ML20045A789
| ML20045A789 | |
| Person / Time | |
|---|---|
| Site: | 05000294 |
| Issue date: | 03/08/1990 |
| From: | Berger J OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | Patricia Pelke NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 9306140264 | |
| Download: ML20045A789 (1) | |
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%b T Oak Ridge Eneroy/
Associated Pcs: Office Box 117 Environment c Universities Oak Ridge Tennessee 37831-0117 Systems Division March 8, 1990 Mr. Paul Pelke Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellym, Illinois 60137
Subject:
FINAL REPORT - CONFIRMATORY RADIOLOGICAL SURVEY OF THE TRIGA REACTOR FACILITY, MICHIGAN STATE UNIVERSITY
Dear Mr. Pelke:
Enclosed are six copies of the final report of the ORAU confirmatory survey of the MSU TRIGA Reactor Facility. Several extra copies have been included, in the event you want to provide them to the State of Michigan Department of Radiological Health and the University.
If you have any questions, I may be reached at FIS 626-3305.
Sincerely,
/ ,G
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James D. Berge Director Environmental Survey and 7 Site Assessment Program JDB:jls Enclosures cc: C. Haughney, tiRC/6H3 G. Sjoblom, h7C/6H3 G. LaRoche, NRC/6H3 D. Tiktinsky, NRC/6A4 V. Tharpe, NRC/6A4 M. Schumacher, NRC Region III sconc pr 9306140264 900300 t\(
ORAU 90/A-69 Pr ar by 9, AssaiatM CONFIRMATORY RADIOLOGICAL SURVEY universities OF THE Prepared for U.S. Nuclear TRIGA REACTOR FACILITY R:gulatory Commission's MICHIGAN STATE UNIVERSITY Region lH OfHee EAST LANSING, MICHIGAN Sponsored by the Division of industrial and J. D. BERGER Medical Nuclear Safety i
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l Environmental Survey and Site Assessment Program Energy / Environment Systems Division
. FINAL REPORT FEBRUARY 1990 !
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I Oak Ridge Associated Universities is a consortium of colleges and universities and a contractor to the U.S. Department of Energy that explores opportunities, solves problems,' and seeks to make increasingly positive contributions to society through science and technology. ORAU operates in four major areas: medical sciences, science and engineering education, training and management systems, and energy and environment systems.
NOTICES E
h The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.
This report was prepared as an account of work sponsored by the United states Government. Neither the United states Government nor the u.s. Department of Energy, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the occuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or f avoring by the U.s. Government or any agency thereof.The views and opinions of authors expressed herein do not necessarily state or reflect those of the U,s. Government or any agency thereof.
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I CONFIRMATORY RADIOLOGICAL SURVEY OF THE l TRIGA REACTOR FACILITY MICHIGAN STATE UNIVERSITY EAST LANSING, MICHIGAN Prepared by J. D. Berger i
Environmental Survey and Site Assessment Program hj Energy / Environment Systems Division y Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff I M. J. Laudeman J. L. Payne R. B. Slaten C. F. Weaver Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region III Office FINAL REPORT i FEBRUARY 1990 This report is based on work performed under an Interagency ' Agreement g (NRC Fin. No. A-9093) between the U. S. Nuclear Regulatory Commission and the g) U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy.
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TABLE OF CONTENTS i
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List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . 11 List of Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii l
Introduction and Site History . . . . . . . . . . . . . . . . . . . . . 1 l
Site Description . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Survey Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 j Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 I Comparison of Results With Guidelines. . . . . . . . . . . . . . . . . . 5 Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 I
References . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Appendices:
Appendix A: Major Sampling and Analytical Equipment I Appendix B: Measurement and Ana'lytical Procedures Appendix C: Regulatory Guide 1.86 - Termination of Operating j Licenses for Nuclear Reactors l
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LIST OF FIGURES l
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FIGURE 1: Map of Michigan State University Campus, Indicating the Locatic,:. sf the Engineering Building. . . . 8 FIGURE 2: Layout of MSU Reactor Facility . . . . . . . . . . . . . . 9 FIGURE 3: Layout of Room 184 (Reactor Room), Indicating
( Measurement Locations. . . . . . . . . . . . . . . . . . 10 FIGURE 4: Map of Reactor Pit Bottom, Indicating Sampling Locations . . . . . . . . . . . . . . . . . 11
, FIGURE 5: Layout of Ro a 184A (Laboratory), Indicating Measurement Locations. . . . . . . . . . . . . . . . . 12 l
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FIGURE 6: Layout of Room 188 (Control Room), Indicating Measurement Locations. . . . . . . . . . . . . . . . . . 13 l
FIGURE 7: Layout of Room 190 (Supervisor's Office), Indicating Measurement Locations. . . . . . . . . . . . . . . . . . 14 FIGURE 8: Layout of Room 192 (Counting Room), Indicating Measurement Locations. . . . . . . . . . . . . . . . . . 15 l FIGURE 9: Locations of Exposure Rate Measurements in the Reactor Facility . . . . . . . . . . . . . . . . . . 16 r
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LIST OF TABLES I Page TABLE 1: Summary of Surface Activity Measurements. . . . . . . . . 17 TABLE 2: Exposure Rate Measurements. . . . . . . . . . . . . . . . 19 TABLE 3: Radionuclide Concentrations in Samples from Reactor Pit Excavation. . . . . . . . . . . . . . . . 20 t
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CONFIRMATORY RADIOIDGICAL SURVEY OF THE TRIGA REACTOR FACILITY MICHIGAN STATE UNIVERSITY EAST 1ANSING, MICHIGAN INTRODUCTION AND SITE HISTORY Between March 1969 and October 1987, Michigan State University operated a 250 kw (thermal) TRIGA Mark 1 reactor under AEC/NRC license R-il4, (Docket 50-294), for purposes of training students in reactor operation principles and to provide a source of ionizing radiation and neutrons for various research programs. The reactor was fueled with 2.5 kg of 19% enriched uranium -
zirconium - hydride; the core was contained in a water filled tank, located approximately 7 m below grade. No major incidents, involving releases of radiological material, are known to have occurred during the operation history of the reactor. .
Following shutdown of the reactor, the fuel was removed and shipped off-site. In July 1989 the NRC authorized dismantling of the facility.
Chem-Nuclear Systems, Inc. (CNSI) was contracted by the University to perform the maj or tasks of the facility decommissioning. Reactor components were removed; the reactor pool-water was disposed of; and the reactor tank and surrounding activated concrete were removed. A final radiological survey of l
the facility was performed and the results, provided in a November 1989 report )
to the NRC, indicate that the facility satisfies the established guidelines for termination of the license and release to unrestricted use. The Region III Office of the NRC requested that the Environmental Survey and Site Assessment Program of Oak Ridge Associated Universities (ORAU) conduct a confirmatory survey of the facility.
, SITE DESCRIPTION 1
The former TRIGA Reactor Facility is located on the lower floor in the southeast corner of the Engineering Building, near the center of the Michigan State University campus (Figure 1). The facility, shown on Figure 2, consists
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of 5 rooms - the Reactor Room (184), a Laboratory (184A), the Control Room (188), the Reactor Supervisor's Office (190), and a Counting Laboratory-(192).
All reactor related components and most furnishings have been removed; however, several laboratory benches, equipment cabinets, and a hood remain in Room 184A.
There are three small storage wells and the reactor pit in the floor of the Reactor Room (184)(Figure 3). A portion of the reactor pit liner and concrete and soil near the bottom of the reactor pit were removed because of activation.
None of the other facility surfaces required significant decontamination actions.
't SURVEY PROCEDURES Document Review ORAU reviewed the Decommissioning Final Report and Termination Radiation.
Survev Results, prepared by CNSI for the licensee.1 Facility Survey On December 18, 1989, ORAU conducted a confirmatory survey of the TRIGA Reactor Facility. The purpose of the survey was to verify the adequacy and j accuracy of the licensee's final survey, and to confirm the radiological condition of the facility, relative to the decommissioning guidelines.
Gridding .
A 2 m alphanumeric grid system was established on the floors and lower walls (up to 2 m) of all rooms. Grids are shown on Figures 3 to 8. The upper room walls and reactor pit walls were not gridded. Measurements taken on the ungridded surfaces were re ferenced to the floor and lower wall grid, or to pertinent building features.
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Surface Measurements I.
Systematic alpha , beta-gamma, and gamma scans were performed on floors and lower walls using a gas proportional alpha / beta floor monitor, zine sulfide alpha detectors, " pancake" CM detectors, and NaI(Tl) scintillation detectors l coupled to scalers /ratemeters with audible indicators. Gamma and beta-gamma scans of the storage wells and reactor pit walls were also performed.
Beta-gamma scans were performed in the utilities tunnel beneath the building hallway; this area was the former location of the secondary heat exchanger for W the reactor.
I Fourteen grid blocks on the floors and lower walls were randomly selected for surface contamination measurements. Total measurements of alpha and beta-gamma contamination levels were systematically performed at the center and four points, midway between the center and block corners. Smears for removable alpha and beta contamination were performed at the location in each grid block where the highest direct reading was obtained. Total and removable contamination levels were also measured at 37 locations on the upper walls, ceilings, and equipment.
Surface activity measurements were conducted on the pad and piping for the secondary heat exchanger, located in the utilities tunnel, t
Exposure Rate Measurements Gamma exposure rates at 1 meter above the floor were measured at 8 locations within the Reactor Facility area, using a pressurized ionization chamber. The Engineering Building hallway, approximately 20 m south of the i
Reactor Facility, was used to establish the baseline for gamma exposure rate measurements. This area has the same construction history as the Reactor Facility and is located in a non-restricted area, which has no history of radioactive material use.
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Sampling Samples of soil and loose concrete were obtained from the four walls and bottom of the scabbled/ excavated portion of the reactor pit.
L Sample Analysis and Interpretation Smears were analyzed for gross alpha and gross beta activity. Samples were analyzed by gamma spectrometry for identifiable gamma-emitting fission and activation products. Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B. Findings of the independent measurements were compared to Regulatory Guide 1.86 (Appendix C) and the NRC criterion that exposure rates not exceed 5 pR/h above background a 1 m from any surface.
RESULTS l
Document Review The decontamination plan appears to have been adequately developed and !
implemented to ensure that decommissioning guidelines were met. The data j contained in the final report demonstrate that the final radiological status of the facility satisfies the applicable NRC guidelines.
Facility Survey Surface Scans Alpha, beta-gamma, and gamma scans did not identify any areas of elevated contact radiation levels.
Surface Activity Levels 1
1 Results of total and removable contamination measurements are summarized in I
Table 1. Total alpha activity ranged from < 20 to 100 dpm/100 cm ;. 2 toe,1 ;
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l beta-gamma activity ranged from < 360 to 1410 dpm/100 cm 2 . The highest levels of alpha activity were on the floor and lower walls of the Reactor Room and the highest levels of beta-gamma were associated with the lower walls of the reactor pit. Removable alpha and beta activity ranges were < 2 to 5 dpm/100 cm 2 and < 5 to 9 dpm/100 cm ,2 respectively. With few exceptions, total and removable activity levels were below the detection sensitivities of the procedures and indistinguishable from ambient background.
l Exposure Rate Measurements i 1 i
Table 2 summarizes the exposure rate measurements, taken at eight !
locations. Rates ranged from 11 to 12 R/h at all locations. The background exposure rate in the hallway outside the Reactor Facility was 10 pR/h.
I Radionuclide Concentrations in Reactor Pit Samples l
Concentrations of radionuclides in samples of soil and concrete chips from the lower reactor pit area are presented in T61e 3. The only fission or y activation radionuclide present at positive concentrations was Co-60; the highest level was 1.6 pCi/g, in samples from the pit bottom and lower south wall. All samples contained less than the detection limit (0.1 pCi/g) of Cs-137 -
the major gamma-emitting fission product expected to be present. No ]
other gamma-emitting nuclides of reactor origin were noted at levels above their detection sensitivities. 1 COMPARISON OF RESULTS WITH CUIDELINES )
NRC surface contamination guidelines for release of facilities for
_ unrestricted use are presented in Appendix C. The guidelines for residual
/ alpha contamination, based on uranium being the principal contaminant, are:
Total Contamination 15000'a dpm/100 cm2 (maximum in a 100 cm2 area) i 5000 a dpm/100 cm2 (averaged over 1 m2 1 5 1
Removable Contamination 1000 a dpm/100 cm2 For residual beta-gamma contamination, the NRC guidelines for mixed fission and activation products are:
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Total Contamination l
15000 #-y dpm/100 cm2 (maximum in a 100 cm2 )
l 5000 B-y dpm/100 cm2 (averaged over 1 m2 )
i Removable Contamination 1000 p-y dpm/100 cm 2 All total and removable alpha and beta-gamma levels were within these guidelines.
All exposure rate measurements, obtained at 1 meter from the facility surfaces, were less than 15 pR/h and therefore within the guideline level of 5 pR/h above background.
Soil concentration guidelines for other than the uranium and thorium decay series nuclides are established by NRC on a site-specific basis. Although there were no guidelines for Cs-137 or Co-60 established for this decommissioning proj ect , the guidelines typically used are approximately 15 pCi/g for Cs-137 and 6 pCi/g for Co-60. All of the samples contained concentrations of these nuclides well beltw such values. No other significant levels of radionuclides, attributable t's the Reactor Facility operation, were present in the samples.
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L SUMM/aY y On December 18, 1989, Oak Ridge Associated Universities performed a L confirmatory radiological survey of the former TRIGA Reactor Facility, located L
in the Engineering Building of Michigan State University in East Lansing, Michigan. The survey included surface alpha, beta-gamma, and gamma scans; measurement of direct and removable contamination levels; exposure rate I measurements; and determination of radionuclide concentrations in soil and L
concrete samples. The findings support the close-out survey performed by the licensee, and confirm that the radiological conditions of the facility satisfy the NRC guidelines established for release for unrestricted use.
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KILOMETERS FIGURE 1: Map of Michigan State University Campus, Indicating the Location of the Engineering Building a
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f FEET O 6 METERS FIGURE 9: Locations of Exposure Rate Measurernents in the j Reactor Facility 16
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TABLE 1
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS l TRIGA REACTOR FACILITY j l
EAST LANSING. MICHIGAN NUMBER OF MEASUREMENTS TOTAL ACTIVITY REMOVABLE ACTIVITY 2
SAMPLEa GRID SINGLE RANGE (dom /100 cm ) RANGE (dom /100 cm2 )
ROOMa LOCATION BLOCKS POINTS ALPHA BETA-GAMMA ALPHA SETA Reactor Room Floor and Lower Walls b (184) 6 (20 - 100 <360 <2 <5 Upper Walls -
8 <20 <300 - 800 <2 <5 - 9
, Reactor Pit -
5 e 510 - 1410 <2 <5 N Wells -
2 e c <2 <5 Laboratory (184A) Floor and Lower Walls 1 2 <20 - 30 <360 - 530 <2 <5 upper Walls -
1 <20 610 <2 <S Ecuipment -
10 <20 - 40 <360 - 430 <2 - 5 <5 - 9 Control Room (188) Floor and Lower Walls 3 -
<20 <360 - 880 <2 <5 Upper Walls -
3 <20 <360 - 430 <2 <5 Supervisor's Office (190) Floor and Lower Walls 2 -
<20 - 80 <360 - 690 <2 <5 Upper Walls -
3 20 - 80 880 - 1010 <2 <5 Counting Room (192) Floor and Lower Walls 2 -
<20 <360 - 1150 <2 <5 Upoer Walls 0 3 <20 <360 <2 <5
M & M M & Y & W W W Y M $ & & &
- TABLE 1 (continued)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS TRIGA REACTOR FACILITY EAST LANSING. MICHIGAN NUMBER OF MEASUREMENTS TOTAL ACTIVITY REMOVABLE ACTIVITY SAMPLEa GRID SINGLE RANGE (dom /IOO cm2 ) RANGE (dom /IOO cm2)
ROOMa LOCATION BLOCKS PGINTS ALPHA BETA-GAMMA ALPHA BETA utilites Tunnel y Heat Exchanger and -
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<360 e c Piping aRefer to Figures 3 to 8, bash indicates not applicable.
C Measurement not performed.
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TABLE 2 EXPOSURE RATE MEASUREMENTS TRIGA REACTOR FACILITY I MICHIGAN STATE UNIVERSITY EAST LANSING. MICHIGAN Exposure Rate I Locationa at 1 m From the Surface (pR/h) 1 11 2 12 3 12 4 11 5 12 6 12 7 11 8 (Reactor Pit-bottom) 12 Building Hallway (Background) 10 a Refer to Figure 9.
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TABLE 3 RADIONUCLIDE CONCENTRATIONS IN SAMPLES FROM REACTOR PIT EXCAVATION I. MICHIGAN STATE UNIVERSITY EAST LANSING. MICHIGAN I
Sample Radionuclide Concentration (pCi/g)
I Location Co-60 Cs-137 I West Wall 0.1 1 0.la <o,3 North Wall 0.4 1 0.2 <0.1 East Wall 0.7 1 0.2 <0.1 South Wall 1.6 1 0.2 <0.1 Bottom of Pit 1.6 1 0.2 <0.1 aUncertainties represent the 95% confidence levels, based only on counting I statistics; additional laboratory uncertainites of i 6 to 10% have not been propagated into these data.
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I- I g REFERENCES l
- 1. Decommissioning Final Report and Termination Radiation Survey Results, Michigan State University TRIGA R.eactor Decommissioning Project, Chem-Nuclear Systems, Inc., November 1989.
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'I APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT ,
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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their
<I employer.
$ A. Direct Radiation Measurements Eberline " RASCAL" Portable Ratemeter-Scaler ;
Model PRS-1 (Eberline, Santa Fe, NM)
Eberline PRM-6 Portable Ratemeter (Eberline, Santa Fe, NM)
Eberline Alpha Scintillation Detector Model AC-3-7 (Eberline, Santa Fe, NM)
Eberline Beta-Gamma " Pancake" Detector Model HP-260
- I (Eberline, Santa Fe, NM)
Ludlum Alpha / Beta Floor Monitor Model 239-1 I (Ludlum, Sweetwater, TX)
Reuter-Stokes Pressurized Ionization Chamber I Model RSS-111 (Reuter-Stokes, Cleveland, OH)
Victoreen Beta-Gamma " Pancake" Detector Model 489-110
. (Victoreen, Cleveland, OH)
Victoreen NaI Scintillation Detector i Model 489-55 (Victoreen, Cleveland, OH)
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I B. Laboratory Analyses Low Background Alpha-Beta Counter Model LB-5110 I (Tennelec, Oak Ridge, TN)
I High Purity Germanium Detector Model IGC25, 25% efficiency (Princeton Gamma-Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL)
I Multichannel Analyzer ND-66/ND-680 System (Nuclear Data Inc., Schaumburg, IL)
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I ig APPENDIX B
!g i MEASUREMENT AND ANALYTICAL PROCEDURES
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APPENDIX B MEASUREMENT AND ANAIXIICAL PROCEDURES Gamma Scintillation Measurement Surface scans were performed using Eberline Model PRM-6 portable ratemeters with Victoreen Model 489-55 gamma scintillation probes.
I Alpha and Beta-Gamma Scans and Measurements Floors were scanned for elevated alpha / beta levels by passing slowly over the surface with a Ludlum Model 239-1 Gas Alpha Proportional Floor Monitor with 2
a 550 cm sensitive area. Other surfaces were scanned for elevated levels by passing slowly over the surface with Eberline Model PRS-1 portable scaler /ratemeters coupled to Victoreen Model 489-110 beta-gamma " pancake" detectors and Eberline Model AC-3-7 alpha scintillation probes.
I Measurements of total alpha radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC-3-7 alpha scintillation probes. Measurement of direct beta-gamma radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window pancake GM probes. Count rates (cpm) were converted to disintegration rates 2
(dpm/100 cm ) by dividing the net rate by the 4r efficiency and' correcting for I active area of the detector. The effective window area was 59 cm2 for the alpha detectors and 15 cm2 for the GM detectors. The average background count rate was approximately 1 epm for alpha probes and 45 cpm for the GM probes.
I Removable Contamination Measurements I Gross Alpha and Gross Beta
. Smears for determination of removable contamination levels were collected on numbered filter paper disks 47 mm in diameter, then placed in labeled envelopes with the location and other pertinent information recorded. The smears were counted on a low background gas proportional alpha-beta counter.
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I Camma Exposure Rate Measurements Measurements of gamma exposure rates were performed using a Reuter-Stokes pressurized ionization chamber. The average of a minimum of eight readings was determined at a distance of 1 meter from the surface to the center of the chamber.
I Soil / Concrete Sample Analysis Samples were dried, mixed, and a nortion sealed in 0.5 liter (0.53 qt)
Marinelli beaker. The quantity placed in each beaker was chosen to reproduce the calibrated counting geometry and ranged from 600 to 900 g (1.3 to 2.0 lb) of soil. Net soil weights were determined and the samples counted using a high-purity intrinsic germanium gamma detector coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background and Compton stripping, peak I search, peak identification, and concentration calculations were performed using the computer capabilities irherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
Cs-137 0.662 MeV Co-60 1.33 MeV I Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data.
These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection limits of the procedure.
Because of variations in background levels, sample weights or volumes, and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument. Additional I uncertainties of + 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
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I Calibration and Quality Assurance Laboratory and field survey procedures are documented in manuals developed specifically for the Oak Ridge Associated Universities' Environmental Survey and Site Assessment Program.
I Instruments were calibrated with NIST-traceable standards.
calibration procedures for the portable gamma instruments are performed by The comparison with an NIST calibrated pressurized ionization chamber.
Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and DOE /EML Quality Assurance Programs.
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'W APPENDIX C REGULATORY GUIDE 1.86 '
TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS I.
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%,,, c. ! DutKTORATE OF RESULATORY STANDARDS GUIDE '
REGULATORY GUIDE tas TERMINATION OF OPERATING LICENSES -
FOR NUCLEAR REACTORS
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A. INTRODUCTION A hommie havet a pomennononly Econa mun retain, with the Part 50 hasass, authonasuon for special .
4 3 Secuan 50.51,"Duradon of boense, renewal," of 10 nucisar metanal (10 CPR Part 70, "Special Nuclear l
.g mi nar"), byproduct ==<=aal (10 CFR Fart 30," Rules CFR Part 50, "Y '===ng of Producson and Utmaanon
- Faciliams," regares that each na- to operate a of General Apphcability to Mosamag of Byproduct Matsnal"), and souros metenal (10 CFR Part 40, I
production and ue=aa= facikty be usued for a !
sp.eW=d duranon. Upon expiration of the specsfied "1.icanans of Sourcs Matenal"), until the fuel, radio. I pedod, the llenass may be ather renewed or ternumsted actne compaa==ts, and sources are removed from the -
by the C- Secuan 50J2, "Applie=aa== for facility. Appropriate ad==wrestive controls and facility ter===.tfan oflicenses," spennes the requsements that reaparamaan are imposed by the Part 50 liosass and the
-I nues be ssdsGod to teramens an opersdag heense . tachacal specificataans to asume that proper survedlane including the regarement ther the disenstimaast of the is perfonned and that tbs reactor facility is maintained facilhy and disposal of the ---i-- e parts not be in a afe condisson and not operated.
I i=nnent to the a===== defsees and snousty or to ths hesith and safety of the pub 5c. This guide describes A7 ' cari license permits various options and t methods and procedures considered acospeshis by the procedures for heng such as mothbaning. l g Regulatory staff for the taansnation of operstag Rooness for suelser ruectors. The Advmory Conumetes entombment, or dismantling. The requiremenu imposed depend on the option aslected.
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on Reactor Safeguards has been consuhed annaarnas this guide and has concuned in the regulatory posinon. Section 50J2 prtmdes that the licenses may dis.
I E. DISCUSSION mentie and depass of the - , =- -t parts of a nuclear reactor in accordance with exzstag regulations. For research reactors and entical facilities, this has usually l
When a lie === decides to termmate his nuclear meant the duassembly of a reactor and fu shipment reactor operatag hcenas, he may, as a Srst step m the of!ste, somenmes to . another appropnately heensed ,
'I proces, request that hs operanas hasass be Mad to organnanon for further use. The ste from wiuch a !
restnct hun to ponen but not operate the facGity. The reactor has been removed must be decontammated. as necomary, and inspected by the Corrmusnan to deter. ,
I advantage to the hcensus of converung to such a por " My lie =a= is reduced sursemance reapare, menu in that penodic arvemanes of equtpunent im.
nuns wasther unrestacted access can be approved. In the cass of nuclest power reactors, dismanthng has usuaDy been v - ,'u ' by shippmg fuel offsite, portant to the safety of reactor operadon is no longer reqused. Ones this y- " dy houses is issued, nelung the reactor inoperable, and d.yv g of some of I reactor operosion is not pansstted. Other activines the radioscuve componenu. ,
I related to caustion of operettoes anch as uniondag fuel frora the reactor and piecmg it in storage (arther oeste Radioactne componsnu may be either shipped off. l of offsite) may be comanued. site for bunal at an authonzad burial ground or secured I *
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ce the ute. Those raccacun matenals rem => mag on the Duids and waste should be remond from the ute.
I ste must be isolated from the public by phyncal bamers or other means to prevent public accme to hazardous kveis of radsauen. Survedlance is necessary to assure the Adequate radiacon momtonns, environmental surveG.
lance, and appmpnate secunty procedures should be
-"Nad under a possesmonenly license to ensure that the health and safety of the public ts not endangered.
long term misgnty of the bemers. The amount of I sury,mmnre reqmnd depends upon (1) the potential hazard to the health and safety of the public from radscacun matenal r=====g ost the ate and (2) the
- b. In.Ptsee Entomboat. In-place entombment con.
men of sealmg all the remammg highly radioacaw or contammated components (e.g.. the pressure vessel and I miesmy of tbs phyncal hamers. Before areas may be released for unrestucted uss, they must how been deconummated or the radioactmty must how decayed to less than presenbed hmns (Table !).
reactor mternals) withm a nructure integral wrth the biological shield after havmg aD fuel assembbes. radio-acuve flu 2ds and wanes, and certa 2n selected com-I ponents slupped offnte. The structure thould prende The hztnrd asocated with the ret: red facdity :s mtepnty over the penod of tune in wiuca ngmficant ershated by comsdorms the amount and type of quanutzes (greater than Table I levels) of rad 2oactmty remammg conummnon. the degree of confmement of remam with the matenal in the entombment. An I the remmmg radioacuve matenala.the phyncal secumy prtmded by the co*- wt, the susceptibihty to releass of radiation as a result of natural phenomena.
appropnate and contmums surwtHance program should be established under a maa.caly license.
'I and the dunnon of reqmrod survem nr.
C. REGUI.ATORY POSITION -
- c. Removal of. Radioactive Componesta and Dio.
mentiing. AH fuel assetablies, radioacuve fluids and waste, and'other matenals havmg acuvities above ac-l l
cepted unrestncted activity levels (Table I) should be removed from the ste. The facihty owner may then have L APPUCATION FOR A UCENSETO POSSESS BUT 8 NOT OPERATE (W wCN.ONLY UCENSE) unresmeted uns of the ute with no requuement for a heense. If the facihty owner so deares, the re=under of the reactor faciHty may be enm=ntled and au vesuges I A request to amend an operating Heense to a possesionenly licanas should be made to the Desciar of Licennng, U.S. Atomic Energy Commerm, Washmg-ton, D.C. 20545. The requen should indude th*
removed and dzspesed of
- d. Coeversias to a New Nuclear Symem or a Fomil I fonowmginformation:
- a. A descripoon of the currat status of the faciHty.
Fuel System. This alternauve, which applies only to nudear power plants, ut!hzes the ex:stmg turbme synem wnh a new s: cam supply system. The crismal nudear steam supply rystem should be separated from the I b. A deae:iption of measures that wiD be taken to prevent enucality or rescurtry changes and to m umm releases of radscactmry imm the facGity.
electric generaung synem and disposed ofin accortiance wnh one of the prenous three retirement ahamsuves.
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- 3. SURVEILLANCE AND SECURITY FOR THE RE.
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- c. Any y.A changes to the tect:nical speciSca- TIREMENT ALTIRNATIVES WBOSE FLNAL ,
STATUS REQUIRES A POSSESSION.ONLY j tiens that resect the mawaly facihty natus and '
the necessary h==Ny/renrement actmuss to be UCENSE A facany which has been heensed under a posses.
- d. A safety analyns of both the actmtses to be non caly brem may contam a sigmftcant amount of accomphshed and the yme d changes to the tae'm I radioactmry m the form of acuvated and contammated ,
I specScuions.
s.An i. - uj of sc=vated 2:sterials and then hardware and nructural matenals. SurveiHance and commeneste secunty should be provided to asure that the public health and safety are not endange.ed.
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tewha in the facihty.
- 2. ALTERNATWES FOR REACTOR RETIREMENT
- a. Phyncal escunty to prevent inadvertent exposure of pg.sgi should be provided by muluple locked bamers. The r.-s of these barners should =ake it I Four alternatrees for retrement of nuclear reactor facQtties are cozmdered acceptable by the Reguistory nafL These are:
extremely difE= ult for an unauthonad person to sum access to areas where radiation or conumwien leveis exceed those spe= Sed in Regulatory Pouuan CA. To prevent inadwrtet up u., radianon areas abow 5 I a. MothbaHzng, Mothbaning of a nudcar reactor facEity conssts of puttmg the facDity in a nate of pro acave norage. In general, the faccity mey be left mR/hr, such : near the acurated pnmary system of a power plant should be appropnately marked and should not be accem'ble except by cuttmg of welded closures er mtact except that an fuel assemblies and ths radme- ve the d:sasse=bly and removal of substantial nruences J C-2
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and/or shielding matenal Mesns sucf: as a remote- (1) Ennronmental surveys, I readout mtrunon aiarm syurm should be pronded to mdicate to dengnated personnel when a physcal barner n penetrated. Secunty penannai that prow'de access (2) Facihty radiat2on surveys.
control to the fachty may be used mstead of the (3) Inspecucm of the phyncal barners, and I phyncal barners and the mtrunon alarm synams.
- b. The phyncal barners to unenthorned entrancz (4) Abnormal occurrences.
mto the facGiry, e.g., fences. bundags, welded doors.
and access opemngs, should be mapected at least 4. DECONTAMINATION FOR RELEASE FOR UN.
quarteny to assure that these barners have not detenor. RESTRICTED USE ated and that locxs and lockmg apparatus are muc.
I c. A fac!!ity radiauon surwy should be performed at least quarterly to venfy that no radioecuve matenal is If it is desired to termmate a license and to elimmate any further surveElance requiremenu. the facHiry should be sufHciently decontammated to prewnt nsk to the escapmg or bems tunsported through the contamment public hashh and safety. After the decontammation :s I barners m the facihty. Wia: should be done along the most probable path by wtuch radioacuve matenal such as that noted in the ener contamment restons sacsfactonly accomplished and the site mspected by the Comm= mon, the Commission may autactne the hcems to be termmated and the facHiry abandoned or '
could be transported to the outer regions of the facihty released for unrestncted use. The beenene should per.
I and ulumately to.the environs.
- d. An ennronmental radiation surwy should be form the d' =" tion unng the 'followmg guide.
lines:
I performed at least ===nanally to wnfy that no ngnficant amounts of rndunan have been reisased to the envunnn=nt from the facDity. Samples such as son,
- a. The hesmes should make a reasonable e5 ort to ehmmate residual contammation.
wgetation, and water should be taken at locassons for b. No covenns should be applied to ndioacuve I wtuch staustical data has been established dunns reactor operanons.
w surfaces of eqmpment or structures by pamt, platmg, or other cowrms matenal untilit is known that contamma.
tion leveis (deternmed by a surwy and documented) are
- e. A ste ..r. =tive should be dangnated to be below the liams spenned in Table L In addition. a I rurponsible for controihng authonzad access into and movement wnha the facihty.
r=anshle eNott should be made (and documentad) to further memm conumnmuon pner to any sucit covenng.
I f A h m- w ho procedures should be estabihhed for the nouScanon and reportag of abnormal occur. c. The radios =:vsty of the intenor surfaces of pipes, rences such as (1) the entnace of an unautherned dram 1mes, or duerwork should be dete=nmed by person or persons into the facGity and (2) a significant mak:ng measmemenu at 2H traps and other appropnate I chany m the ndianon or contammanon levels m the facihty or the offnte environment.
access pomu, provided contammanen at these locauens is lucaly to be :vp:vsentanw of conta=mation on the stenor of the poes. dram 1mes, or ducrwork. Surfaces of premanes, comoment, or serso which are ifrely to be I
- g. The fonowmg reports should be made:
contanunated bc: are of such :=e, constructen, or (1) An annual report to the Duse:or of f weae95 locanon as to mass the surface maccessfois for purpose U.S. Atenac Energy Comsmeson Washmston, D.C. of measurement should be asumed to be conta:mnated ,
I 20545, ? <-+-; the resuhs of the " . .- .. -tal and facihty radiation surwys, the status of the facility, and an evahmation of the perfoemence of secanty and m excess of the pe== ssable radiation hunts.
- d. Upon reouest, the Comnussion may authorse a licemee to relingmsh possesnon-or control of premises, surwGlance measures.
I eqmpment, or scrap havmg surfaces conumented m (2) An abnormal occurrence repon to the Regula- excess of the !innts specSei This may include, but is tory Opersoons Regional OfBce by telephone wtmm 24 not lim:ted to. sce=al c:rcumstances such as the =2=sfer !
bours of discovery of an abnonnal occurrence. The of premises to another licensed orpmzation that win I abnocnal occ:rrence wC1 also be reported in the annual report described in the precedmg item.
contmus to work with radioacuve matenals. Requesu for such author = anon shoidd prende:
(1) Detaned, rpecSc information desenting the I h. Racords or loss relauw to the foHowns items should be kept and retamed unta the license is termi.
nated, after winch they may be stond wnh other piant recorcia:
prem:ses, equ:pment, scrap, and radioacuve conta:m.
nanu and the =sture extent, and degree of rendual surface contamuon.
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, (2) A detailed health and safety analyns mdi.
canng that the rendual amounts of matenals on surface revtewed and approved in accordance with the require-areas, together with cther consderzuons such as the ments of 10 CFR 550.59.
orospecun use of the premises, soutpment, or scrap. are unlike y to result m an untzasonaole nst to the health if maror structural changes to radioactaw components and safety of the public. of the facihty are planned, such as removal of the
,I preseure veneel or major componenu of the pnmary
- e. Pnor to release of the premises for unrestncted system, a diamantlement plan mcindmg the mformauon use. the hcensee'should mass a compreheneve radiance required by 150.82 should be subantted to the Comrms.
I survey estabhahmg that contammauon is withm the hrmu specSed in Table 1. A survey report should be med with the Director of1.tcenang. U.S. Aterrac Energy non. A dwmentiernent plan should be subtratted for af the alternauws of Regulatory Pomuon C.2 except mothbalhas. liowent, mmor duassembly acuvines may Commamon, Washmgton. D.C. 20545, with a copy to still be performed in the absence of such a plan.
the Director of the Regulatory Operations Regional provided they are permitted by ex2stmg operaung and EI OfLee havmg junsdicuan. The report should be filed at rnantenance procedures. A d2smantisment plan should indude the followmg:
least 30 days pnor to the planned date of abandonment.
The surwy report should:
- n. A desenpuon of the ultunate sutus of the facdity (1) Identfy the y..w
- b. A desenpuon of the dumanthng activities and the precauuons to be taken.
(2) Show that reasonable effort has been made to l
- reduce rendual contw mation to as low as pracusable 4 levels; c. A safety analyns of the dismuttling acuvities including any efDuenu which may be released.
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I (3) Describe the scope of the surwy and the general procedures followed; and d. A safety analyss of the facHity in its ulumate status.
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I (4) State the finding of the surwy in umu spectSed in Table 1.
After rerww of the report, the Comrmaion may Upon satisfactory review and approval of the dis.
mantling plan a dismantling. order is assued by the C=mi-ion m accordance wnh $50.82. When das.
'I mspec: the facGities to ermh the survey prior to grantmg appmval for abandonment.
mantling is completed and the Comrnanon has been notified by lener, the apprepnate Regulatory Opera.
tions Reysonal OfGet mspecs the facility and vennes
- 5. RI. ACTOR R. NIT PROCIDURES completion in accordance wnh the dismantiement plan.
'g If residual radianon levels do not exceed the values m g As indicated m Regulatory Pontion C.2, several Table I, the Communen may termmate the beenz. If ahemauves are acesptable for reactor facihty reurement. these levels are exceeded, the licensee retams the If =mor h mMy os "mothbaning" is planned, this posesnon-only license under which the dismantung E acuvtues have been conducted or, as an alternauve, may
, g could be done by the ex: sung operatmg and mamte.
nasce procedures under the license m effset. Any maxe apphcanon to the State (if an Agreement State) planned acuans involvtag an unreviewed safety quesuon for a byproduct matenais heense.
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I TABLEI ACCZFTABLE SURFACE CONTAMINATION LEVELS I NUCI. IDES AVERACEo e l MAXIMUMo d l REMOVABLED' 5.000 dpm a/100 ed 15.000 dpm a/100 cm2 1.000 dpm a/100 cm 2 I U.nat. U.235, U.*.38, and asociated decay producu 100 dpm/100 ed 300 dpm/100 ed 20 dpm/100 cm2 T,a A Ra 226, Ra 228, I Th.230.Th 228,Pa 231. ~
Ac.0 7,1125,1129 Th-nat. Th.232. St-90, 1000 dpm/100 ed 3000 dpm/100 ed 200 dpm/100 ed I Ra-223. Ra 224. U 232, 1-126.I.131,I.133 .
5000 dpm M/100 cm2 15,000 dpm h/100 cm 2 1000 dpm M/100 ed I Beta-gamma emitters (nuclides .
with decay modes other than alpha emisson or spontaneous fission) except Sr 90 and others noted a'oove.
- _ ,_ _ _ m. _ by - _ _ e b s . _ .. b _ . _ .d ,.r
_ and tag necudes should apply sadopenden 4 I
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bas weed in thss table. dpus (dsauntepanees per nannte) immens the rete of namenom by radionstrue smotenal as determined by correcung es counts per manne oteerved by an apprepnate detector for backpound, escasacy, and soon.stric factors assocated with the mscrosuunstaan.
- Meneersaments of eveense contamasas: sould not be averaged over more than 1 aguase inster. For onnets of less surface arza. the I avezays sound be denved for each sich otpoet.
2 dThe ======a= costernesatsom level appens to an area of pot more than 100 cut ,
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'The amount of removebia rodienetWe ===r==a per 100 cur of surfaes ares abandd be determoed by wiping that area with dry Star or I soft asseripost papac, applyng man-ste possaare, and =====mg the amount of radioactres maternal ca me wrpe enth an apprispnais insuvmeet of kaswa emmency. When reenovehne contamsnation on objects of less marfass area is determmed, the perunent leveh shondd be reduced pre r E---"y and the ennre erface should be wrped.
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