ML20012E321

Confirmatory Radiological Survey of Triga Reactor Facility Michigan State Univ,East Lansing,Mi, Final Rept

ML20012E321
Person / Time
Site:	05000294
Issue date:	02/28/1990
From:	Berger J OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
CON-FIN-A-9093 ORAU-90-A-69, NUDOCS 9004030228
Download: ML20012E321 (40)

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CONFIRMATORY RADIOLOGICAL SURVEY un w *s OF THE lP a nd TRIGA REACTOR FACILITY 1

M MICHIGAN STATE UNIVERSITY I

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EAST LANSING, MICHIGAN Sponsored by the I

DivisionW industrial and J. D. BERGER Medical Nuclear Satuty I

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I Environmental Survey and Site Assessmert Program I

Energy / Environment Systems Division FINAL REPORT FEBRUARY 1990 g

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I Ook Ridge Associated Universities is a conso, tium 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 tedinology. ORAU operates in four o major areas: medical sciences, science and engineering education, training and management-systems, and energy and environment systems, NoDCEs The opinione espressed hwein do not nonosowi6y renooi the opinions of the openewing ineihutione of ook nldge Associeted univatelties.

This toport woe prepared se en sooount of work aponsored by the unhed states Government. Neither the Unhed states Government not sne U.s. Department of snergy, not any of thalt employees, makes any wertenty, espress et impl6ed, et soeumes ony legal liability of toeponalbility let me enouracy, completenees, et uteluinoes of eny informetton, apperetus, product, et pressee 46ee40eed, et represente that he use would not infringe privelely owned r6ghts. Reference hete6n to any spoolf6c commeretel product, proosse, et servles by trade name, merk, manutecturer, et otherwlee, does not necessarily constitute or imply he endorsement or recommendellen, et lowering by the U.s. Government et any spency thoroof.The views end opinions of authore l

emptoosed herein de not noosenerity state et refloot those of the U.s. Government or any agency thereof, i

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9 CONTIRMATORY RADIC1hGICAL SURVEY OF THE I

TRIGA REACTOR TACILITY MICHIGAN STATE UNIVERSITY EAST 1ANSING, MICHIGAN t

Prepared by I

J. D. Berger i

Environmental Survey and Site Assessment Program

)

i Energy / Environment Systems Division i

Oak Ridge Associated Universities Oak Ridge. Tennessee 37831 0117 i

8 Project Staff

'l N. J. 14udoman l

J. L. Payne l

R. 5. 81 sten i

9 C. F. Weaver j

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Prepared for i

Division of Industrial and Medical Nuclear Safety l

U.S. Nuclear Regulatory Commission Region III office FINAL REPORT FEBRUARY 1990

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This report is based on work performed under an Interagency Agreement

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t (NRC Fin. No.

A 9093) between the U. S. Nuclear Regulatory Commission and the

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U.S. Department of Energy.

Oak Ridge Associated Universities performa complementary work under contract number DE.AC05 760R00033 with the U.S. Department of Energy.

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l TA&LE OF CONTENTS I"11 l

List of Figures 11 List of Tables..

............ iii i

introduction and Site History 1

site Description............................

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Survey Procedures 2

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Results 4

Comparison of Results With Guidelines.

5 Summary.................................

7 References.

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Appendices:

Appendix A: Major Sam.plin" and Analytical Equipment Appendix 8: Measurement and Analytical Procedures Appendix C: Regulatory Guide 1.86 Termination of Operating Licenses for Nuclear Reactors l

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LIST OF TICURES i

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1 FIGURE 1: Map of Michigan State University Campus, j

Indicating the Location of the Engineering building.

8 FIGURE 2: Layout of MSU Reactor Facility..............

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FICURE 3:

Layout of Room 184 (Reactor Room), Indicating Measurement Locations.

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i FICURE 4: Map of Reactor Pit Bottom. Indicating Sampling 14 cations.

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FIGURE 5: Layout of Room 184A (Laboratory), Indicating i

Measurement Locations..

. 12 1

i FIGURE 6: Layout of Room 188 (Control Room) Indicating Measurement Locations...'.

. 13

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i FIGURE 7:

Layout of Room 190 (supervisor's office), Indicating i

4 Measurement Locations..................

14

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I FICURE 8: Layout of Room 192 (Counting Room). Indicating Measurement Locations..................

15 FIGURE 9: Locations of Exposure Rate Measurements in i

the Reactor Facility..................

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.,,..cn LIST or TAB 1J.S f.aig 5

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TABLE 1:

Summary of Surface Activity Measurements.

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TABLE 2:

Exposure Rate Measurements.

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TABLE 3:

Radionuclide Concentrations in Samples from Reactor Pit Excavation.

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T C(sNTIRMATORY RADIOLOGICAL SURVEY OF THE

{i TRIGA REACTOR TACILITY MICHICAN STATE UNIVERSITY j

EAST 1ANSING MICHICAN

+

INTRODUCTION AND SITE HISTORY p

Seeween March 1969 and October 1987, Michigan State University operated a j

I 250 kw (thermal) TRICA Mark 1 reactor under AEC/NRC license R 114, (Docket

$0 294),

for purposes of training students in reactor operation principles and g'

to provide a source of ionizing radiation and neutrons for various research p

programs.

The reactor was fueled with 2.5 kg of 194 enriched uranium +

zirconius. 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 l

of the reactor.

]

Tollowing shutdown of the reactor, the fuel was removed and shipped off. site.

In July 1989 the NRC authorised dismantling of the facility.

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Chem Nuclear Systems, Inc. (CNSI) was contracted by the University to perform j

t the major tasks of the facility decommissioning. Reactor components were i

f removed; the reactor pool water was disposed of; and the reactor tank and 9

surrounding activated concrete were removed. A final radiological survey of 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 I

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, j

SITE DESCRIPTION The former TRIGA Reactor Tacility is located on the lower floor in the southeast corner of the Engineering Building, near the center of the Michi an G

State University campus (Tigure 1).

The facility, shown on Figure 2, consists I

I

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).

j All reactor related components and most furnishings have been removed; however, several laboratory benches, equipment cabinets, and a hood remain in Room IB4A.

There are three small storage wells and the reactor pit in the floor of t.he Reactor Room (IB4)(Tigurs 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.

SURVEY PROCEDURES Docunient Review ORAU reviewed the Decommissioning. Final Report and Termination Radiation Survey Results, prepared by CNSI for the licensee.1 Tacility Survey On December 18, 1989, ORAU conducted a confirmatory survey of the TRICA i

Reactor Facility.

The purpose of the survey was to verify the adequacy and accuracy of the licensee's final

survey, and to confirm the radiological condition of the facility, relative to the decommissioning gu delines.

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Gridding g

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 teken on the ungridded surfaces were referenced to the floor and lower wall grid, or to pertinent building features.

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Surface Measurements Systematic alpha, be t a ganna, and gatama scans were performed on floors and lower walls using a gas proportional alpha / beta floor monitor, zine sulfide alpha detectors,

' pancake" GM detectors, and NaI(TI) scintillation detectors

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coupled to scalers /ratemeters with audible indleators.

Camma and beta gamma scans of the storage wells and reactos 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 the reactor.

Tourteen 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, reidway 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.

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 c hanibe r.

The Engineering Building hallway, approximately 20 m south of the 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 ano loose concrete were obtained from the four walls and bottom of the scabbled/ excavated portion of the reactor pit.

Sample Analysis and Interpretation Smears were analyzed for gross alpha and gross beta aceivity.

Samples were analyzed by gamma spectrometry for identifiable gamma emitting fission and I

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 KRC criterion that exposure rates not exceed 5 pR/h above background a 1 a from any surface.

I RESULTS Document Review The decontamination plan appears to have been adequately developed and implemented to ensure that decommissioning guidelines were met.

The data contained in the final report demonstrate that the final radiological status of the facility satisfies the applicable NRC guidelines.

I Tacility Survey Surface Scans Alpha, beta gamma, and gamma scans did not identify any areas of elevated

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contact radiation lovels.

Surface Activity Levels Results of total and removable contamination measurements are summarized in Table 1.

Total alpha activity ranged from < 20 to 100 dpm/100 cm2; total 4

2 beta games activity ranged from < 360 to 1410 dpa/100 cm.

The highest levela 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 2 and < 5 to 9 dpa/100 cm, respectively. With few exceptions, 2

5 dpm/100 cm total and removable activity levels were below the detection sensitivities of the procedures and indistinguishable from ambient background.

1 Exposure Rate Measurements Table 2 summarizes the exposure rate measurements, taken at eight locations.

Rates ranged from 11 to 12 pR/h at all locations.

The background exposure rate in the hallway outside the Reactor Facility was 10 pR/h.

Radionuclide Concentrations in Reactor Pit Samples Concentrations of radionuclides in samples of soil and concrete chips from the lower reactor pit area are presented in Table 3.

The only fission or 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.

COMPARISON OF RESULTS WITH GUIDELINES 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) 5000 a dpm/100 cm2 (averaged over 1 m2 5

llN Removable Contamination 2

1000 o dpa/100 en For residual beta gamma contamination, the NRC guidelines for mixed fission and activation products are:

Total Contamination 15000 A y dpa/100 es2 (maximum in a 100 cm )

2 2

5000 A 7 dpa/100 cm2 (averaged over 1 m )

Removable Contamination i

2 1000 A-7 dpa/100 cm 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.

I, Soil concentration guidelines for other than the uranium and thorium decay I

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 project, the guidelines typically used are approximately I

15 pCi/g for Cs 137 and 6 pCi/g for Co 60.

All of the samples contained concentrations of these nuclides well below such values. No other significant levels of radionuclides, attributable to the Reactor Facility operation, were present in the samples.

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SUleUJtY On December 18, 1989 Oak Ridge Associated Universities performed a confirmatory radiological survey of the former TRICA Reactor Facility, located 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 measurements; and determination of radionuclide concentrations in soil and concrete samples.

The findings support the close.out survey performed by the I

licensee, and confirm that the radiological conditions of the facility satisfy the NRC guidelines established for release for unrestricted use.

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TABLE 1 SIM%RY OF SURFACE ACTIVITY MEASUREMEhT5 TRIGA REACTOR FACILITY EAST LANSINO, MICHIGAN NUMBER OF MEASUREMENTS TOTAL ACTIVITY REMOVABLE ACTIVITY 2

2 SAMPLES GRID SINGLE RANGE (dom /100 cm )

RANGE (dom /100 cm )

ROOMa LOCATIO*:

BLOCKS POINTS ALPHA

-BETA-Gesu ALPHA BETA Reactor Roern (184)

Floor and Lower Walls 6

b

<20 - 100

<360

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<5 Upper Walls 8

<20

<300 - 800

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<S - 9 Reactor Pit 5

c 510 - 1410

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<5 N

Wells 2

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<5 Laboratory (184A)

Floor and Lower Walls 1

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<20 - 30

<360 - 530

<2

<5 Upoer Walls 1

<20 610

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<5 Ecuicment 10

<20 - 40

<360 - 430

<2 - 5

<S - 9 Control Room (188)

Floor and Lower Walls 3

<20

<360 - 890

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<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

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<S Counting Room (192)

Floor and Lower Walls 2

<20

<360 - 1150

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TABLE 1 (contirsed)

SUIMARY OF SURFACE ACTIVITY MEASUREMENTS TRIGA REACTOR FACILITY EAST LANSING, MICHIGAN N'JMBER OF MEASUREMENTS TOTAL ACTIVITY REMOVABLE ACTIVITY 2

2 SAMPLEa GRID SINGLE RA W E (dom /100 cm )

RA %E (d e/100 cm )

ROOMa LOCATION BLOCKS POINTS ALPHA SETA-gap 98A ALP $'.A BETA Utilites Tunnel C

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Heat Exchanger and 3

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%efer to Figures 3 to 8.

D ash indicates not ecolicable.

C 'easureet not performed.

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!I TABLE 2 3I EXPOSURE RATE MEASUREMENTS TRIGA REACTOR FACILITY

,3 MICHIGAN STATE UNIVERSITY

'5 EAST LANSING. MICHIGAN LI Exposure Rate

.I at 1 m From the Surface Locationa (pR/h) 1 11 2

12 3

12 4

11 5

12 6

12 7

11 8 (Reactor Pit-bottom) 12 l

3 Building Hallway (Background) 10 g

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I TABLE 3 RADIONUCLIDE CONCENTRATIONS IN SAMPLES FROM REACTOR PIT EXCAVATIOW

'I MICHIGAN STATE UNIVERSITY EAST LANSING. MICHIGAN 3

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Saaple Radionuclide concentration (DC1/r)

- I Locatica Co-60 Cs-137 i

West Wall 0.1 1 0.la go,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 Bottoa of Pit 1.6 1 0.2

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l aUncertainties represent the 95% confidence levels, based only on counting statistics: additional laboratory uncertainites of i 6 to 10% have not been propagated into these data.

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REFERENCES I

1 1.

Decommfseionina' Final Report and Termination Radiation Survey Results, Michinan State University TRIGA Reactor Decommissionina Proioct, 1

,Chen Nuclear Systems, Inc., November 1989.

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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT I

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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT 8

The display or description of a specific product is not to be conatrued as an endorsement of that product or its manufacturer by the authors or their employer.

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Direct Radiation Measurements Eberline " RASCAL" 3

Portable Ratemeter Scalor Model PRS 1 (Eberline, Santa Fe, NM) iW Eberline PRM-6 Portable Ratemeter

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(Eberline, Santa Fe, NM) l g

i Eberline Alpha Scintillation Detector Model AC 3 7 (Eberline ' Santa Fe NM)

Eberline Beta Gamma ' Pancake" Detector I

Model HP 260 (Eberline,' Santa Fe, NM)

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.Ludlum Alpha / Beta Floor Monitor

'g Model 239-1 (Ludlum, Sweetwater, TX)

.8 Reuter Stokes Pressurized Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveinnd, OH)

Victoreen Beta Gamma " Pancake" Detector Model 489-110 (Victoreen, Cleveland, OH)

I Victorcen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH) 8 8

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Laboratory Analyses Low Background Alpha Beta Counter I

Model LB-5110 (Tennelec, Oak Ridge, TN) t i

High Purity Germanium Detector Model IGC25, 25% efficiency

.l (Princeton Gamma Tech, Princeton, NJ) i Used in conjunction with:

Lead Shield i

(Nuclear Data, Schaumburg, IL) l Multichannel Analyzer ND 66/ND 680 System (Nuclear Data Inc., Schaumburg, IL)

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APPENDIX B lLg

('W MEASUREMENT AND ANALYTICAL PROCEDURES I

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APPEND 1X B MEASUREMENT AND ANAINTICAL PROCEDUP.2S Camma Scintillation Measurement L

l Surface scans were performed using Eberline Model PRM 6 portable r

ratemeters with Victoreen Model 489 55 gamma scintillation probes.

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 l

e scaler /ratemeters coupled to Victoreen Model 489 110 beta-gamma " pancake" I

detectors and Eberline Model AC 3 7 alpha scintillation probes.

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 active-area of the detector.

The effective window area was 59 cm2 for the I.

alpha detectors and 15 cm2 for the GM detectors. The average background count rate was approximately 1 cpm for alpha probes and 45 cpm for the GM probes.

Removable Contamination Measurements

'3:

Gross Alpha and Gross Beta 3

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 i

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 Router Stokes pressurized ionization chamber. The average of a minimum of eight readings was t'

determined at a distance of 1 meter from the surface to the' center of the L

chamber.

W-Soil / Concrete Sample Analysis Samples were dried, mixed, and a portion sealed in 0.5 liter (0.53 qt)

Marinelli beaker.

The quantity placed in each beaker was chosen to reproduce g

the calibrated counting geometry and ranged from 600 to 900 g (1.3 to 2.0 lb) of soil.

Not soil weights were determined and the samples counted using a high purity intrinsic germanium gamma detector coupled to a Nuclear Data Model j

ND 680 pulse height analyzer system.

Background and Compton stripping, peak search, peak identification, and concentration calculations were performed I

using the computer capabilities inherent in the analyzer system.

Energy peaks used for determination of radionuclides of concern were:

.l Cs 137 0.662 MeV Co 60 1.33 MeV l

_I Uncertainties and Detection Limits I

a The uncertainties associated with the analytical data presented in the tables of this report, represent the 954 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 not sample count was less

~

than the 954 statistical deviation of the background count, the sample l

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 detect' ion limits differ from sample to sample and instruraent. 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 C_alibration 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.

Instruments were calibrated with NIST traceable standards.

The calibration procedures for the portable gamma instruments are performed by comparison with an NIST calibrated pressurized ionization chamber.

I.

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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APPENDIX C

,l 3

6 W

.REGUIATORY GUIDE 1.86 e

TERMINATION OF OPERATING LICENSES

)

FOR NUCLEAR REACTORS j

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O' ~REGULATORY GUIDE U.S. AT9tB88 SMS#4BY 008888888005 8

DemeBTORATB 0F RSSULATORY STAssOARDS RSOULATORY00608ts8 I-TERMINATION OP OPERATING LICENSES POR NUCLEAR REACTORS I

A. INTRODUCTIO88 A homemos havag a panamen only hasass sua rema, with the Part 50 usasse, authanamuon for sysmal I

Seatsom $0J1 "Dwanen of Mcsass, maewal," of 10 austeer mesenal (10 CPR Past 70. "Spenal Nualeer.

CFR Part 50, "t 1-n=rg of Produseos aar Vielsesses Messme!"), bypredest maumal (10 CFR Part 30," Rules Passass," isquares that each lisenes m rperses a of Genen! ApphenbBty to 1swastag of Byprodust I

prodsence and =eme=*= teeGity be immed der a Mesenal"), and soures manaami (10 CPR Part 40,

"" darsman. Upon empleases of the apardad "Liesamag of Sousee Masenal"), until the fuel, redle.

pasnod, the liceans may be either renewed or teretneasd neuve esopomaan, and muroes are regnoved from the by the Cama *aian. Seedon 90.82, "Appilsamens for fassty. Appropetste ad=Imierative controls sad factity I

ternmanen ofllenaeus," spectDes the requesments thus tespammean are impeeed by the Part 50 Usemes and the aus be metsood to tenniness en opereeng Ileases, tarhatant spesinsemons to senare that proper surveGanes tastudlag ths sequbement that the demannenamann of the is perfonned and that the roastor fasdity is meintmoed fastny and diepeal of tbs enmpnnant puts act be la a afe soadis6es and not opeemed.

I hemical to the mennen dadema and secutey or to the health and afety of the polene. This guido da==84a A

" di lisenes peastes various options and 3

astbeds and pescadures acesidend ascopenble by tbs procedures for does==*=aning suset as asothba& lag, estomimesaL or hnasmiling. The requirements imposed I

o Regalatory maB Amr the 'amemmenna of opeasting licenses for nuclear manos. The Advisory Coatmestes depend on the opoca seleeted.

on Reassor Safegaards has been essamhed an==== ming this gu6de sad has=====1e6 la the regolatory posenoa.

Seensa 50.82 provides that the lisonnes may dis.

I saantle end dispees c.' the component parts of a nuclear B. OSSCUSSION reactor la assordanes with exsettag regulations. For resserch reactors and entical facalues, tha has usually When a tan==== desdes to ternunate his nuclear meant the 46sassembly of a reactor and in shipment I

seester operatag Heense, he may, e a Asst step a the oftum, somenmes to emother oppropnately bcensed orgamaanon for further uns. The ate from wtuch a presen, request that hs operatag hemass be===adad to roernet han to posses be not operate the faeDity. The reactor has been removed mum be desentenannted. as advantags to the Ha==== of ecoverttag to such a necesary, and Inspected by ttw Commismon to deter.

I p

M'y Haeces is seduced surwemanen reapare.

mee wtisther unreatneted acesas een be approved. In meats la that penodle arveElence of ecpupment is.

the esse of nuaient power reactors, diamenthng has portant a the safety of seestor operance ts so longer suaDy been --

. ' " by sluppas fuel offste, I

toepssed. Cace this,-

'-' J, Hemose is immed, malung the reactor inoperable, and dispoems of some of reassor opersuca is 1 mot peaststed. Other aestvenes the rad 6anstive componsnu.

related to esandom of symaniens each as =mnc-itag fusi from the rummer and piectag tt la storage (etsber contos Radiosense esmposeau may be either shipped off.

I of offatte) may be contmoed.

alte for bunal at an authonsed bunal ground or secured I

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o m m.e.s be -.e sta.

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see sees be innlened frees the pebbs by physeal barness AdMlumes ressuem meestomag, enwreamental surve0 er oest mean to preams pubus asses to hasandom lance, and appsopnose sneunty prosedwas should be levels of radanuen. Survedames a fineme=ry to anwe the amah uneer a ;

n'y hasam to easme that long term mesytty of es bemen. Tbs assount of tan heale sad safety of the potus is not endangered.

I swvedlanse sequesd esponds upos (1) the potestsal basesd to the health and safety of the puhus fross

b. k>Ptses Easombesent. la.pless emembtneat son.

redecesovo anneaal rammasas sa the see and (2) the een of senhos au the r=mamnag highly radiossaw or meegsty of es playasal beenen. Dadose areas say be eastenmoind===pa===u (e4 es preeswe vessel and I

seleased for unnamened me, they mest hose been seestor mtsunals) walsa a arusture integral with the desonenmuseem$ er the raamaaneiry aua have decayed beeloglel shseld aher having as fuel asombben, radio, to less thes psenellsed homas (Table 1).

aserve Sunds sad wenes, and eersma seisaed som.

ponesa slupped offets. The structure should prowde I

The hasard assessed with the foured facihty a mtegnty over the pened of tune in whaert agruficant evolussed by erandarsag the assount and type of quasuties (grants than Table ! levels) of radioactmty romandag anntasmaanna the dessee of manAmame" of mass wah the fastoral a the entombment. An I-the rammeneng radoessee motoriala, the phyncal seewity appropnase and conneums surve Ramos pr grain abould psovided by the armanament, the susceptibetty to be seuMished under a posesmospoaly lissess.

releans of mendes as a resett of annual Wa "d **

• I "F8'*8

s. Renoval of Rama==tive Q

^ sad Dlo, B

seassilag, AR fuel asombuss, radosense Quids and C. REtBul.ATORY POSITION weste, and'ather astenals bevtag asuvtties above ac.

espied unroesteasd andvity levels (Table !) abound be I

1. APPUCATION FOR A UCENER TO Pom2t SUT removed frees the su. The fasetty owner may then have NOT OPERATE (PoetteuCN4MLY UCENEE) unrestnesed oss of the as with no requiremsat tw a thana. If es facShy owner so deares, tbs runatador of A reqossa to amand en operestag Besass to a the roaster fandley tasy be 44umentled and au vesuges I

" y theensa should be made to the D6 rester removed and esposed of.

of 1 knanalng. U.S. Atoscis Bastgy f'aramammaa. Wastung.

tea. D.C. 20$45. The segeen should lastude the

d. Cosveeles to a New Noaiser Symen or a Feed foDowinginfammam*

Feel Sysma. This absensove, widch applies omty to I

maaleer power plaam. u Genes the emessag turbme symem

a. A doestpose of the surisat susus of the fasotty.

with a new messa supply sysseen. The orismal auskear sesam supply systems should be separated from the I

b. A desenpeks of mesess that wG1 be takes to ensetric pseerating sysess and disposed of m accordance prevent anneauty or ressemry changes and to unairn==

with one of the previos three retitement alternauws.

rolesses of radioneuvity frees the faeGiry.

3. SURVE1LLANCE AND SYCURITY FOR THE RE.

I

c. Any proposed changes to the testudeal spesinor TIREMENT A1.TIRNATTVIS WBOSE FINAL uous the ro6ect the,

17 facGtry natua and STATUS REQUIRIS A POS$13510N.ONLY the naammary enamamblyhousemsat asuvtnes to be UCENSI I

periossed.

A faeGky wtuch has been hasased under a pocas.

d. A safety analyus of both the astmass to be sosponly hasam any contam a ngiensant amount of z

-nf f and.e proposed abanges to the testmisal rasossamty a the form of acuvesed and contaminated hardwese and nrustumi tastermia. SurwGlanes and I

7" m

- seeunty should be prowded to assure that

- >< u

e. An laventory e( aeoveted==tariah and their the pubus health and safety ese act endaagsred.

locastoa ks the faoGety.

I

a. Phyesal secumy to prevent inadwrtsat exposure

2. ALTERNATfYES FOR REACTOR RETIREMENT of personnel should be provided by mulupne locked bamers. The presense of these bamers should maxe it Four alterneuves for retusment of nuclear reactor m

4 difDealt for an unasthensed person to gam I

facGities am soendered neceptable by the Regulatory necess to areas winere radiation or contanimauon levets maff.These are:

escoed them spectned in Regulatory Posuon C.4. To present medienent exposure, radianon areas abow $

a. Mo.beRtng, Mothbaatas of a nuelsar reactor mR/hr, such a near the acavated pranary sysem of a I

facGAty coasses of puttag the facGity to a nate of power plant, should be appropnetely masked and should proteserve morags. la general, the facGity mary be left not be sensaible surept by cuttmg of welded closures or stast exasyt that aR fusi ameabiles and the rasboscove the disamembly aad refnovel of substanual structures

~~

C-2

p I

I and/or steekkas mateneL Meem such a a remote.

(1) Esmreemanal surwys, I

reedoet mawson alassa syneen should be pnmeed to indiants to daagnated posesemel wtsa a phymeel barner (2) Fasikey radianen surwys.

a peassated. Seeunty passemel that provibe access control to the famiirty may be used maced of the (3) Inspessoas of the phyasal bamers, and I

physsel besrises and the msnman alens symmma.

(4) Abeormal oesurrences.

b. The phrasol barries to unessbormed entrense mio the feeWey, e4., isnea6 wannge weigeg doom,

~I and esame opsamsk should be toopened at nees

d. DSCOPfTAldDIATION FOR RELEASE FOR LH.

querserly to asun that thee barnen have not detenor.

Rgrfgucign um ated and that lossa and neslung appassus us must.

I If it is dessed to terramate a lleense and to ehmmate

s. A fandhry radianca surpoy should be perfooned at my further surve81enes regaremeau, the fasihty should least quarterly to versfy that so rammamsve meterialis be sufnmently desentanupated to prevent ruk to the esengsag or bang tassponed tiuough the sontmament publie haakh sad safety. After the decontanuantion a I

barnes a the feelbry. $scaphag should be done along stanfastorey assomphshed and the ute mspected by the mes probabis pesh by wheek radioastlw matsnal the Co==nman the Connannon may authorse the sunk a that mored la the immer sonumammam repoas heemse to be tarmanated and the faellity abandoned or could be teasponed to the esser regicas of the fasihty reisesed for umeansted use. The tiennese should pet.

I ad ulthmose6y to.the envhoma, form the da==-*=

usag the'foDowns smde.

hass:

d. An eviromaanal rama*= survey should be I

performed at loom sesdamanaBy to vestfy that no

a. The hasases should asks a resonable edert to agaAssos aumanes of sammenn beve been reisand to the shadaste rendual sont===amnan-amreament from the feetty. Samples meh as sot, segnation, and weser shoeld be taken at locatness for

b. No sevanas should be appued to radioacave

'I wh6ch saastseent dem hos basa =mam=d duang reestor surfaces of espapment or structures by psant, plauss, or op= men-other semens notestal untilit is known that contanana.

ties novels (deamuned by a surwy and doemanated) are

a. A sas.v abossid be densmesed to be below the lines speelned la Table L la addition, s I

respamede for sentraalag ausbaneed ascan hste and veesonable eNort should be made (and desumsated) to saevnamaan wedda the fastity.

further mammhe somammansa pnor to any such

coveses, I

f. Adnedarasive procedures should be emahlkhed for the not18essoa and repornag of abnormal oeoar.

c,.The radk my of the intener surfaces of pipes, tenses such as (1) the entnmes of an meesthonsed dmin ham, or ductwork should be deteramed by persos er pemens into the faeGity and (2) a afahaat mannes masuremen s at a!! traps and other appropnate I

stunge is the radiassa or sostessassea )evels ta the aseses pouns, pnmded contammason at these losanons faskty or the oftas sovireament.

is IDaly to be representaava of contaannetion on the misnor of the papes. dram haes, or ductwo it. Surfaces

s. The foDowing repone should be meda:

of profanes, eqmpment, or scrap which are likely to be conta==='ad be are of such ans, consrucuos, or (1) As anmal repset to the Diremor o(T wnmas lossuon as to mese the surface mama==ible for purpose U.S. Atom 6c Raery Coomassen Washagion D.C.

of.

.~ t should be asumed to be contarmaated 20548, essadatag um resules of the enstr====mtal and in essess of the pernessable radiataca hanu.

I feeWay radiades serveys, thh masus of the fasSity, and sa ovahamba of the psedermansa of esamtey sad

d. Upsa reques, the Comnueden may authorse a susselRance metamos.

lisonnes to reknquish ponenion or control of premises, I

eqmpsest, or susp having surfanos contananated in (2) As abnormal ossacrease report to the Regulo.

emesse of the linau specified. This may include, but is tory Opieasons Reposal OfBee by telephone withm 24 not htmted to, speaal carsumstances such as the transfer hours of dissowry of se uhmonast osennense. The of premtses to another llosased organization that wiD abnonaal oseurtenor wlD also be reponed ta the annual continue to work with radioacuve matenais. Requesu report demeribed in the preesdtag item.

for such authonasuon should provide:

h. Records or logs relasve to the foBowas items (1) Detaned, spectSc informanos describing the I

should be kept and retained untu the license is tenni-premuss, equipment, scrap, and radioacun contarm.

noted, after which they rusy be stored with other plant manu and the nature, extsat, and degree of rendual

- e n.m C-3

I m Ade.d. ~.a.da,ety

y. m..

m. -p m es m

e.,m-.o_

sauas that the reedual amouse of matenals on surface reviewed and opposed a asserdamm with the require, areas. topther wie othee seendereuens suah as the nwau of 10 CFR 950Jf.

peeposuve un of the prenases, equipment,or sersp.are unukely to resent a na unsanomatie rak to the health lf ager streetural changes to redteestros semposeats and estery of the pubha, of the fasthty are phoned, sash as removal of the I

penure vessel or maper====f====a of the prurary

e. Pnot to release of the premsses for unrenneted system, a thsamistisemat pian meludan6 the taformanon um. the hamuses should make a :

2 _,rednamos roepssed by 55032 should be sutanned to the Conano.

I survey ematdthsag thus==*v===**== ts wutua the sea. A diammallement' pies should be subastted for aR c

hases spostBed la Table 1. A surwy repart should be the alterneuves of Regulatory Pesuon C.2 essept med wie the Duomar of t.neenmas, U.S. Atonne Raergy mothbalhas, Nosever, asser senessahiy asuvines may Ceauenmen. Washngtsa. D.C. 20$48, wie a espy to aiu be performed in the absense of such a plan.

'I the Derester of the Regalasory Opeist6sas Repenal prowded they are penamed by exasung opereung and Omas havingjunsdienoa. Tbs report abound be Sted at am.atenames prosedwes. A dismaatismaat plan should 1esst 30 days poor to the planned dass of =had=== rat.

in ede the foRowag-

'nis surwy report shoundt I

a. A desertption of the situente status of the fastuty (1) Ideanfy the presatsast

b. A doesnposa of the dinamattin6 asuvines and the (2) Show that ressoashie eSort has been made to pressumons to be taken, I

rednes res6 dual semanumattaa to as low a presumabis

s. A safety analys of the dissentling asuvities leveis; taaluding any emusas which any be released.

I (3) Deaurfte the esope of the surwy and the peeral procedures foDowed;and

d. A afety analyas of the fanatty la is ultimate

' matus.

(4) Stass the Sadlag of the sarwy la uma I

spost8edia Table 1.

Upsa adsfastery review sad approval of te dis.

aanding plan, a shammatting order is issued by the After revese of the report, the Comedmien sney Comunismen ta asserdanes with 150J2. When da.

I tespea the fastitles to scaAna the airwy prior to mantung is arampia'ad and the Coenatsmen has been gesung appoval for ah==h===<

aedned by letter, the apprognate Regulatory Opera-noms Reposal Ofoes inspoon the faatty and verifles

s. REACTOR RETEDENT PROCEDURES sompledon la uomdanse wnh me esmandement plan.

I If raidual radanos lewis do not enesed the value in As ladianted ta Regulatory Pooden C.2, everal Table 1, the Conunamon may ternumste se haansa. If altenauves are asseptable for reemot fuelDry retirement.

these levels are easseded, the liesasse retams the If meer d=====hiy es "mothbaulag" is planned, this p_2 -5y lisease under which the dismantung

~I sould be done by the ensung opesettog and remate-aedvines have been saaduated or, as an alternauve, may naam preesdwes. under the 11 ease a eneet. Any maae applieanon to the State (if an Agreement State) planned assess lavolvuig an unroviewed afety question for a byproduct mawnals beenes.

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I' TABLEI ACCEPTABLE SURFACE CONTAMIN ATION LEVELS AVERAGIOC

\\

MAX 1MUMbd l

REMOVARLESe NUCL1Dga i

p. net, U.35. U 238. and 5.000 dpm s/100 ed 15.000 dpa al100 car:

1.000 dpan al100 cM I

asemented doesy peduou Treasuresca. Ra.226. Ra 228, 100 dpen/100 ed 300dpm/100ed 20 dpm/100 ed

~

I Th.30. Th.23.Ps.231.

As.: 7.1125.1129 Th ast. Th.232. $r 90, 1000 dpm/100 cM 3000 dpm/100 cm2 200 dpm/100 ed I

Ra 33. Ra.224. U.232.

1126.1131.1133 nee games eastten (nucildes.

5000 dpm M/100 cM 15.000 dpm M/l00 cm2 1000 dpm M/100 ed I

with desey medes other than alpha aneman or spessemos namen) eassp Sr.90 and others noted about.

I eWhose oestems -- by toeb esph> and beergennee assemag mentos seassa es huseu estabhahed let septe. sad base gismeareasitag W sheeM oppsy adopenteady.

I t,,,eg to tus inhes, eps (duemiennenes pas mennen seems es see of m W sesceswee asional as deevnesed by eemenne A

no esenes per messe steerved W m oppsegnese detacuer for tem 5reena, etRcasesy, and gecensene fastoes eeneestes wie the 8lN*H*'"**

eMassenessoas of gueteps oestanteest shonM act be evenped euer esove then 1 squese senter. per obsses of less surface eres, the I

avesepe steeld be desmed for each esti chpoch 2

eThe emme=== - naset oppdbes to es esse of pot mese een 100 cat.

'The emeest of sumosekte sneensilse=====a per 100 em2 of serfees was sheeM tse entenmoed 1pr sepses that eres me dry futer er esit eksestent papes, meeense peanum. and==mment the sneemt of sadneesese mesenal as Ine espe w9e se appropriate haftB5tet of kaoWe

. h 16 eSeBRIBmDS M Chleets of ham SIrface este is detsfResse$. the pertassent levek should be reduand 7:- ' end the emese sesfase eensid tie wipes.

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