " Possession Only" Facility j l
License will require modification of the FSAR (Section III) l Technical Specifications and Security Plan (Appendices A & D to the FSAR). The Facility has reduced its SNM inventory to zero under its present license and wishes to maintain the facility as a " Possession Only" Facility until the NRC terminates the licen'se. An application for a dismantling plan will be submitted for NRC approval at an early date.
Use of the Facility:
~
The Facility will be utilized for the safe storage of the reactor components and other licensed material until the dismantling effort has been completed and the license terminated.
,o Duration of the License:
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It is desired that the license be effective until its present renewal date January 28, 2002 unless terminated l sooner.
Other Licenses: See Westinghouse Electric Corporation Letter Corporation Information for Licenses Dated December 2, 1979, A.J. Nardi-to Mr.
John G. Davis and Mr. Harold R.'Denton.
1 (f) Financial Qualifications of Applicant:
(1) and (2) See Westinghouse Electric Corporation ,
Letter Corporation Information for Licenses Dated December 2,1979, A.J. Nardi to Mr.
John G. Davis and Mr. Harold'R. Denton.
(3) Estimated Costs of Permanently Shutting Down the Reactor.
Due to the extremely low power history of the core, the-fuel and component structures of the reactor are essentially unirradiated. Dismantling of the core structure and other potentially radioactive portions of the reactor system _could be performed within one week af ter complete removal of the f uel. The following.
provides estamated decommissioning costs (1981 dollar value):
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- a. Project Management Engineering and Labor ~ 6 man months at $70/hr. $72,000
- b. Disposal of Core Components 60,000 )
- c. Decontamination of Facility 10,000 l
- d. NRC's Fee for Ammendment to Terminate License and Final Inspection 10,000 i
- e. Packaging, Transportation and Reprocessing fuel and Source Material 125,000 Unexpected Expenses 50,000 TOTAL $327,000 O
V Following complete removal and shipment of the fuel', waste and sources, the requirement to maintain the room housing the i
reactor as a restricted area would no longer be necessary. I Due to an extremely low integrated power history, irradiation of all core components and support structures is minimal. Radiation levels are well below the prescribed -
limits set forth in Regulatory Guide 1.86 (Table 1) within i minutes after fuel is removed from the reactor.
During the . operating hi, story of the reactor no contamination has been detected that exceeds the prescribed limits set forth in Regulatory Guide 1.86 (Table I).
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l In view of the facts presented above, the room housing the reactor could be cleared for unrestricted use immediately i following complete removal of fuel, waste, and sources a comprehensive survey for contamination and inspection by the commission. )
Estimated one time cost (1981 dollar value) to maintain the shutdown facility in a safe condition:
- a. Radiological Survey, Maintenance.and Administrative 5,000 i
- b. Regulatory Inspection 4.200-TOTAL $9,200 4 (g) Radiological Emergency Response Plans:
Not Applicable l
(h) Alterations to Facility:
Not Applicable- ,
I i
(i) Generation and Distribution of Electric Energy:
Not Applicable-1
-(j) Restricted Data:
Not Applicable I-6 0181N
) Westinghouse Electric Corporation v
Nuclear Sertice Integration Division Pittsburgh, Pennsylvania (15230)
Application for Modification of Facility License R-119, Docket 50-87 to a " Possession Only" Facility License"Section II Environmental Impact Appraisal (3 In accordance with the requirements of 10 CFR 50.30 (f), the y/
following information is submitted:
I l
I I
(a) Facility Environmental Effects of Construction The Westinghouse Nuclear Training Reactor is housed in the j south wing of the Westinghouse Nuclear Training Center, Zion, Illinois. The construction of the room housing the reactor was concurrent with construction of the remainder of the Training Center building; therefore construction of the reactor room alone had no significant affect on the terrain, vegetation, wildlife, nearby waters or aquatic life.
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There are no exterior conduits, pipeline, electrical or mechanical structures or transmission lines attached to the nuclear reactor facility other than utility service facilities which are required in other training center facilities, especially simulator rooms.
The. societal, economic and esthetic impacts of construction of the Reactor facility were no greater than those associated with the construction of a large office building such as the remainder of the Nuclear Training Center.
(b) Environmental Ef f ects of Facility Operation O Air particulate is routinely monitored by means.of a portable air sampler. Dust particles are trapped on a filter paper and counted in a gas flow counter. Concentrations of radioactive particles in air at the f acility have never exceeded limits specified in 10 CFR 20, Appendix B Table II.
Thermo-luminescent dosimeters (TLD) are located at various positions both inside and outside the reactor. room. The TLD's-are currently placed in the numbered locations. indicated on Figure 11-1. Prior to 1978 TLD location were placed as indicated on Figure 11-2. TLD location indicated on Figures 11-2 Ol81N -
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II-1 and II-2 identify locations outside the reactor room.
TLD's indicated on Figure II-3 are located inside'the reactor room. TLD's are processed once a quarter. Average quarterly totals for TLD's located outside the reactor room are given in Table 11.1. Average totals for TLD's located inside the reactor room are given in Table 11-2. The annual totals-for all TLD's are given-in Table 11-3.
Environmental TLD exposure histories confirm the Westinghouse Nuclear Training reactor operations produce radiation levels outside the reactor room we11'below the' limits for unrestricted areas as specified in 10 CFR 20.105.
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OUARTERLY AVERAGE READINGS- I i..
FOR TLD'S LOCATED OUTSIDE THE !
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T.L.D2/PasitionNumber' YEAR 1 2 3u 4 5 6 7 8- 9 10 11 12 1972 .
47.k 7.6 10.6 9.3 7.8 16.8 133.1 - 9.2 -- 45.7
- d. 1973 59.8 180.4 27.6 9).6 35.2 29.0 ,28.7 390.7- 31.1 - 43.9 40.3 a ,
1974 44.3 93.4 34.5 35.1 37.5 36.9 1 '41.7 114.1 35.9 ;40.9 34.0 61.3 1975 46.6 105. 34. 36.7 38.5 34.< ^32.2 191. 34.5 44.1 35.0 50.4 1976 149. 1077. 132. 135. 173. 101. 163. 501. 99. 103. 94 91.
1977 17.1 23.4 19 6 7
24.9 27.5 23.4 '54.2 381.3 36.3 18.4 17.6 16.1 1_
1978 15.0 15.8 18.0 23.8 25.7 18.2 24.9% 333.2 40.3 16.4 % 9m. IS.5 q t ,.
i J 1979 15.4 16.9 16.1- 17.3 18.2 15.9 18.0 99.7 15.0 14.7 15.2 14.6
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1980 15.2 21.8 15.5 19.6 19.3 15.8 \ 20.7 94.4 18.7 15.8~ 15.1 Itv. 2 ;
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' NOTES: ,[ A s.
- 1. All readings in MREM l
' 2. Refer to Figure II-7 for TLD Locations 1978 to present .q y- 3. Refer to Figure Il-2 for TLD Locations prid to 1978 s.
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,/ TABLE II-2 MONTHLY AVERAGE READINGS FOR TLO'S LOCATED IN THE .
REACTOR ROOM T.L.D. POSITION NUMBER 14 15 16 YEAR 13 f 1972 177.5 73.3 45.0 -429.2 !
1973- 287.5 111.6 62.5 961 .6 ;
1974 30.8 38.3 22.5 356.6 l 1975 223.3 75.8 44.2 375.8 1976 200.0 103.3 66.7 1085.8 1977 229.0 133.0 1140.0 819.0 1978 89.8 90.0 800.5 583.5 ;
1979 37.6 47.9 53.4 445.6 1980 31.4 36.9 62.1 266.0 O
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NOTES:
- 1. All readir.gs.in MREM
- 2. Refer to Figure lII-3 for.TLD location ~
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1 TABLE II-3 ANNUAL TOTALS FOR FACILITY ENVIRONMENTAL MONITORING TLD'S TLD Position Number YEAR 1 2 3 4 5 6 7 '8 9 10 11 12 13 14 15 16 i 1972 -
191. 30. 42, 37. 31. 67 533. -
-37.0. - 183. 2130. 880. 540. 5150. l 1973- 239. 772. 110.4 122.4 140.8 87. 57.4 1563. 62.2 - 175.2 161.2 3450. 1340. 750. 11540, 4 1974 132.8 280.2 103.6- 105.2 112.6 110.8 125.2 470.2 107.8 122.8 102. 183.8 379. .460. 270. 4280. .
1975 182.5 419.8 135. 147. 154. 136. 129. 764, 138. 177. 140. 234. 2680. ;910. 530. 4510.
'1976 149 1077 132. 135. 173. 101. 163. 501. 99. 103, 94. 91. 2400. 1240. 800. 13030.
.1977 102.8 82.6 74.5 100.3 106.8 140.1 133. 1525. .67.0 70.5 70.5 61.5 2747. 1593. '13676. 9828.
1978 85. 73. 77.3 100.4 100.1 1%.6 108.7 1403. 62.9 65.6 67.1 66.4. 1077. 1080. %06. 7002.
1( 61.9 33.9 48.2 69.2 72.7 63.0 75.0 398.6 60.0 60.0 59.0 61.0 451. 575. 641. 5348.'
1980 60.9 87.5 61.9 78.5 77.0 63.4 83.0 495.1 74.9 63.2 60.2 64.7 377. 443. 745. 3192.
NOTES:
- 1. All readings in MREM
~
- 2. Refer to FIGURE 11-1 for Positions 1 through 12 (1978 t > Pres 9nt)
- 3. Refer to FIGURE 11-2 for Positions 1 through 12 (Prior to 1978)
- 4. Refer to FIGURE 11-3 for Positions 13 through 16 1
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NOTE: TLD's numbers 3, 4, 5, 6 and 8 are located on Reactor Room roof
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. FIGURE II-1: ENVIRONMENTAL MONITORING (1978 to Present)
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NOTE: TLD's numbers 3 and 4 were located on Machine. Shop Roof TlD's numbers 5, 6, and 7 were located on Reactor Room Roof ;
FIGURE 11-2: ENVIRONMENTAL ~ MONITORING (Prior to 1978)
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/; Another area for consideration is the generation of high and '
\'~') low level radioactive wastes. The fuel elements utilized at the Westinghause Nuclear Training Reactor have been shipped to a NRC approved receiver for reprocessing in accordance with NRC-DOT regulations. Solid radioactive wastes which have been generated will be packaged and shipped off-site for disposition at a licensed waste disposal site. The transportation of such waste will be accomplished in accordance with existing NRC-00T regulations in approved shipping containers.
Potentially radioactive liquid ef fluents are collected in a storage drum and monitored prior to dilution and release to the sanitary sewer system. The sanitary waste system associated O
(d with the f acility is similar to those at university laboratories. Small amounts of chemicals and/or high-solid content water may be released from the facility through the .
sanitary sewer system during periodic laboratory analysis.
Other potential effects of the facility operation, such as esthetics, noise, societal or impact on local flora and fauna are too small to measure.
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O (c) Environmental Effects of Accidents Due to the non-operating status of the reactor and the small quantity of radioactive materials being stored in the facility, accidents which could result in doses of only a small fraction of 10 CFR 1M guidelines are considered negligible. ]
1 I
(d) Unavoidable Effects of Facility Construction and Operation I
The unavoidable effects of construction and operation i involved the materials used in construction that could not be recovered and the fissionable material used in the reactor. No g adverse impact on the environment is expected'from'either of the j unavoidable effects.
(e) Alternatives to Construction and Operation of the Facility There were no suitable or more economical alternatives which couldhaveaccomplishedtheeducationakobjectivesof'this
, facility. The main objective of the facility is now focused on
.e dismantling- the reactor and decontaminating the f acility for free release. ~l II-11 0181N ' .j g1
ex (f) Long-Term Ef f ects of Facility Construction and Operation
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j The long-term effects of a research facility such as the l Westinghouse Nuclear Training Reactor are considered to be beneficial as a result of the contribution to scientific f knowledge and training. This is especially true in view of the i l
relatively low c;pital costs involved and the minimal impact on the environment associated with a facility such as the Westinghouse Nuclear Training Reactor, j 1
1 (g) Costs and Benefits of Facility and Alternatives l I
The cost for a f acility such as the Westinghouse Nuclear
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Training Reactor is on the order of $2 million with very little environmental impact. The benefits included, but was not limited to: training of operating personnel, and education of students and public. Some of these activities could be I
conducted using reactor simulators or radioactive sources, but these alternatives were at once more costly and'less efficient.
There is no reasonable alternative to a nuclear research reactor of the type used at the Westinghouse Nuclear Training facility for conducting the broad spectrum of activities previously l mentioned.
D (Q II-12 Ol81N Y
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WESTINGHOUSE' NUCLEAR TRAINING REACTOR ZION, ILLIN0IS O .
SAFETY ANALYSIS' REPORT REVISED JUNE.1987
- v., 4- FOR ;
" POSSESSION ONLY" R
FACILITY LICENSE R-119 DOCKET NO. 50 i u
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1 1 A ' CONTENTS OF NTR FINAL SAFETY ANALYSIS REPORT l N.J
- l. Introduction - Revised
- 2. Background 2.1 General Description of NTR Facility in the Westinghouse Nuclear Training Center 2.2 History of the Reactor System - Revised 2.3 Sunrnary of Previous Reactor Operating Experience and Reactor Performance - Deleted
- 3. Site and Environment 3.1 General 3.2 Location 3.3 Topography 3.4 Population 3.5 Land Use .
3.5.1 Regional Land Use 3.5.2 Local' Land Use <
l 3.5.3 Heavy Industry, Transportation and Military Facilities !
I 3.6 Hydrology 3.6.1 General 3.6.1.1 Surface Water 3.6.1.2 Ground Water O
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3.6.2 General Lake Hydrology ;
3.6.2.1 Currents, Tides, Waves and Littoral Drift i
3.6.2.2 Potable Water Sources J 3.7 Meteorology and Climatology 3.8 Geology 3.8.1 General 3.8.2 Descriptive Geology 3 . 8 . '. . l Regional Geology 1 k
3.8.2.2 Local Geolgoy i I
3.9 Seismology 3.9.1 General !
3.9.2 Descriptive Seismology l
- 4. Reactor Facility' Description 4.1 Reactor Description - Revised 4.1.1 Reactor Components and Systems 4.1.1.1 Dump Tank j 4.1.1.2 Reactor Tank 4.1.1.3 Core Structure 4.1.1.4 Fuel and Fuel Element - Deleted q 4.1.1.5 Graphite Reflector Rods-l 4.1.1.6 Control Rods, Control Rod Drives and '
Platform - Deleted 4.1.1.7 Moderator-Shield - Deleted 4.1.1.8 Neutron' Source - Deleted 1
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1 l t f~s 3.6.2 General Lake Hydrology
)
3.6.2.1 Currents, Tides, Waves and Littoral Drif t i j l l 3.6.2.2 Potable Water Sources I i 3.7 Meteorology and Climatology 3.8 Geology 3.8.1 General I l 3.8.2 Descriptive Geology ) i 3.8.2.1 Regional Geology ) 3.8.2.2 Local Geolgoy l l 3.9 Seismology j 3.9.1 General 3.9.2 Descriptive Seismology I ,Q 4. Reactor Facility Description V 4.1 Reactor Description - Revised i 4.1.1 Reactor Components and Systems 4.1.1.1 Dump Tank j 4.1.1.2 Reactor Tank 4.1.1.3 Core Structure 4.1.1.4 Fuel and Fuel Element - Deleted 4.1.1.5 Graphite Reflector Rods 4.1.1.6 Control Rods, Control Rod Drives and Platform - Deleted 4.1.1.7 Moderator-Shield - Deleted 4.1.1.8 Neutron Source - Deleted i%.)I III-2 0181N ' W
5.1.2.3 Reactor Lead Engineer O 5.2 Technical Support 5.3 Reactor Safeguards Committee 5.3.1 RSC Organization and General Practices. :j 5.3.2 RSC Responsibilities and Duties 5.4 Facility Operations - Revised 5.4.1 General 5.4.2 Operating Procedures 5.5 Radiation Safety Practices 5.6 Facility Security - Revised q 5.7 Emergency Plans ,
- 6. Initial Reactor Testing and Reactor Operations - Deleted O 7. Safety Analysis 7.1 General - Revised 7.2 Environmental Conditions and Analysis - Revised 7.2.1 Flood 7.2.2 Earthquake 7.2.3 Windstorm 7.2.4 Fire 7.2.5 Riot and Strike 7.2.6 Sabotage 7.3- Operational. Conditions and Analysis - Deleted-III-4 0181N L
g
i i 4.1.2 Reactor Control Systems - Deleted O 4.1.2.1 Control Rod Drive System j 4.1.2.2 Moderator-Shield System 4.1.2.3 Nuclear Instrumentation System 4.1. 2.4 Reactor Trip Systems ! 4.1.2.5 interlock System 4.1.2.5.1 Integrated Interlock Control 4.1.2.5.2 Interlock Bypass 4.1.3 Reactor Auxiliary Systems 4.1.3.1 Water Purification System - Deleted 4.1.3.2 Waste Disposal System 4.1.3.3 Fuel Storage - Deleted 4.1.3.4 Radiation Safety Equipment , 4.2 Facility and Support Systems 4.2.1 NTR Facility and Controlled Area - Revised 4.2.2 Utilities 4.2.2.1 Water and Sewer Service 4.2.2.2 Electrical Service 2 4.2.3 Ventil'ation-1 4.2.4 Compressed Air - Revised
- 5. Organization and Administration of the Facility .
] ~'
5.1 Administration Organization 5.1.1 Corporate Organization - Revised I 5.1.2 Staff Organization-5.1.2.1 Manager 5.1.2.2 Training Reactor Coordinator. O O 1 i III-3 J 0181N
1 7.4 Radiation Conditions and' Analysis' 7.4.1 Normal Operating Levels - Deleted 7.4.2 Loss of Shielding Water - Deleted 7.4.3 Radioactive Material Storage Areas 7.4.3.1 Fuel Storage - Deleted 7.4.3.2 Radioactive Sample - Revised 7.4.4 Irradiated Material Handling . Revised 7.5 Maximum Credible Accident - Deleted 7.5.1 Description and Summary of Accident 7.5.2 Analysis of Accident'- Deleted 7.5.2.1 Introduction 7.5.2.2 Power Excursion 7.5.2.3 Conclusion A 7.5.2.4 References NY e III-5
- m,,
gj
I 1 I I LIST OF' TABLES O 3.4.1 Population Centers of > 25,000 Inhabitants'W'. thin 50 4 Miles of the Zion Site 3.4.2 Population Density
'3.7.1 Meteorological Extremes 3.9.1 Regional Earthquake Occurrences 3.9.2 Modified Mercalli Intensity Scale 1931 O
4 I 1 1 III-6 0181N I o . l
i LIST OF FIGURES 1
-I 3.2.1 General Site Topography l 3.2.2 Site Aerial Photograph 3.2.3 Zion Site 3.9.1 Regional Earthquate Events 4.1.1 . Reactor Assembly i 4.1.5 Graphite Reflector Rod 4.2.1 Restricted Area 4.2.2 Electrical Distribution 5.1.1 Corporate Organization 5.1.2 Facility Organization O
m O Ol81N~
l CHAPTER 1
..O INTRODUCTION As required under Title 10, Code of Federal Regulations, Part 50, this document is compiled as the Safety Analysis Report for the
, Westinghouse Nuclear Training Reactor located at the Westinghouse
' Nuclear Training Center, in Zion, Lake County, Illinoir.. It is the general purpose of this Report to substantiate the safety aspects of- a the facility and to describe clearly the facility design and intended use. This Report includes sections which cover the 'Jesign bases and safety analysis of the facility in accordance with the provisions of 10 CFR 50.34 b.
/ The reactor facility is housed in a 3200 square foot enclosure which makes up the south wing of the Westinghouse Nuclear Training' Center. The boundaries of the facility are established to provide 1 I
the proper radiation safety control and facility security. The reactor is . installed in a separate reactor room and the reactor core is situated approximately eleven (11) feet below ground level. Adjacent rooms house the support-facilities.for the reactor including the console room. The reactor was a light water-- moderated.. graphite reflected and ' light water shielded, highly enriched uranium-aluminum, low power system.- The reactor core, core support structure, moderator-shield water, graphite reflector rods and instrumentation were contained in an open eight (8)' foot 1 III-8 0181N
I l i f^g diameter, aluminum tank. Access into the core is gained only from the top of the reactor tank at ground level. The primary use of the reactor facility will be to store radioactive materials and Reactor components until a dismantling order has been issued. O +V I l i 4 I i j l O L) III-9 0181N W I l
p CHAPTER 2 1 BACKGROUND j l 2.1 GENERAL 3ESCRIPTION OF NTR FACILITY IN THE WESTINGHOUSE NUCLEAR l TRAINING CENTER i l The Nuclear Training Reactor (NTR) is owned and operated by the i Westinghouse Electric Corporation. The Nuclear Training and I Operational Services group, Nuclear Services Integration Division, I l Power Systems Divisions will be responsible for the management of the reactor facility. The reactor is located in the City of Zion,
)
Illinois, and is part of the Westinghouse Nuclear Training Center. The Nuclear Training Center (NTC) is a joint venture.between Westinghouse and the Commonwealth Edison Company of Illinois j (Commonwealth Edison). The NTC building and land is owned by l
' Commonwealth Edison and the internal training and support equipment j i
is owned by Westinghouse. The training programs performed at the NTC and their execution is the responsibility of Westinghouse and the NTC is operated solely by Westinghouse employees. The NTC consist of the reactor facility, two PWR power plant simulators, simulated PWR power plant console rooms, associated laboratories, classroom areas and office space, totaling over 40,000 square feet. Its primary function is the training of Westinghouse customer personnel in the operations, design and management of pressurized water reactor power plants. O. U III-10 ' f 0181N r 1 L
i p The reactor facility is located in the isolated south wing of the t i NTC. The main entrance into the reactor facility is through the NTC building. 2.2 HISTORY OF THE REACTOR SYSTEM r The Nuclear Training Reactor (NTR) has been in existance as a reactor facility at Zion, Illinois for the past fifteen years. The Reactor System achieved initial criticality under NRC Licesne R-119 in February 1972. In August of 1981, an NRC concurred 50.59 change was instituted that changed the normal core configuration from a 37 element, water reflected configuration to a twenty-four element, graphite reflected configuration. A complete and comprehensive analysis was conducted on the new core configuration that concluded (V) that the change involved no unresolved safety questions and an amendment to the facility license was not required. The Facility License R-119 was renewed in 1984 until January 28, 2002. The decision to (lismantle the reactor was made in January of 1987 and the SNM was shipped to NRC approved facilities in May of 1987. i l 1 l l 2.3
SUMMARY
OF PREVIOUS REACTOR OPERATING EXPERIENCE AND REACTOR 1 PERFORMANCE I NA for " Possession Only" Facility License, fC\ v III-11 Ol81N
,e ,g CHAPTER 3 j \" / 1
^
SITE AND ENVIRONMENT 3.1 GENERAL Information presented herein is based largely on the site analysis
'for Commonwealth Edison's Zion Station as presented in the Preliminary Safety Analysis Report (Docket No. 50-295 and 50-304).
The NTR facility is located approximately 2400 feet from the Zion Station, adjacent to the Zion exclusion area as shown in Figure 3.2.3. The proximity of the two facilities makes the Zion site data valid for the NTR site in almost every detail. [] The site is located in Northeast Illinois on the west shore of Lake b/ Michigan about 40 miles north of Chicago, Illinois, and about 40 miles south of Milwaukee, Wisconsin, as shown in Figure 3.2.1. The site is covered mainly by sandy soil with patches of peat and muck. The site is well ventilated and not subject to severe persistent inversion. While tornadoes occur in the region, none i have been reported to effect the lake shore site directly. High winds (ontheorderof70 mph)2anbeexpectedoncein50yearsfrom storms. j l l' ~%J III-12 > Ol81N
3.2 LOCATION .O The site is located in the extreme eastern portion of the city of Zion, Lake County, Illinois, on the west shore of Lake Michigan approximately 6 miles.NNE of the center of the city'of Waukegan, Illinois, and 8 miles south of the center of the city of Kenosha, Wisconsin. It is located at longitude 87* 48.l' W and latitudc 42* 26.8'N. . 1 The Zion site comprises approximately 250 acres which is owned by Commonwealth Edison. The site is traversed from west to east by Shiloh Boulevard near the northern property boundary and by no through ways from south to north. Figure 3.2.1 shows the general topography of the region within a 5 mile radius of the site. Figure 3.2.2 is an aerial photograph depicting the site boundaries and details of the site. . 1 3.3 TOP 0 GRAPHY The topography of the NTR site and its immediate environs is i relatively flat with a mean elevation of approximately 586 feet a which is 6 feet above the level of the lake. Approximately two miles west of Lake Michigan there is a topographical divide causing ; surface water drainage west of the divide to be away from the lake while to the east drainage is toward the Lake. The site itself has very little slope and is relatively marshy. O - 111 ; 0181N-
l I I ) 3.4 POPULATION DISTRIBUTION { Q("N 1 Table 3.4.1 lists the population centers of over 25,000 people within a radius of 50 miles of the Zion site, their geographical relation to the Zion site and their populations. The distance to the closest boundary of the nearest such population center, Waukegan, Illinois, is 3.6 miles. These data are for the Zion Station and would be changed only slightly for the NTR site because of the 2400 ft difference in location. Additional population distribution data appears in the Zion Station Preliminary Safety Analysis Report, referenced in Section 3.1. The 1981 population estimates in Table 3.4.2 are based on aerial O photographs an U.S. Census Bureau 1980 figure for number of people
;O per household. Based on past trends in populations and probable future industrial, commercial, residential and recreational developments, the total projected population of Lake County, Illinois, is 669,000 in 1985; and 2,000,000 in 2000. The Illinois State Beach Park i,mmediately to the south of the site maintains picnic and camping areas. Approximately one mile south of the site, )
within the park, there is also a 100 room lodge which is used year round. 1 m -1. - OlBlN g
t . TABLE 3.4.1
'u Population Centers of > 25,000 Inhabitants Within 50 Miles of the Zion Site.
Distance From The Population Community Site (miles) Direction (1980 Census) Waukegan, IL 7 SSW 67,653 North Chicago, IL 7 SSW 38,774 Kenosha, WI 9 N 77,685 Highland Park, IL 18 5 30,611 Racine, WI 22 N 85,725 Northbrook, IL 23 S 30,735 ( Palatine, IL 26 SSW 32,166 Glenview, IL 26 5 30,842 Wilmette, IL 26 S 28,229 i Evanston, IL 27 S 73,706 DesPlaines, IL 28 SSW 53,568 Mount Prospect, IL 28 SSW 52,634 Skokie, IL 28 S 60,278 Niles, IL 29 SSW 30,363 Park Ridge, IL 30 S 38,704 Hoffman Estates, IL 32 SSW 38,258 j Elk Grove Village, IL. 32 SSW 28,907 I' Schaumburgh. IL 33 SSW 52,319 111-15 0181N l
28,850 ,q Hanover Park, IL 35 SSW Greenfield, WI 37 NNW 31,467 Elgin, IL 37 SW 63,798 Dak Park, IL 37 5 54,887 Addison, IL 37 SSW 28,836 l West Allis, WI 38 N 63,982 New Berlin, WI 38 NNW 30,529 Milwaukee, WI 40 N 636,212 Maywood, IL 40 S 27,998 Chicago, IL 40 S 3,005,072 Elmhurst, IL 40 SW 44,251 Berwyn, IL 41 S 46,849 Cicero, IL 42 5 61,232 Lombard, IL 42 SSW 37,295 Wheaton, IL 43 SSW 43,043 Janesville, WI 44 NW 51,071 Wauwatosa, WI 44 NW 51,308 l Waukesha, WI 44 NW 50,319 Downers Grove, IL, 45 SSW 39,274 Brookfield, WI 46 NNW 34,035 Naperville, IL 47 SSW 42,330 Burbank, IL 48 5 28,462 Menomonie Falls, WI 50 NNW 27,845 O III-16 , Ol81N
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A TABLE 3.4.2 POPULATIDN DENSITY % 0 111-17 W e Ol81N
3.5 LAND USE O ' l 3.5.1 Regional Land Use i The Waukegan-North Chicago-Gurnee area is predominantly an industrial region with approximately 100 manufacturing establishments employing some 30,000
'ndividuals.
i The product of the largest of these manufacturing firms is i pharmaceuticals and chemicals with the most predominant product of the J remainder being in the metallurgical and fabricated metal products field. None of the industries listed by the Waukegan-North Chicago Chamber of Commerce will represent a limitation to the operation of the NTR. The areas starting some 4 miles inland from Lake Michigan are predominantly agricultural regions. The agricultural products are grain crops (mainly corn and wheat), cattle, horses, dairy products and furs (mink ranches). The number of farms in Lake County, Illinois', is approximately 800 utilizing about 40 percent of the county land area. The nearest areas in which there are dairy farms are 5 miles to the west and to the northwest of the site near the Illinois-Wisconsin state line. 3.5.2 Local Land Use The Zion-Winthrop Harbor area is a small industrial region, though there is extensive farming to the west of the area as previously discussed. A major portion of this industry is located between the ( O I III-18 . 0181N k
'I western. boundary of the site and the Chicago and Northwestern Railroad tracks approximately 0.4 miles due West of the NTR location. The industries in this area are:
Name Products Employment Midway Heating and Heating, Air Cond. Air Conditioning and Refrig. Supplies 40 Zion Industries, Inc. Cookies 75 Burges, Anderson and Tate Printing and Office 100 Supplies There is also a warehous'e located in this industrial park. Other industries in the area produce candy, clothing, and printing.
.O The Zion site is bordered on the south by the Illinois State Beach
. Park and to the north by relatively open marshy land with some. . scattered residents located principally along the lake shoreline. I The centers of the communities of Zion and Winthrop Harbor are located about 1.2 and 2.5 miles, respectively, f rom the NTR location. The areas within the Zion and Winthrop Harbor city limits are approximately 6.5 and 3.9 square miles, respectively. O III-19 0181N
3.5.3 Heavy Industry, Transportation and Military Facilities The industries located in the vicinity of the reactor are discussed l in section 3.5.2. These industries consist of only light industries. The Waukegan Memorial Airport, located approximately.4 miles-southwest of the reactor sight does not have regularly scheduled commercial air carrier service. It is utilized primarily for executive and small private air crafts. Chicago and Northwestern : Railroad tracks are located approximately 0.4 miles to the west of I the NTR location. This line is used for both passenger and freight transportation. The major military installation is the Great Lakes Naval Training Center located approximately 10 miles south of the NTR site. Ordinance of this base is limited to a small arms practice range. The staf f concludes that there is virtually zero probability of risk of accident to the reactor from activities associated with military, j heavy industry or transportation operations. 3.6 HYDROLOGY l 3.6.1 General l O l 111-20 0181N
i i l I i 3.6.1.1 Surface Water l O l The Lake County Public Water District has . located a water intake about one mile north of the Zion Plant site and about 3000 feet out in the Lake. This action negated the use of wells. j 3.6.1.2 Ground Water Ordinarily there will be no potable uses of ground water 1 the Benton or Waukegan townships. There are wells in the communities of I Zion and Winthrop Harbor (Benton Township) maintained on a standby basis to meet emergencies. However, of these wells the one with the highest yield is 1025 feet deep due to a 700 foot drop since 1864 in : the artesian pressure of the deep aquifers. These wells are located I near the southern edge of Shiloh Park about 1-1/2 miles west of the
\
Zion plant. location. Considering this location and the l l topographical divide which causes surface water to drain toward the east, any effects on these ground water supplies is very unlikely. 3.6.2 General Lake Hydrology I l The normal water level in Lake Michigan is approximately 580 feet ) above MSL. The maximum recorded water level is 583.2 feet above MSL which occurred in 1886 and the minimum recorded to date in 1964 at 576.6 feet above MSL. I O ll III-21 0181N
l In the general vicinity of the site, the 30-foot depth contour of the Lake is 1.2 miles, and the 60-foot depth contour 2.0 miles from I the shore. 1 3.6.2.1 Currents, Tides, Waves, and Littoral Drift 1 A detailed description of the currents, tides, waves, and littoral . drift appears in the Zion Staticn Preliminary Safety Analysis Report. A maximum elevation of wave run-up and wind tide was 4 estimated to be 6.7 f t. above the normal water level (at an occurrence frequency of once in 500 years). A maximum seiche level of five f t. above lake was considered for the Zion site. Of the two phenomena, the seiche presents the greater potential hazard to the site. Although of greater height, the deep-watch wave will be quickly dissipated as it over-runs the shore and is I therefore of little consequences to structures located at some distance from the shore line. However, the seichel-generated wave will encompass a much greater quantity of water, and the rise in level will endure for longer periods of time. Since the NTR facility is located 3250 ft. from the shoreline land at an elevation 10 ft. above the normal lake level, the site is not endangered by -
]
l either of the wave phenomena, o III-22 Ol81N
3.6.2.2PotableWaterSources The subsurface water table of the area is sloped to the east towards the lake. The shallow aquifers are the sand and gravel overburden i and the underlying dolomite formations. The deep aquifers are sandstone and dolomite formations with a strata of shale above them. The ' free water" in the shallow aquifers over the six county 12 northeast Illinois region is 4.72 x 10 gallons and in the deep 4 aquifers is 3.53 x 10 gallons. However, the artesian pressure of the deep aquifers has dropped some 700 feet since 1864. Since 1957, the cities of Zion, Winthrop Harbor, and the Illinois Beach State Park plus a number of retail establishments in unincorporated communities have obtained their water from Lake Michigan via the Lake County Public Water District (see 3.6.1.1). Two older wells in Zion are maintained on a standby basis to meet emergencies. The next nearest potable water intake which utilizes surface water from Lake Michigan is 6 miles south of the site at Waukegan. Potable water supplies from Lake Michigan are also located at - Kenosha, Wisconsin, and North Chicago, Illinois, ten miles north and l south, respectively, of the site. Others are located farther up and down the lake shore. i i O ' III-23 0181N
3.7 METEOROLOGY AND CLIMATOLOGY The climate of the region around the site. is primarily continental, with characteristic cold winters and warn 3ammers. There is no dry season; precipitation occurs with some uniformity throughout the w year. Average annual precipitation is atout 33 inches, average i annual snowfall is about 40 inches, and tha mear2 annual temperature in the area is near 50'F. l Extreme winds are not expected to exceed 70 miles per hour once every fifty years. Tornadoes occur with relatively high frequency in Illinois, but are mostly found in the southern half of the state. l i l Northern Illinois is well-ventilated, with infrequent periods of I calms. Most frequent wind direction occurrences are southwest and northeast during the warm months of the year, and southwest and northwest during the cool months. The lake breeze effect is an important f actor in wind direction during the summer months. The longest duration of uninterrupted winds blowing from one direction was 39 hours from the northwest. Some extremes of meteorological variables are listed in Table 3.7.1, below: O III-24 0181N
I i Table 3.7.1 O Meteorological Extremes Chicago Milwaukee Highest Temperature 105*F (July 1934) 105* (July 1934) Lowest Temperature -28'F (December 1983). -25'F (Jan. 1875) Greatest Monthly Precipitation 14.17" (Sept. 1961) 10.03" (June 1917) Greatest 24-Hour Precipitation 6.24" (July 1957) 5.76" (June 1917) Greatest Monthly Snowfall 42.5" (Jan. 1918) 52.6" (Jan. 1918) Greatest 24-Hour Snowfall 23.0" (Jan. 1967) 20.3" (Feb. 1924) Maximum Wind Velocity NE 87 mph (Feb. 1894) SW 73 mph (March 1954) Data and analyses in Section 3.7 are based on five years of hourly observations from Milwaukee, Wisconsin and Chicago (O' Hare Airport),-wind summaries f rom Waukegan, Illinois, summaries of climatological data f rom O Wisconsin and Illinois and other reference data of a more specifice nature. Hourly observations over the past six years at the CWE Zion Nuclear Station ! located adjacent to the NTR facility have detected no extremes greater than those tabulated above. 3.8 GEOLOGY 3.8.1 General i l l l 1 The site is located on the shore of Lake Michigan in the extreme 0 111-25 0181N
eastern portion of the city of Zion, Illinois, and occupies portions of Sections 22, 23, 26, and 27 in Township 46 North, Range 23 East. t Marshy depressions and sand ridges comprise the principal surface features. The uppermost soils at the site consist predominantly of granular lake deposits. These sediments are underlain by glacial drif t which consists of till, outwash, and lake deposi?.s. Beneath the glacial soils, Paleozoic sedimentary rocks extena for several thousand feet to the depth of the crystal line Precambrian basement rock. There is no evidence of faulting closer than the Des Plaines disturbances located approximately 25 miles southwest of the site. Other inactive faults exist at a distance of about 45 miles to the northwest and 75 miles to the southwest. 3.8.2 Descriptive Geolgoy ; 3.8.2.1 Regional Geology Bedrock in the region consists of Paleozoic sedimentary rocks which rest on the Precambrian basement rock. The thickness of the Paleozoic sedimentary rocks in northeastern Illinois is approximately 4,000 feet. The bedrock dips gently toward the east at a rate of about 10 feet per mile. O III-26 Ol81N
] The bedrock surface in the northeastern Illinois region is covered ( p i L by a thick mantle of glacial drift, formed when most of the Wisconsin, Illinois and adjacent areas were subjected to repeated glaciation during the Pleistocene epoch. The advancing glaciers scoured major stream valleys and formed the large depressions now l occupied by the Great Lakes. The glacial drift deposited by the glaciers consisted of till, outwash, and lacustrine deposits. Recent deposits in the region consist of unconsolidated sand, silt and peat. 3.8.2.2 Local Geology The site is located on a narrow strip of lake deposits which borders ( the Lake Michigan shoreline. Crossing the NTR and adjacent Zion l N']'J site is a series of low, parallel, beach ridges separated by marshy depressions. The beach ridges are composed primarily of sand. In the depressio'ns, organic materials have accumulated. The subsurface conditions at the adjacent Zion site were I investigated by drilling seven exploration test borings. The test i borings revealed that the site is blanketed by granular lake -
)
l deposits which range in thickness from 24 to 33 feet. The granular j i lake deposits consist of fine and fine to medium sand which contains j l variable amounts of coarse sand and gravel and occasional pockets of j peat and organic material. The granular lake deposits are underlain i by Pleistocene glacial till, glacial outwash, and glacial lacustrine j III-27 Ol81N W i
l l I p deposits. The glacial deposits consist essentially of silty clays, ) 'b) ( clayey silts, and silt; contain variable amounts of sand and gravel; -l contain pockets of granular outwash; and extend to depths ranging i from approximately 102 to 116 feet below the existing ground surface. The glacial tills and glacial lacustrine deposits are firm I to hard and are relatively impermeable. A detailed description of the subsurface conditions at the Zion site is presented in the Zion Preliminary' Safety Analysis Report'(Docket 50-295 and 50-304). Ground water is near the surface over much of the site area. The beach ridges project slightly above the water table, and most of the intervening depressions are marshy and are at or slightly below the water table. A very slight ground water gradient trends to the east and south. A stagnant condition now generally prevails between the beach ridges. 3.9 SEISMOLOGY 3.9.1 General The region within 100 miles of the site is considered an area of 1 minor seismic activity and has experienced a few earthquake events of moderate magnitude during the last 150 to 200 years. The regional earthquake events are shown in Figure 3.9.1, Regional Earthquake Events, and are summarized in Table 3.9.1, Regional Earthquake Occurrences. Earthquake intensities are described in terms of the Modified Mercalli Intensity Scale of 1931 which is explained in Table 3.9.2.
~
0181N-
TABLE 3.9.1 REGIONAL EARTH 0VAKE OCCURRENCES EPICENTER LOCATION AREA DATE INTENSITY LOCALITY N.LAT. W.LONG. 50. MILES 1804 VII Ft.
Dearborn 4.20 87.8 30,
000 Aug. 20 1811 XII New Madrid, 36.6 89.6 2,000,000 Dec. 16 (Felt through- Missouri out Illinois) 1812 XII New Madrid, 36.6 89.6 2,000,000 l l Jan. 23 (Felt through- Missouri out Illinois) ( 1812 VII Mew Madrid, 36.6 89.6 2,000,000 Feb. 7 (Felt through- Missouri ) out Illinois) j l 1883 VI North of 42.3 85.6 8,000 Feb. 4 Michigan-Indiana Border 1886 X Charleston, 32.9 80.0 2,000,000 Aug. 31 (Felt in S. C. Chicago) 1895 VIII Charleston 37.0 89.4 1,000,000 Oct. 31 (Felt through Missouri out Illinois and Wisconsin III-29 0181N
l l l
- p. g TABLE 3.9.1 l O REGIONAL EARTHOUAKE OCCURRENCES EPICENTER LOCATION AREA DATE INTENSITY LOCALITY N.LAT. W.LONG. S0. MILES 1905 V Menominee, 45.0 87.7 March 13 Michigan 1909 VII N.E. Illinois 42.5 89.0 500,000 May 26 (IV at Kenosha) 1912 VI N.E. Illinois 41.5 88.5 40,000 Jan. 2 1917 VI E. Missouri 38.1 90.6 200,000 b 1923 V Cass County, Nov. 9 Illinois 1931 VI Madison, Oct. 18 Wisconsin 1933 IV Stoughton to Dec. 6 Putland, l
Wisconsin 1934 VI Rock Island, 41.5 91.5 , Nov. 12 Illinois l l 1935 VI Timiskaming, 46.8 79.1 1,000,000 j Nov. 1 (Felt in Canada l Wisconsin) l O ' III-30 0181N W ! l l
( TA8LE 3.9.1 REGIONAL EARTHOUAKE OCCURRENCES 1 EPICENTER LOCATION AREA DATE INTENSITY LOCALITY N.LAT. W.LONG. S0. MILES 1939 y Southern Nov. 23 (III at Illinois Janesv.111e, Wisconsin) 1943 II Thunder Mt., Feb. 9 Marinette Co., { Wisconsin 1 1947 S.E. Wisconsin V
)
O i
)
1947 VI So. Central 42.0. 85.0 50,000' Aug. 9 Michigan 1956 IV Postburg, ! July 18 Wisconsin 1956 IV Milwaukee-Oct. 13 Racine, Wisconsin 1968 VII Southern, 38.0 88.5 Nov. 9 (III At Site Illinois Location) i 111-31 0181N
I i l I The principal sources of data are given in the Zion PSAR (Docket O 50-295 and 50-304). 4 l i 3.9.2 Descriptive Seismology l I Northeastern Illinois is considered an area of minor seismic activity. King's distribution of epicenters contours the area as l having approximately three epicenters per 10,000 square kilometers, I a figure near the lower levels of his classification. .The Seismic Zone Map of the United States prepared by U.S. Department of Defense, dated 1966, also indicates that the area is a zone of minor seismic probability. The site itself is free of known seismic disturbance. O Since the beginnin.g of the 19th century, two earthquakes with epicentral intensities of VII, Modified Mercalli Intensity Scale of 1931, and with epicenters within a distance of 60 miles of the site are known to have occurred. The first of these earthquakes, near Fort
Dearborn,
Illinois, occurred in 1808 at an epicentral distance of approximately 35 miles from the site. The second occurred in 1909 south of the Illinois-Wisconsin border near Beloit, Wisconsin, , j at an epicentral distance approximately 60 miles from the site. Including the earthquakes described above, three earthquakes'are known to have occurred within a distance of 50 miles with epicentral intensities ranging from III to VII, and nine earthquakes have been recorded within 100 miles with epicentral intensities ranging from O III-32 Ol81N
11 to VII. In addition to these, a few very great but distant earthquakes may have been felt at the site but with very low intensity, o ! l III-33 0181N
P 1 1 i l
,c3 TABLE 3.9.2 MODIFIED MERCALLI INTENSITY SCALE 1931
{ (Abridged) i l I I. Not felt except by a very few under especially favorable l circumstances. ( l II. Felt only by a few persons at rest, especially on upper floors of buildings. Delicately suspended objects may swing. III. Felt quite noticeably indoors, especially on upper floors of buildings, but many people do not recognize it as an earthquake. Standing motor cars may rock slightly. [] G' Vibration like passing of truck. Duration estimated. IV. During the day f elt indoors by many, outdoors by few. At night some awakened. Dishes, windows, doors disturbed, walls make creaking sound. Sensation like heavy truck striking building. Standing motor cars rocked noticeably. V. Felt by nearly everyone, many awakened. Some dishes, I windows, etc., broken; a few instances of cracked plaster; unstable objects overturned. Disturbance of trees, poles, and other tall objects sometimes noticed. Pendulum clocks may stop. f*) d III-34 0181N
VI. Felt by all, many frightened and run outdoors. Some heavy p\' furniture moved; a few instances of fallen plaster or damaged chimneys. Damage slight. VII. Everybody runs outdoors. Damage negligible tn buildings of good design and construction; slight to moderate in well-built ordinary structure; considerable in poorly built or badly designed structures; some chimneys broken. Noticed by persons driving motor cars. VIII. Damage slight in specially designed structures; considerable in ordinary substantial buildings with partial collapse, great in po,orly built structures. Panel walls thrown out of 3 frame structures. (d Fall of chimneys, factory stacks, columns, monuments, wall. Heavy furniture overturned. Sand and mud ejected in small amounts. Changes in well water. Disturbs persons driving motor cars. IX. Damage considerable in specially designed structures; well-designed f rame structures thrown out of plumb; great in 4 I substantial buildings, with partial collapse. Buildings , shifted off foundations. Ground cracked conspicuously. Underground pipes broken. I I i V 111-35 0181N W
~
X. Some well-built wooden structures, destroyed; most masonary and frame structures destroyed with foundations; ground
. badly cracked. Rails bent. Landslides considerable from river banks and steep slopes. Shifted sand and mud. Water splashed (slopped) over banks.
XI. Few, if any, (masonary) structures remain standing. Bridges-destroyed. Broad fissures in ground. ' Underground pipe lines completely out of service. Earth slumps and land slips in soft ground. Rails bend greatly. l XII. Damage total. Waves seen on ground surfaces. Lines of 1
)
sight and level distorted. Objects thrown upward into the j O I O III-36 0181N
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E metrasiti er tas7mewart FIGURE 3.9.1: REGIONAL EARTHQUAKE EVENTS O III-40 0181N
I l l CHAPTER 4 ( \ REACTOR FACILITY DESCRIPTION 4.1 REACTOR DESCRIPTION NA for " Possession Only" facility License. i 4.1.1. Reactor Components and Systems 4.1.1.1 Dump Tank The reactor dump tank functioned as a storage tank for the moder-ator-shield water. The tank is made of 3/8 inch thick aluminum, has an outside diameter of 12 feet and is 22 feet, 4-1/2 inches deep. ('N The outside surface of the tank is coated with a Bitumastic coating V to prevent corrosion. The tank itself is enclosed inside a cylind-rical pit 24 feet, 1/2 inch deep. The pit is constructed of reinforced concrete with a minimum thickness of 30 inches for the base and 18 inches for the wall. The dump tank is recessed in the concrete pit, 20 inches below the floor level. the concrete pit provides the physical support for the dump tank and the suspended reactor tank (See Figure 4.1.1). . 4.1.1.2 Reactor Tank l The reactor tank, which is constructed of 6061-T6 aluminum 3/8 ; inches thick, is 8 feet in diameter and 19 feet deep. The open () 1 V 111-41 0181N
q ended tank is suspended within the dump tank near the top by a welded, six inch square, ring collar made of 1/2 inch thick j aluminum, which rests on and is coupled to a horiz'ontal I-beam i structure. The I-beam structure consists of four (4), 12 inch beams welded into a square lattice resting on the concrete pit walls and ) i embedded in the concrete floor. The reactor tank is positioned eccentrically in the dump tank so that its outer wall is 6 inches from the west side of the dump tank. This facilitates personnel and equipment access into the dump tank on its east side. An additional collar is bolted against the reactor tank approximately 5 feet from its bottom. Extending from this collar to the dump tank are seven (7) horizontal support rods to prevent horizontal motion of the reactor tank. O The support for the core structure within the reactor tank is provided by an aluminum ring 1 inch thick and 26 inches wide supported by eight (8), 1/2 inch thick aluminum gussets. The ring and gussets are welded to the reactor tank 4 feet from the bottom of the tank. A 2 inch overlap is provided for the core structure whose base plate is 4 feet in diameter. Figure 4.1.1 illustrates these construction features. 4.1.1.3 Core Structure The core is supported by the lower grid plate which is constructed of aluminum and is 48 inches in diameter. The lower grid plate is 2 l 111-42 0181N i
1 inches thick at the edge and 6 inches thick in the center. This plate is directly coupled to the annular support ring in the reactor tank, thus providing support for the core and also preventing the core from shifting within the tank. There are one hundred and forty-four (144) positioning holes in the lower grid plate for fuel elements, control rods, associated shroud tubes and experimental equipment. The upper grid plate, constructed of 1 inch thick aluminum, has an elongated hexagonal shape and assures the proper vertical alignment of fuel elements and control rods. The upper grid plate is located 44 inches above the lower grid plate and has ninety-three (93) positioning holes. The upper and lower grid plates are connected together by intervening aluminum core position guides or shroud tubes and held rigid by several tie rods. Fuel elements were loaded downward through the upper grid plate into the shroud tubes. They were supported by the lower grid plate and. held in position by gravity. The control rod guide shrouds which were mounted on the upper grid plate and served as water dash-pots for the control rod shock absorbers and as support for the control rods when fully inserted in the core.
. I Due to the history of the reactor as an experimental f acility, there exists in the core structure certain experimental positions. the center 7 shroud tubes have been made such that they are removable anti an additional 7 positions are oversized such that an adapter sleede is required to hold the standard fuel assemblies or graphite O :
111-43
l a reflector rods in position. In addition, the outer fifty-ene (51) positioning holes in the lower grid plate are available for experimental equipment. Figure 4.1.2 is a vertical section of the core support structure and Figure 4.1.3 is a top view of the core structure. ! 4.1.1.4 Fuel and Fuel Element 1 NA - No fuel remains at the facility. 4.1.1.5 Graphite Reflector Rods Twenty one (21) graphite reflector rods are available for use in the fs reactor. A graphite reflector rod consists of a 2.625 inch in diameter rod of type G83 graphita forty-eight inches long. The rod has a .500 inch hole bored axially the full length of the rod. A
.500 inch aluminum support rod is inserted through each graphite rod '
with support spacers bolted on each end. A ball joint handling
)
adapter is screwed and pinned to the top of each reflector rod support rod. Figure 4.1.5 indicates the structural support and construct features of a typical graphite reflector rod.
- I 4.1.1.6 Control Rods, Control Rod Drives and Platform l
I NA - For Non-Operating Reactor l l A , 111-44 0181N
4.1.1.7 Moderator-Shield NA for " Possession Only" License. All moderator-shield water has been removed from the facility. 4.1.1.8 Neutron Source NA - Neutron sources have been shipped from facility. 4.1.2 Reactor Control Systems NA for " Possession Only" Facility Licence. 4.1.2.1 Control Roa Drive System NA for " Possession Only" Facility Licence. 4.1.2.2 Moderator-Shield System NA for " Possession Only" Facility License 4.1.2.3 Nuclear Instrumentation System NA for " Possession Only" Facility License O III-45 0181N
I l , 4.1.2.4 Reactor Trip Systems D NA for " Possession Only" Facility License l 4.1.2.5 Interlock System NA for " Possession Only" Facility License 4.1.2.5.1 Integrated Interlock Control NA for " Possession Only" facility License 4.1.2.5.2 Interlock Bypass O NA for " Possession Only" Facility License 4.1.3 Reactor Auxiliary Systems sa 4.1.3.1 Water Purification System NA for " Possession Only" Facility License 4.1.3.2_ Waste Disposal System The operation of the NTR involves the disposal of contaminated wastes only on a very intermittent basis. The disposal of reactor
~
O III-46: Ol81N
l l water will comply with the requirements established in Title 10 Code l of Federal Regulations, Part 20 and other Federal, state and local regulations. The disposal of facility materials and equipment will be in accordance with Reg. Guide 1.86. All materials found to 1 exceed the above requirements and regulations will be packaged {
}
properly and shipped of f site to an authorized receiver of j l radioactive materials for storage, reprocessing or disposal. ! 4.1.3.3 Fuel Storage l NA - No fuel at Facility. 4.1.3.4 Radiation Safety Equipment l O A minimum of three stationary radiation area monitors are present in the facility. Two of the monitors, which can also be used for j I personnel contamination monitoring, are located near the main I l entrance to the facility and in the control room. The third area monitor is located inside the reactor room and causes an alarm to be actuated if the gamma level reaches a predetermined value. Portable radiation monitoring instruments capable of measuring all , expected radiation types and levels are located in the f acility. I 5
- 111-47 Ol81N W
,y- The minimum portable instruments which must be present in the ( ) V> facility are: Detector Range B-y Detector 0-20 mR/hr B y Detector 0-5 R/hr y Detector 1- t 100 R/hr a Detector 0- 1 100,000 CPM A small radiation safety laboratory exists in the f acility in which routine analysis of air, water, and smear surveys are conducted. Laboratory radiation detector systems are available for measuring a, 0, and y radiation. (s) Each member of the operating staff is issued a B-y sensitivethermolumingscentdosimeter(TLD)andadirectreadoution chamber dosimeter whi[h must be worn whenever they are in the facility. Visitors in the facility are either issued TLD's or pocket dosimeters, or they are provided with an escort having personnel monitoring devices. l l l Proper storage containers are kept on hand to store suspect radioactive waste materials until they are shipped of f for disposal. i i l f 9
. I gs, ' 111-48
{ 'sY ' l
\
S././ i 0181N 1
4.2 FACILITY AND SUPPORT SYSTEMS 4.2.1 NTR Facility and Controlled Area The NTR Facility is located in the south wing of the Nuclear Training Center building. The main construction of this building consists of poured concrete, concrete block and steel supports. Figure 4.2.1 describes the Facility layout and also defines the controlled area of the Facility. The Facility building consists of the reactor room, console room, equipment room and other support areas. The Facility building enclosure is approximately 70 feet x 45 feet. f The controlled area which is approximately 90 feet x 100 feet, is enclosed either by a 10 foot cyclone fence with barbed wire on the top or by building walls. The minimum distance from the controlled area boundary to the reactor centerline is 44 feet. Entrance to the controlled area can be normally gained through the main entrance ; door in the south corridor of the Training Center or through either of two normally locked, 20 foot, fence gates. The main entrance door has a standard key lock on the outside and a manual and electrical solenoid lock on the inside. O III-49 0181N
The 27 foot square, 27 foot high reactor room is constructed of 8 inch concrete block walls and has a 5 inch thick concrete floor. The reactor dump tank and concrete pit are centered in the room. Two access doors lead into the reactor room. The 3 x 9-5/6 foot exterior door, which is set in 10 x 7-1/6 foot opening can only be unlocked from the inside and may be used as an emergency exit. The panels supporting this door and closing the remainder of the 10 x 7-1/6 foot opening can be removed from the inside to serve as a large equipment entrance. The interior door, which has a 3 x 9-5/6 foot opening, provides the main access into and out of the reactor room. Access to the Facility and Reactor Room will be controlled in accordance with the Security Plan and as required for radiation protection in accordance with 10 CFR 20. 4.2.2 Utilities 4.2.2.1 Water and Sewer Service The water and sanitary sewer service is supplied by the Lake County Public Water District through the City of Zion system. 4.2.2.2 Electrical Service Electric service is provided by Commonwealth Edison. A substation with a 1000 kVA transformer is located on the Nuclear Training O III-50 0181N
Center, Zion Site. A main switchboard distributes power at 440 volts, 3 phase, 60 hertz to the site. Power to the reactor system is stepped down through a transformer which is independent of the rest of the site. A schematic diagram of the system is given in I Figure 4.2.2. 1 1 4.2.3 Ventilation ) The NTR Facility is heated by an all electric system which also j l heats the complete Nuclear Training Center. The heating control 1 center for the south wing and the reactor facility is located in the upper level of the equipment room. There is an auxiliary 9 kW heater-fan in the reactor room which can be used as necessary. O A separate air conditioning unit, which is independent of the air conditioning unit for the Training Center, exists for the facility and is also located in the upper level of the equipment room. The air in the reactor room is not recirculated through the air conditioning system,'but rather is exhausted through a~ fan in the roof of the room. This fan and the air supply to the room can be . secured from the equipment room. Both the heating control center and the air conditioning unit can be secured either in the facility , or at the main switchboard ih the Training Center Mechanical Equipment Room. O III-51 0181N
I 4.2.4 Compressed Air O Compressed air is supplied f rom an air compressor system installed in the facility equipment room. I i l i O O III-52 0181N
y FAST FILL VLV a i Fa - F. C O >v NO NC
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SUPPORT SPACER I (2.600" O.D.) ll 1I I8 1.1 I I I I I I I I CORE POSITION I I SHROUD TUBE ALUMINUM ROD m! ,1 (2.84 5" I.D.) (.500" DIA.) I 1 i l' il O I I Ii.g 1I GRAPHITE REFLECTOR ROD (2.625" O.D.) I I I I I I I I I l l I II II LOWER CORE SUPPORT fl1 I le. PLATE (6" THICK) SPACER (2.600, 0.D.) 4 I i / > 0 /-
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- 111-55 W
0181N l
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l i I () CHAPTER 5 ORGANIZATION AND ADMINISTRATION OF THE FACILITY 5.1 ADMINISTRATIVE ORGANIZATION 5.1.1 Corporate Organization The administration and operation of the Westinghouse Nuclear Training Center is a function of Nuclear Training Services, Nuclear Services Integration Division, Power Systems Division, Nuclear Energy Systems, Westinghouse Electric Corporation (Refer to Figure 5.1.1). ENERGY SYSTEMS If O POWER SYSTEMS DIVISIONS If NUCLEAR SERVICES INTEGRATION DIVISION i U TRAINING AND OPERATIONAL-SERVICES U W.N.T.C. ZION, ILLIN0IS I II I NTR FACILITY 4
. . 8 III-57 Ol81N
, 5.1.2 Staff Organization j ( ) The NTR facility will be operated under the direction of the NTR l Facility Manager. The staff shall be chosen and qualified to i maintain the facility as a " Possession Only" Facility. The NTR ) Facility staff organizatien is given in Figure 5.1.2. I 5.1.2.1 NTR Facility Manager l I The Manager is appointed by the higher management of Westinghouse { l Power Systems Divisions. He/she is an individual who, by training j l and experience is capable of understanding the reactor, can exercise judgement as to the safety of its operation and administration, and : r k can assume responsibility for changes and modifications in the (v) ! { reactor system. It is the responsibility of the Manager to assure the operation of the reactor facility within the limitations and i constraints specified in the Facility License and Technical Specifications. The decisions of the Manager are subject to higher management review and approval, but this does not relieve the Manager from the final responsibility for the decisions. III-58 v W
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O ; 1 NTR FACILITY MANAGER F TRAINING REACTOR C00ROINA10R t O 'Y f REACTOR I LEAD I ENGINEER l I I 1 l l ( FIGURE 5.1.2: NTR STAFF ORGANIZATION 0181N
i O- 5.1.2.2 Training Reactor Coordinator D The Training Reactor Coordinator is officially appointed by and reports directly to the Manager of the NTR. The Training Reactor Coordinator is responsible for the administration of the NTR Facility with respect to compliance with the Facility operating i license and Technical Specifications, related documentation and records, and Facility reports. The Training Reactor Coordinator also offers technical support for the Facility, and serves as the secretary of the Reactor Safeguards Committee. 5.1.2.3 Reactor Lead Engineer The Reactor Lead Engineer is officially appointed by the Manager of , the NTR. His responsibilities and duties are involved directly with the administration of the Facility. The Reactor Lead Engineer coordinates all the routine maintenance and surveillance activities of the Facility. He reports to the Manager through the Training Reactor Coordinator. 5.1.2.4 Senior Reactor Operator NA for " Possession Only" Facility License. 5.1.2.5 Reactor Operator NA for " Possession Only" Facility License. O e,0,, @
5.1.2.6 Cognizant Person NA for " Possession Only" Facility License. 5.2 TECHNICAL SUPPORT
-In addition to its own personnel in Training & Operational Services the Westinghouse Nuclear Training Center can also teek expertise
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i from the many-varied disciplines.of reactor technology encompassed throughout the Nuclear Services Integration Division of Westinghouse. 5.3 REACTOR SAFEGUARDS COMMITTEE The NTR Reactor Safeguards Committee (RSC) consists of a group of persons of recognized capability in the nuclear and associated fields. The RSC basically functions as a review and advisory committee in matters pertaining to the safe operation of the r$hetor , facility. The qualifications of the committee members must be consistent with the following: (1) Each member must have a minimum of five (5) years industrial. experience in nuclear and related fields and' must have a. minimum of three (3) years of active participation in-his , nuclear orientated discipline. - r III-61 0181N
(2) The experience and knowledge of each member must be applicable to or pertain to the Comittee's responsibility to properly review the facility and its operation from the standpoint of safety. (3) Each member must be capable and willing to exercise his individual judgement in regard to all Comittee reviews and decisions. (4).The " nuclear orientated discipline"'of a minimum of two Committee members must lie in the areas of reactor physics and reactor operations. 5.3.1 RSC Organization and General Practices The reactor Safeguards Committee consists of five or more members, Westinghouse or non-Westinghouse employees, whose experience is in accord with the above qualifications. At least four members must not be in the line organization which is responsible for reactor operations (Training and Operational Services Group, TOS). The NTR Fac'ility Manager is automatically a member of the Committee and the NTR Training Reactor Coordinator serves as the RSC Secretary, a non-voting committee position. One of the non-line organization members'is appointed Chairman by the NTS management and holds the-position for not more than three years. The RSC meets at least once O V
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I j I l each six (6) months. A quorum of the Committee consists of at least ' four members and at least half of those present must be from non-line organizations, d 5.3.2 RSC Responsibilities and Duties The Reactor Safeguards Committee _ reviews NTR activities and advises the Manager and/or whatever echelon of Westinghouse management it feels appropriate on all matters pertaining to the safe operation of j the Facility. The matters which are to be specifically reviewed are listed below:
- 1. Proposed changes or modifications to the facility not described in the Safety Analysi.s Report.
- 2. Proposed changes to the Technical Specifications.
- 3. Proposed normal operating procedures and emergency procedures, and proposed changes thereto. ,
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- 4. Facility operation for compliance with internal rules, I procedure! and regulations, and with license provisions.
- 5. Performance of facility apparatus and equipment.
i Quarterly inspections of the facility and reactor operation are made by an individual committee member. A report of this inspection is made immediately if necessary, or at the next Committee meeting. O III-63 0181N
/3 A semi-annual audit of the radiation safety practices and records is V 1 made by an experienced group of Committee members. A written report is made of this audit and distributed to the Comittee Membership. The of ficial records of the RSC include the minutes of each meeting, special reports on proposed experiments reviewed including the I Committee findings, and reports on facility inspection and radiation saf'ety practice inspections. All Committee reports and meeting ) minutes are transmitted to the membership and through line management up to and including the Manager, TOS. 5.4 FACILITY OPERATIONS 5.4.1 General , The basic responsibility for all Facility operations rests with the Facility Manager. All operations must be initially approved by the Manager. The execution of the approved operations is the responsibility of the operating staff. All Facility surveillance and maintenance procedures are documented by the Facility l Procedures. These procedures are reviewed by the Reactor Safeguards Committee prior to their use. Changes to these procedures which do not af fect the intent of the original procedures may be made by the Facility Manager and then reported to the Safeguards Committee. Changes which can possibly change the intent of the original procedure must first be reviewed by the Reactor Safeguards Committee. This is also true for any new procedure. z u-s4 0181N ,
5.4.2 Operating Procedures All operating procedures must conform with the restrictions established in the Facility License and Technical Specifications. Approved written operating procedures are documented and followed for the following items: (1) Radiation safety practices. (2) Radioactive material handling procedures. (3) Radioactive waste handling procedures. 5.5 RADIATION SAFETY PRACTICf.S O All radiation saf ety and protection practices of this Facility comply with the regulations set down in Title 10, Code of Federal Regulations, Part 20. The major responsibility for the proper control of radiation hazards at the NTR Facility rests with the Manager and the Operating Staff. In conjunction with the technical services supplied by Commonwealth Edison Health Physics Section at the Zion Site and off-site Westinghouse Health Physics groups the proper safety standards and procedures are.to be established. These procedures are documented in the Facility Operating Manual and accurate records of the results of the practices employed are kept. l O
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I l O The radiation safety and protection procedures which are followed s (O include the following items: i l (1) Personnel monitoring, dose limitations and exposure records. , 1 (2) Environmental monitoring and records thereof. (3) Periodic and routine radiation and contamination surveys and records thereof. (4) Radioactive material handling, inventory, storage, receipt and shipment and records thereof. (5) Radioactive waste storage and disposal and records thereof. 5.6 FACILITY SECURITY l l n Q Facility security is the responsibility of the Manager and Operating Staff. Security regulations are implemented by the operating staff. These individuals include the operating staff members, and designated Training Center Management.
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l The facility building (south wing of the Training Center) is fenced by a ten (10) foot woven wire fence which is buried in the ground a minimum of one (1) foot and is topped with three (3) strands of barbed wire. Two gates are located in the fence for the purpose of permitting truck access to the facility. These gates are padlocked closed. The main entrance into the facility is located in the south end of the east hall of the Training Center. O Q.,/ III-66 0181N W
t' Appendix D provides further discussion and reference to the Physical l Security Plan. 1 5.7 EMERGENCY PLANS Written emergency procedures are prepared to guide facility i personnel in the event of unusual occurrences which endanger their j lives. These procedures are included in the Facility Operating i Manual and a shortened version is posted. The plans include all I creditable emergencies and the proper use of the local emergency j l support groups,. including: l l
- 1. Medical Aid and Hospitals
-s ;
( 2. State and Local Police
- 3. Fire Department i
O III-67 W
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CHAPTER 6 INITIAL REACTOR TESTING AND REACTOR OPERATIONS NA for " Possession Only" Facility License.
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r-CHAPTER 7 SAFETY ANALYSIS 7.1 GENERAL This chapter evaluates the safety aspects of the facility and demonstrates that the facility will be operated safely and that credible accidents will not produce any hazardous conditions. The genera,1 safety of the facility in accordance with its intended fmiction is deemed excellent as is evidenced by the Facility's use over the past fif teen years at Zion. The chapter is divided into five sections. .The next three sections deal with categories of conditions that can affect the safety cf the facility; environ-mental, operational and radiation. As a general rule, the analysis of the environmental conditions from a safety standpoint involves evaluating the environment in terms of the increase in probability of unexpected occurrences causing accidents from which hazards can develop. The radiation conditions of the facility are analyzed for ; normal operations and credible incidents that could cause excess i exposures to personnel. Both environmental and operational I occurrences could produce radiation hazards. ] 7 2 ENVIRONMENTAL CONDITIONS AND ANALYSIS l 7.2.1 Flood l Section 3.6 describes the hydrology conditions surrounding the O site. The manium seiche level of 5.0 feet above lake level and the 4 0181N
maximum wave run-up of 6.7 feet above lake level are seen to be of l no consequence at the site since the elevation of the facility is 6.8 feet above the maximum recorded lake level. 7.2.2 Earthquake The key structural components of the reactor are designed to withstand loads from seismic accelerations greater than those which have been recorded or are expected at the NTR Site. The low radiation levels of the material stored at the Facility does not represent a significant hazard to the area surrounding the J Facility. Therefore, in the event of an earthquake of unexpected I strength which causes damage to the reactor and facility, the only resulting radioactive hazards will be localized at the reator site. 7.2.3 Windstorm The maximum expected wind (Sect. 3.7) of 70 mph is not severe enough to cause significant damage to the reactor building. l 7.?.4 Fire i i The buildings at the site are of fireproof construction. Flammable materials inside the building are minimal. Fire fighting equipment ) i is located at several prime locations throughout the site and I includes dry and wet chemicals as well as water. ,,g,, @
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7.3 OPERATIONAL CONDITIONS AND ANALYSIS NA for a " Possession Only" Facility License ,. 7.4 RADIATION CONDITIONS AND ANALYSIS 7.4.1 Normal Operating Levels NA for a " Possession Only" Facility License 7.4.2 Loss of. Shielding Water NA for a " Possession Only" facility License O 7.4.3 Radioactive Material Storage Areas i 7.4.3.1 Fuel Storage NA - No fuel at the Facility J 7.4.3.2 Radioactive Samples and Source Storage 1 J All radioactive materials above exempt quantities are stored in the Facility in appropriate containers and with adequate shielding. ~The.
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radiation levels outside the shields are kept well below that which constitutes a high radiation area. Careful documented inventories , are made periodically to assure that the location of all radioactive III-71 - 0181N @ : I
materials is known. Through proper management of these materials, the possibility of causing an incident that would produce hazardous conditions can be readily kept minimal. 7.4.4 Irradiated Material Handling The practices utilized at the facility when handling radioactive material include: establishment of approved procedures, estimations of the activity to be handled and expected exposure to handlers, adequate practice of procedures involving physical manipulations, careful monitoring of radiation levels when actually performing operations, and procedur.es to be following in case of credible accident. Since the quantities of radioactive materials to be handled are normally sma.ll (usually well below 10 Ci), manual handling of the materials is utilized using appropriate handling tools when necessary. The possibility of a physical accident occurring is credible; however, the resulting hazards produced by the accident will be readily contained within the Facility and will be of no consequence to the public. The clean-up problem which may exist will depend on the scope of the accident and the material in question but it is not expected to be significant. 7.5 MAXIMUM CREDIBLE ACCIDENT NA - For Non-Operating Reactor and Possession Only Facility License.
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