ML20236S052
| ML20236S052 | |
| Person / Time | |
|---|---|
| Site: | 05000054, 07000687 |
| Issue date: | 09/24/1996 |
| From: | Condra R, Payne J, Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20236S022 | List: |
| References | |
| CON-FIN-A-9076 ORISE-96-0709, ORISE-96-709, NUDOCS 9807240103 | |
| Download: ML20236S052 (82) | |
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ORISE 96-0709 i
CONFIRMATORY SURVEY OFTHE i
PHASE 2 AREAS OF THE REACTOR BUILDING l
l CINTICHEM, INCORPORATED TUXEDO, NEW YORK Prepared by L
J.L.Payne Environmental Survey and Site Assessment Program Environmental and Health Sciences Division Oak Ridge Institute for Science and Education -
Oak Ridge, TN 37831-0117 l
J Prepared for the U.S.
Wer a gulatory Commission e
E q;i 'n I Office FINAL REPORT SEPTEMBER 1996 i
l This report is based on work performed under an Interagency Agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number DE-AC-05-760R00033 with the U.S. Department of Energy.
Cmtichem lacorporated. September 19.1996 h ussapteparts'cmtichewnedo 002 i
CONFIRMATORY SURVEY OFTHE PHASE 2 AREAS OF THF REACTOR BUILDING
)
CINTICHEM, INCORPORATED TUXEDO, NEW YORK Prepared by:
w I.
Date: 4//<//h J.//. Payne, Fie'id Team Mader Brivironmental Survey and Site Assessment Program 9 3[f6 i
Reviewed by:
Date:
T. J. Vitkie, IIurvey Projects Manager Environmental Suney and Site Assessment Program Reviewed by:
I Date: 92t#/t &
7
R. D. Condra, Technical Resources Mannger j
Environmental Survey and Site Assessment Program Reviewed by:
Mwn ]
Mr>J Date: 9h4/9/j, A. T. Payne, Administrative $ervices Manager Quality Assurance / Health & Safety Manager Em>ironmental Survey and Site Assessment Porgram f!N Reviewed by:
L_
Dste:
s E. W. Abelquist, As'sistant Pgfgram Director Environmental Survey and Site Assessment Program Date: 9I3/M Reviewed by:
~
7 /~
W. L. Beck,'frogram Director Environmental Survey and Site Assessment Program Cmuchern incorporated. September 19.1996 b VesapVeportskmtichemmedo 002
i ACKNOWLEDGMENTS The author would like to acknowledge the significant contributions of the following staff members:
FIELD STAFF E.
W. Abelquist T.
L.
Bright A.
L.
Mashburn i
LABORATORY STAFF f
R.
D.
Condra J.
L.
Cox
)
M.
J.
-Laudeman S.
T.
Shipley CLERICAL STAFF j
D.
K.
Ash T.
S.
Fox K.
E.
Waters I
ILLUSTRATOR
]
T.
D.
Herrera Cauchem incorporated. September 19.1996 h 'essapwepertatmuchetuxedo 002 4
TABLE OF CONTENTS PAGE List of Figures '.....
. ii List of Tables...
.v Abbreviations and Acronyms...............
vi Introduction and Site History...
1
' Site Description..
.. 2.
Objectives..............,...
.3 Document Review.
.3 Procedures...
.4 Findings and Results
.6 Comparison ofResults with Guidelines.
.7 Summary
.9
- References...
. 59 i
Appendices:
1 Appendix A:
Major Instrumentation Appendix B:
Survey and Analytical Procedures j
Appendix C:
Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors i
l i
i l
k h 'essarvepans'cmuchesuxedo 002 Cmuchem Incorporated. September 19,1996 t
a
t LIST OF FIGURES l
PAGE l
l
. FIGURE 1:
Location of the Cintichem Site, Tuxedo, New York 10
- FIGURE 2:
Cintichem, Inc.-Plot Plan.......
11 FIGURE 3:
Reactor Building-Floor Plan..
12
. FIGURE 4:
Reactor Building Floors, Survey Unit 200.1-
. Measurement and Sampling Locations.
13 FIGURE 5:.
Reactor Building Control Room and Office Floors, Survey Unit 200.2-Measurement and Sampling Locations........
14
' FIGURE 6:
Reactor Building Mezzanine Floor, Survey Unit 200.4-Measurement and Sampling Locations..
15 FIGURE 7:
Reactor Building First Floor Stairs, Survey Unit 200.5-Measurement and Sampling Locations.........
16 FIGURE 8:
Reactor Building Floors, Survey Unit 200.8--
Measurement and Sampling Locations
. 17 FIGURE 9:
Pool Sweep Duct Trench, Survey Unit 200.9-
' Measurement and Sampling Locations 18 FIGURE 10: _ North Pool Interior and % East Bioshield Wall, Survey Unit 201.1-Measurement and Sampling Locations.....................
.19 FIGI'RE I1: External Bioshield Walls, Survey Unit 201.2-Measurement and Sampling Locations
.20 FIGURE 12:' _ Bioshield Horizontal Surfaces, Survey Unit 201.3-1 Measurement and Sampling Locations
.. 21 FIGURE 13: Pool and Stall Floor, Survey Unit 201.4-j Measurement and Sampling Locations..
. 22 1
i FIGURE 14: South Pool Interior and % East Bioshield Wall, Survey Unit 201.5-Measurement and Sampling Locations
. 23 FIGURE 15: West Pool Interior Wall, Survey Unit 201.6-l
. Measurement and Sampling Locations.......
. 24 u
FIGURE 16: Internal Bioshield Walls, Survey Unit 201.7-Measurement and Sampling Locations..
.25 i
$k h bsapreports'cmuchewxedo 002 Cmuchem incorporated. September 19.1996
I FIGURE 17: External Pool North Wall, Survey Unit 201.8-Measurement and Sampling Locations 26 FIGURE 18: Reactor Building West Wall, Survey Unit 202.1-Measurement and Sampling Locations...
27 FIGURE 19: Reactor Building West Wall, Survey Unit 202.2-Measurement and Sampling Locations.
28
)
FIGURE 20: Reactor Building South Wall, Survey Units 203.1 and 203.2-Measurement and Sampling Locations 29 FIGURE 21: Reactor Building Nonh Wall, Survey Units 204.1,204.2,204.3 and 204.6-Measurement and Sampling Locations
.30 FIGURE 22: Reactor Building East Wall, Survey Units 205.1,205.2 and 205.3-Measurement and Sampling Locations
.31 FIGURE 23: Reactor Building, Control Room and Offices Ceilings, Survey Unit 206.2-Measurement and Sampling Locations.
32 FIGURE 24: Orifice Pit, Survey Units 208.1 and 208.5-Measurement and Sampling Locations 33 FIGURE 25: Primary Pipe Trench, Survey Units 208.1, 208.2, 208.5, and 208.6-Measurement and Sampling Locations 34 FIGURE 26: Primary Pipe Trench, Survey Units 208.2 and 208.6-Measurement and Sampling Locations.
.35 FIGURE 27: Reactor Building Nonh Wall Below 781' l.5", Survey Unit 208.4-Measurement and Sampling Locations 36 FIGURE 28: Reactor Building First Floor Storage Vr.ults, Survey Units 209.2, 209.6, and 209.9-Measurement and Sampling Locations
.37 FIGURE 29: South Exterior Wall of Control and Instrument Rooms, Survey Unit 210.1-Measurement and Sampling Locations 38 FIGURE 30: Control Room Walls, Survey Unit 210.2-Measurement and Sampling Locations
.39 FIGURE 31: Office Walls, Survey Unit 210.3-Measurement and Sampling Locations 40 FIGURE 32: Instrument Shop Walls, Survey Unit 210.4-Measurement and Sampling Locations
.41 Catichem incorporated. September 19.1996
$kk h Wasapteparts'emtichetuxedo 002
E.-
- FIGURE 33: Mezzanine Walls, Survey Unit 210.5-p
' Measurement and Sampling Locations....
.. 42
. FIGURE 34: Interior / Exterior Count Laboratory Wall, Survey Unit 210.6-Measurement and Sampling Locations.
. 43
' FIGURE 35: Reactor Tunnel Survey Units 211.1,211.4,211.5,211.7 Upper Walls (above 2 m), and 211.8-Measurement and Sampling Locations....
. 44 l
le FIGURE 36: Lower Pump Room, Survey Units 212.1, 212.2 and 212.5-t Measurement and Sampling locations.
.45 I-FIGURE 37: ' Butterfly Valve Room and Valve Room Entrance Walls, Survey Unit 212.4-Measurement and Sampling Locations..
. 46
)
1
- FIGURE 38: Upper Pump Room, Survey Units 212.7 and 212.9-Measurement and Sampling Locations......
.47
' FIGURE 39: Tunnel Airlock, Survey Units 213.1 and 213.2--
l' Measurement and Sampling Locations
.48 l
' FIGURE 40: Reactor Building Stair Stringers, Against Walls, Survey Unit 215.1-l.
Measurement and Sampling Locations.....
.49
. FIGURE 41: Reactor Building-Exposure Rate Measurement Locations..
. 50 i
l:
!=
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l LIST OF TABLES PAGE TABLE 1: Summary of Surfhce Activity Levels.
51
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TABLE 2: Exposure Rates.
58 1
Cmuchem Incorpm sted. September 19,1996 V
h wasapveportstmucheituwdo 002
ABBREVIATIONS AND ACRONYMS pR/h microroentgen per hour ASME American Society of Mechanical Engineers j
cm centimeter 2
cm square centimeter cpm counts per minute D&D decontamination and decommissioning DOE Depanment ofEnergy 2
dpm/100 cm disintegrations per minute /100 square centimeters EML Environmental Measurements Laboratory EPA Emironmental Protection Agency ESSAP Environmental Survey and Site Assessment Program ha hectare m
meter.
2 m
square meter MDC minimum detectable concentration MW megawatts Nal sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education PIC pressurized ionization chamber I
Contichem Incorporated. September 19,1996 v
h bsaptepoets'cinuchetstedo 002
CONFIRMATORY SURVEY OF TIIE f
PHASE 2 AREAS OF TIIE REACTOR BUILDING CINTICHEM, INC.
TUXEDO, NEW YORK I
INTRODUCTION AND SITE HISTORY I
Originally constmeted by the Union Carbide Corporation during the period 1957 to 1960, the Cintichem, Inc. research reactor and radiochemical processing facilities operated for 30 years until their shutdown in 1990. Union Carbide Corporation operated the facility until 1985 when Cintichem, Inc. became the owner under the parent company, hiedi-Physics, a subsidiary of Hoffmann-La Roche.
The hiedi-Physics business, including a portion of the Cintichem operations, was sold in 1990 at which time Cintichem, Inc. became a direct subsidiary of Hoffmann-LaRoche. Cintichem retained ownership of the site. The 1990 shutdown occurred when two basic defects rendered the plant functionally outmoded and it was decided that radiochemical processing be terminated and decommissioning initiated.
Union Carbide operated a reactor housed in Building 1 that achieved criticality in 1961 and commenced routine operation at 5 h1W on a limited duty cycle. Experimental work in neutron activation analysis, radioisotope production, and neutron spectroscopy was also initiated in 1961.
In 1963, the routine production of radioisotopes such as I-131, I-125, hio-99, Au-198, Fe-59, Hg-197, Hg-203, and P-32, was initiated in the reactor and hot labocatory buildings. In 1971, fission products from U-235 were separated for the production ofhio-99. This process eventually allowed for the production ofXe-133 and I-131, and was the predominant operation activity until shutdown in 1990 (Cintichem 1994).
The first of the two defects that led to the operations halt and decommissioning commencement involved a hot cell exhaust duct. The duct, which was constructed of vitreous clay, ran underground from the main filter room to the hot cell filter room and to a header under the hot cell operating floor of Building 2. In late 1989, groundwater contamination was detected in a sump in the northwest corner of the Tl room. Evidence indicated that voids caused by backfilling with large pieces of rock in the surrounding ground of the Tl room allowed air leaking from the hot cell exhaust t
Cmuchem incorporated. September 19.1996 h wasapveportswmuchehedo 002
l duct-upstream of the hot cell filter room-to pass around the Tl room and re-enter the hot cell exhaust duct system somewhere under the hot cell filter room or downstream of it. While investigating the groundwater contamination created from the hot cell exhaust duct leak, two leaks were discovered in the reactor primary coolant system at the base of the north wall of the gamma facility and the southwest corner of the hoid-up tank. Additionally, a third leak was discovered during decommissioning in the south end of the canal where it connects to the reactor pool.
Cintichem is licensed by the Nuclear Regulatory Commission (NRC) under license numbers R-81, Docket No. 50-54, and SNM-693, Docket No.70-687. The facility is also licensed for possession of by-product materials under New York Code Rule 38 by the Agreement States Program, license number 0729-0322. Currently, only decommissioning activities are taking place at the site.
Cintichem has divided the decommissioning project into five phases; the first phase included the exterior areas of Buildings 1 and 2. The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed a confirmatory survey of the Phase I areas during April 1995 (ORISE 1995a).
Cintichem completed the decontamination and final status surveys of the Phase 2 areas in February 1996. Included in the Phase 2 areas are all the interior structural surfaces of the reactor building, the tunnel, and the pump room. At the request of the NRC's Region I Office, ESSAP performed an independent confirmatory radiological survey of the Phase 2 areas at Cintichem, Inc., in Tuxedo, New York.
SITE DESCRIPTION The Cintichem, Inc. site is located off state highway 17A in the extreme southeastern carner of Orange County, New York within the boundary of the Town of Tuxedo. The plant occupies 100 acres (40 hectares) ofland in a mountainous area known as Sterling Forest, approximately 5 kilometers northwest of the village of Tuxedo Park (Figure 1). The operating facilities at the site are located on approximately 12 ha in the eastern portion of the property. The plant portion of the property is bounded to the east by Long Meadow Road and the Indian Kill Reservoir and to the west by Hogback Mountain (Figure 2).
Cmtschem incorporated September 19. Im 2
h Wuapveportscmtscheausedo 002
2 Building 1, the reactor building, has an approximate ground floor area of 600 m. It is constructed ofreinforced concrete set into an excavation in the side of Hogback Mountain. The west side of the reactor building is formed against the excavated bedrock which extends to the full height of the building (approximately 17 m). Building i is adjoined to Building 2, the hot laboratory, at its north end. The scoth side's upper portion extends above grade, while the lower portion is backed by fill and soil. There are ten cylindrical storage ports located in the lower south wall. The east wall has two grour.d floor portals; one to allow access to the tunnel, which opens at a roadway on the lower level of the site, and the second to allow access to the pump room. The reactor and its associated pool were located in the center of the reactor room. The pool dimensions were 6.1 m wide by 12.2 m long by 10.4 m deep. The reactor sat within the stall area of the pool. Two additional floor levels on the north side of Buildirig I housed two small hot cells, a radiochemistry laboratory, counting laboratories, an instrument shop, a restroom, and several offices.
Decontamir.ation activities in the reactor building included the removal of portions of the reactor pool and the stall. A large portion of the ground floor concrete was removed to allow for the removal of embedded piping and trenches. All equipment (lighting fixtures, ductwork, conduit, etc.) was removed from the building, and many of the remaining concrete surfaces had been extensively scabbled. Figure 3 shows the floor plan of the reactor building after remedial activities.
OBJECTIVES The objectives of the confirmatory survey were to provide independent document reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and term' nation survey results.
DOCUMENT REVIEW ESSAP reviewed the licensee's decommissioning plan and radiological survey data (Cintichem 1994).
Procedures and methods used by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness and compliance with guidelines.
Cmucheminenrporated September 19.1996 3
m e, nveron.tmuchemeae 00:
l PROCEDURES During the period ofMay 6 through 9,1996, ESSAP performed a confirmatory survey of the Phase i
2 areas at the Cintichem, Inc. site in Tuxedo, New York. The survey was conducted in accordance l
with a survey plan dated May 1,1996, submitted to and approved by the NRC's Region 1 Oflice (ORISE 1996a). Procedures were in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995b and c). This report summarizes the procedures and results of the suney.
SURVEY PROCEDURES Cintichem divided the areas of concern for this phase into 16 separate areas for purposes of establishing sampling and measurement frequency and pattern. These areas were funher sub-divided into survey units and classified into two categories based on the potential for residual contamination.
The two area categories, referred to as "affected" or " unaffected", are defined as follows: "afTected areas are those areas where radioactive materials were used and stored, where records indicated spills or other unusual occurrences that could have resulted in the spread of contamination, where radioactive materials leaked from systems or structures, and where decontamination work was performed. Areas immediately surrounding or adjacent to these locations were included in this classification because of the potential for inadvertent spread of contamination; unaffected areas were all areas not expected to contain residual radioactivity (Cintichem 1996)." Area classification was determined by plant operating history and the results of radiological characterization and/or measurements made during D&D operations. The reactor building, the tunnel, and the pump room contained a total of 70 affected survey units and 19 unaffected survey units.
Reference Grid ESSAP used the grid system established by the licensee for referencing measurement and sampling locations.
Cmuchem incorporated. 5eptember19,1996 4
h wanapseponstmticheuxedo 002
)
Surface Scans Su. face scans for alpha plus beta and gamma activity were performed on approximately 10 to 20%
l of structural surfaces in affected areas. Four unaffected survey units were selected and alpha plus
)
beta and gamma surface scans were performed on approximately 10% of the area in these units.
Scans were performed using gas proportional and NaI scintillation detectors coupled to ratemeters or ratemeter-scalers with audible indicators. Location.s of elevated direct radiation were marked for further investigation.
S.giface Activity Measurements Initially, construction material specific backgrounds were performed on surfaces at the east end of the tunnel. Direct measurements for total alpha and teral beta activity were performed at 302 locations using gas proportional detectors coupled t.) ratemeter-scalers. A smear sample, for determining removable activity levels, was colle.:ted at each direct measurement location.
Measurement and sampling locations are shown on Figures 4 through 40.
Exposure Rate Measurements Two background exposure rate measurements were performed at the east end of the Tunnel.
Exposure rate measurements were performed at 1 m above the surface at a total of ten locations using a pressurized ionization chamber (PIC). Measurement locations are shown on Figure 41.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were retumed to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Smears were analyzed for gross alpha and gross beta activity using a low background gas proportional counter. Sample analysis was in accordance with the ORISE/ESSAP Laboratory Procedures Manual (ORISE 1995d). Direct measurement and smear data were converted 2
2 to units ofdisintegrations per minute per 100 cm (dpm/100 cm ). Because the radionuclides Fe-55, 11-3, and Ni-63 comprised approximately 75% of the reactor building radionuclides mix, and were not Cmuchem incorporated. September 19. Im 5
m % - nch e meae =
i considered detectable with the field instrumentation used, a scaling factor was applied to the net count rate to account for all of the detectable and non-detectable radionuclides present. Thus, a l
scaling factor of 0.25 was used to correct the net count rate as follows:
I 2
surface activity (dpml100 cm ) =
(
(detector efficiency) (probe areal 100) (0.25) f Exposure rate measurements were reported in units of microroentgens per hour (pR/h). Additional
)
information concerning major instrumentation, and analytical procedures is provided in Appendices A and B. The data generated were compared to the licensee's documentation and to NRC guidelines established for release for unrestricted use, which are provided in Appendix C.
FINDINGS AND RESULTS DOCUMENT REVIEW ESSAP reviewed the licensee's final survey plan and report, including the final status survey data for the Phase 2 areas (ORISE 1996b). The survey instrumentation and procedures used, including measurement and sampling frequencies, were discussed at length, and guidelines for surface contamination and exposure rates were clearly stated. The site description, operational history, and decommissioning activities provided detailed information on the radiological status of the site.
SURVEY RESULTS Surface Scans Surface scans identified one location of elevated beta activity in a firehose compartment on the south wall of the tunnel, and one location of elevated gamma activity at the floor / wall excavation in the l
nonheast corner of the reactor room.
l b
h empwWmuchewedo N2 Cmuchem incorporated. September 19,1m 3
Surface Activity Levels Surface activity levels for total and removable alpha and beta activity are summarized in Table 1.
Total alpha activity levels for all measurement locations ranged from < 32 to 130 dpm/100 cm. Total 2
beta activity levels for all randomly selected measurement locations ranged from <1900 to 12,000 2
' dpm/100 cm. Total beta activity levels for the two locations of elevated surface activity, identified by scans were 16,000 dpm/100 cm' for the tunnel firehose compartment, and 37,000 dpm/100 cm 2
for the reactor room north wall excavation (Figures 35 and 27, respectively). At these locations, a 2
1 m gridblock was established and a 5-point measurement was performed to determine the area 2
2 average activitylevels. The average beta activity within these 1 m areas was 2,600 dpm/100 cm for 2
the tunnel firehose compartment, and 7,700 dpm/100 cm for the reactor room north wall.
All removable activity was less than the minimum detectable concentration of the procedure, which 2
2 was 9 dpm/100 cm for gross alpha and 15 dpm/100 cm for gross beta.
Funosure Rate Measurements Background and reactor building exposure rates are summarized in Table 2. The two background exposure rates, performed at the east end of the tunnel were 13 and 14 pR/h. The reactor building exposure rates, performed in the west end of the tunnel, ',he pump room, and the three floor levels of the reactor room ranged from 12 to 14 pR/h.
COMPARISON OF RESULTS WITH GUIDELINES The primary contaminants of concern for this site are activation and fission products l
(i.e., beta-gamma emitters) from the operation of the research reactor (e.g., H-3, Fe-55, Co-60, Sr-90, and Tc-99). The applicable NRC guidelines for surface activity levels are based on the 7
h WeponhmuchmedM.
Cmuchem incorporated. 5eptember 19. Im
Regulatory Guide 1.86 limits, a's modified by the NRC-approved increased H-3 and Fe-55 surface contamination limits (NRC 1994). The effective beta-gamma surface contamination limits, using the sum-of-the-fractions methodology, are:
Total Activit'y 2
2 14,500 p-y dpm/100 cm, averaged over a 1 m area 2
2
- 43,500 p-y dpm/100 cm, maximum in a 100 cm area Removable Activity 2
1,000 p-y dpm/100 cm
)
The alpha surface contamination limits are based on uranium:
J 1
Total Activity 2
2 5,000 a dpm/100 cm, averaged over a 1 m area 2
2 15,000 a dpm/100 cm, maximum in a 100 cm area Removable activity 2
1,000 a dpm/100 cm Surface scans identified two locations of elevated beta-gamma activity in the Phase 2 areas, one in
[
a firehose compartment in the tunnel, and one on the north wall excavation in the northeast corner.
ohthe reactor room. Surface activity levels, for the firehose compartment and the reactor room north l
l wall, as well as all other total and removable measurements, are within the established guideline limits.
It should be noted that the elevated area of radioactivity was also identified by the licensee's final survey (Cintichem 1996). The licensee performed in situ gamma spectroscopy in this area and determined that the elevated area is due to a concentration of natural radioactivity.
The esposure rate guideline, measured at I m from the surface, is 5 pR/h above background (Cintichem 1996). All exposure rates are within the guideline limit.
Canhcham 1 incorporated. September 19.1996
'8 h Vsuptepartswmuchewuxedo 002
L
SUMMARY
t During the period May 6 through 9,1996, at the request of the NRC's Region I Office, the Environmental Survey and Site Assessment Program of ORISE performed a confirmatory survey at t
j the Cintichem site in Tuxedo, New York. Survey activities included document reviews, surface scans, direct measurements and smear samples, and exposure rate measurements.
l The confirmatory survey identified two locations of elevated direct radiation.
Additional 2
l measurements within a contiguous 1 m area indicated that the elevated activity was isolated and t:te 2
average activity over the 1 m was within the established average guideline limits. The confirmatory survey results are consistent with those obtained by the licensee and support the licensee's conclusion
. that residual activity levels and exposure rates for the interior structural surfaces of the reactor building, including the tunnel and the pump room, satisfy the guidelines for release for unrestricted l
.use.
l l
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1 l 619-033(2) l l I -r t. I 22 1 i 21 4 20
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619-034 (2) 15 1 4 13 12 11 1 0 9 8 7 6 E 4 3 2 1 9 8 3 A e OFFI'CE OFFICE STAIRS B 3 i e' .: #l C REACTOR ) x .. CONTROE" ROOM o 1 j_. ...j..... ;. _..;.. l ..q... i G, l l l E l EL 808'3" F l N A J L MEASUREMENT / SAMPLING Y LOCATIONS g SINGLE-POINT j( FLOOR FEET 0 6 M 0 METERS FIGURE 5: Reactor Building Control Room and Office Floors, Survey Unit 200.2 - Measurement and Sampling Locations }4 h wsaPVePortskmuche'.tunedo 000 Cmuchem Iwwporated September 19,1996
619-035 (2) O N M L K J l H G F E D C B A L t 1 i f 1 4 ..9.. iUP G 2 l... ...i.. LAVATORY ,,,,,j., iCALIB, RATION f le ^ i a _.. h ..t.. .. j... l lNSTRUMENT 4 r -, ...i... .p.._, SHOR... ) i DN l 8 5 1 ..t.. 9 l 6 4 7 EL 798'3" N h J L Y MEASUREMENT / SAMPLING LCCATIONS g SINGLE-POINT k FLOOR FEET 0 6 l M 2 uETEas FIGURE 6: Reactor Building Mezzanine Floor, Survey Unit 200.4 - Measurement and Sampling Locations Cmtw. hem incorporated. September 19, i m 15 6
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619-036(2) i j 1 i LANDING G F E 'el FIRST STEP 3 s 2 e 3 l DOWN 4 l 5 E i OPEN SPACE I i l i N A t J L T MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT k FLOOR FEET 0 6 o METERS l 1 l FIGURE 7: Reactor Building First Floor Stairs, Survey Unit 200.5 - l l Measurement and Sampling Locations Cmuchem Inctwprated. September 19, IN !b h Wn@muche M2
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1 619-015 (3) / l A j
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619-012 (3) l ) 1 2 3 4 3 3 8 J i K; i 1 2 3 4 5 6 7 :8 9 l A '3 r Aj l i i i 8 l B' i l C C. i i .j.. j... .J.,. Df Di i i i l j E p i E! J ...l. l F j '. F i G e i G - +- 4 .... g H H g., _I I i l e l l l l MEASUREMENT / SAMPLING FEET LOCATIONS 0 6 M SINGLE-POINT O 0 2 WALLS METERS FIGURE 11: External Bioshield Walls, Survey Unit 201.2 - Measurement and Sampling Locations CmtichemIncapwated September 19, IN 20 a w pveperi.wmiicheauxcao 002
619-014 (4) ..7... ..7... j i 7l j j i i i i i i ..4. ..t... .4.. 4 e _t j i i . g o i 5. m . 1... e: 4: l ..m_ ^ l STALL. i AREA =
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.. C..,. 0... i i i i g t 3 ~ ...p__ \\+- 6 a 7 % I i ...p...\\ ...} ! POOL! 2 ... i- ...e.-. g j... ...j. ? ...4... ...j. - ..9.., i i e i t i 1 3 I t j i ....a... i MEASUREMENT / SAMPLING FEET LOCATIONS 0 6 SINGLE-POINT o 9 WALLS METERS ) l FIGURE 12: Bioshield Horizontal Surfaces, Survey Unit 201.3 - Measurement and Sampling Locations l 21 h kanapvepons'emuchetuxedo 062 i Cu*etwm incorporated. Septemte19,1996 L________
619-018 (2) r p_ \\ l \\i '/ 0 ! x$%'.. 4 IM ~ r u /i x i ...i....... .. 4... . s...v... \\! E i 1 l j i i s ..+..._.............._...t.... p D l l l l ! 'i +.. ..f..... h...
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r i i 3 i i ..,i. i i i ) ..... +... l /i iN ^ !;'y H H H H / H H h-1 2 3 4 5 6 7 8 9 10 11 12 13 ) I' L N i 1 H 1 MEASUREMENT / SAMPLING h LOCATIONS SINGLE-POINT O N FLOOR O 6 0 METERS j FIGURE 13: Pool and Stall Floor, Survey Unit 201.4 - Measurement and Sampling Locations 22 hw pwegon.w.iiche2uxeao002 Cmuchemincorporated September 19,1996
619-017 (2) \\ A t. 1 [... l.- - 808' 3" ~ r j B BW N-i i i + ..i. i i i. i i C C l i, I i e...!. - 4 h D D i l i STEEL N... .t... ......,4.. 1 -...i.- LINER l E E i l I O j.. - ......p. F7 ) ,,, i F i 3 i i e i i G i l i i i e i e G i ..g ... g.... i i H i i i f.., ,,> +j H ,,,.i, i [ t l i e l i i ~' i 1 l l ,N- .i
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i J t J i l 778*-6" l [ K 4 I 5 6 7 i 8 9 10 i 1 2 3 MEASUREMENT / SAMPLING FEET LOCATIONS 0 3 SINGLE-POINT 1 9 METERS WALLS I i FIGURE 14: South Pool interior and 1/2 East Bioshield Wall, Survey Unit 201.5 - Measurement and Sampling Locations 23 h w ar eroa <mucheu='dooo2 v en, chem i,c,.wa. sepwmba 19, im
619-016 (2) i 7.r ~.r,7 ~ rf- ~ ~ 7.~ T ~ ~ ~ ~ ~ q.- ~ ~.~ ~ - ~ B08'-3" A i .i.... .. i i .. q.. B
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l 1..., .. t.. .i i j C i 1 i 797* 1.5" CANAL FLOOR = & CONST D 0 l JOINT EL. 5 4 i l i e E .q - g i F 7 ...j l r t t G i 4 i .{...... ... y. = l H l i i -.....,...i.. .3...... ...i.. ...i..., ... j... i i j i i I f I 778'-6" 1 2 3 4 5 6 MEASUREMENT / SAMPLING LOCATIONS FEET o 3 SINGLE-POINT O O WALLS METERS FIGURE 15: West Pool Interior Wall, Survey Unit 201.6 - Measurement and Sampling Locations l 24 h wasarveportsemtactewuxedo 002 cmuchem inc p..ted. seriember 19. im l l ___________m_.___._____..__ _._.-___i.
619-013(3) i ) l I SOUTH INTERIOR B10 SHIELD NORTH INTERIOR BIOSHIELD 8 9 10 11 12 A! j .. j ~ ...l... ..h......... .. y.._ ...g f... Bi i ..h,....- C,! j j {.. -..l... . j... ...i Di e i i 1 I.. i i E, i l F i i g -... 4.. ....y..- e, t H ... j....., .........y.... g i i L. ; _. 9_.. 1 g J> i i ......../....... i i K' l l l l MEASUREMENT / SAMPLING LOCATIONS FEET I 0 6 SINGLE-POINT WALLS O METERS FIGURE 16: Internal Bioshield Wolls, Survey Unit 201.7 - Measurement and Sampling Locations I Cmuchem incorporated September 19,1996 2b h wasapWportsicmtichtstuxedo 00 1
619-011 (3) 1 2 3 4 5 6 ! 7 i A i e 8 s i 4 C i l . 7.. ~ g i I i D i m i - STEEL LINER:, E I l i s M. ! n O:\\f..?}&;<!V :.?y *:*:, & T, ) F W.%.,)t:J.*:.*. r.i a. W A.; 4':. i.,? a
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.3..... ~,!.:, yW.;.e T,y;, %.,;,. l, '... ~,.::i 5 k MEASUREMENT / SAMPLING FEET LOCATIONS o 6 E CONCRETE g SINGLE-POINT } WALL METERS i l l RCURE 17: External Pool North Wall. Survey Unit 201.8 - Measurement and Sampling Locations i i L Cmtschem Incorporated. September 19, im 26 n w p',,pon wintica.. ao oo:
7 l 6f9-032 (2) i r EL. 808'3" ..7.._.. ....g S -.. 7. .,. 7... I G i S ! I i l I ....p.. ..... 9 .._......a.- .9.. ...j... -... +... i 9 l l I G i F l i i. j i g -.....p. .7 i-7.- ..7... i O g E i O i i i .... 4. -...d.., .. i. ..d..- d... ..4... i i i i i t i D i e i i ...g... -. j. j... ...j... .. l... i C g t ...j. B 4 ! ) i t i i l .a..- 4 A l l 9 i EL. i i 781'1.5" 1 2 3 4 5 6 7 8 9 ) I MEASUREMENT / SAMPLING FEET o 6 LOCATIONS g SINGLE-POINT METERS FLOOR 1 l I l i FIGURE 18: Reactor Building West Wall, Survey Unit 202.1 Measurement and Sampling Locations - Cmuchemincorpwated.Sepember 19,im 27 h w upon.emnain e m2
619-031 (3)- 1-L _.J OPERAT!NG r C FLOOR L I POOL \\ / Ruiseend B 3 I I ..p. p ...g... ..g.....+... s ...g... y ...j.i.-q...... I l i .i....A......i..,...i... ...i.... . i.. ...>....4....4... .4...
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1 i 'e' le! ' i i #l l B T.! ! ' SURVEY;UN T T202'2" ' ~~~ T 7 A 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 MEASUREMENT / SAMPLING FEET LOCATIONS o 12 M SINGLE-POINT 0 4 4 WAL METERS l l l 1 I FIGURE 19: Reactor Building West Wall, Survey Unit 202.2 - Measurement and Sampling Locations Cmuchem incaporated. September 19. im 28 %,mucne caom l
619-030(2) l l p.. .??_.2.p.2.Q. 24._23.22. 21,_?0.,,J 9 1 Qj 7,,J.6 15,..,14 13.12 11_,10 9,., 8. 7. 6 _ 5. _4 3.. 2..,1. a ..28 4 7..
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iGi og 19i ! ; it! ' . +.. -..+.-+..i...-,... . lgi HH n MEASUREMENT / SAMPLING FEET LOCATIONS 0 12 M g SINGLE-POINT o 4 WALLS METERS FIGURE 20: Reactor Building South Wall, Survey Units 203.1 and 203.2 - Measurement and Sampling Locations l Cmtwhem Incorporated. September 19, IM 2h h W.W Mchewedo M
619-027(2) l l i l l '28!27i 26..25: 24123' 22. 21! 2019 !18 ;17 ;16 l15 ;14,13 ;12 ;11 ;10 l 9, 8 l 7 !. 6, 5 l 4 l 3 I.2_._..,..,. i e .,..,........................,..,..,i 1l n-..a.._......
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<n u u n,* 4 'f r -# > ~t~ 4 6 -,G ////////r/t r x ?o. nu,ue, F ELEV.,, ,u u u u r,. 798'3 .i - ...F. i.. -., E c;;;;j;;;; ...[. - ...;... f.., ..l.... p..... ,'#.: UNIT 204!2 !* l !#! :D ";;;;;';! !e - i 4 a .-+ a 4 .+ .S. .. +. jg,p !o! 5 ST6 } ///F/ 8 / / / /./ .y ^ { "2 0; is i i ; ioi d "' B g j . 2......UdT 2,04',1"i !4 U"4" ~* lA ELEV. - u. r i + 781 1.5" 4,, ;; 7 1 7 ; "; < 7"3 ~f ' " 'f "y ' y " M ';~ ' f ; AA MEASUREMEtJT/ SAMPLING FEET 0 12 LOCATlONS
- NOT PART OF UNIT 204 SINGLE-POINT 0
4 O WALLS METERS l, FIGURE 21: Reac+.or Building North Wall, Survey Units 204.1, 204.2, 204.3 and 204.6 - Measurement and Sarnpling Locations Cmuchem incorporated September 19, tu 30 m wego,..u semw2
l 619-028(3) I 1 2 34 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 S S .n.. l g , i, g p i i 1 i .. 9._ a Q . Q 4 P .P O .+.. ~1.. O ELEV. N N .,...j.............;.....p. ' ? _..].. 824'7 8 M i '....r.....!. M .. 7..., p ....p.. ELEV. L i L ...,......3.. K _. 7.. 7....,.. ..7.--, 7 K J,9i S.. 20,.5. 3. .s,. .6.,..L....>,.......L...i... 4 ...i.. i. ..4. .J i (... jgl 808'3., H i G!,. - 9 ...) 4 p ...p. p ..L.. .g..,..J.. H
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8 4 G ELEv. F 4 F ~' ~~ ~ " ' ~ " ~ "" 798'3" i E,. E Os .o i ...p.. t y <_...,...i 2 ,. - g. C .i # :205.1 : b i C_JLEV. B8i....l.9.,l _ S 767'6.3" ,...t............,!.S. i.... .,i y s .B i .. 7. - ELEV. A 9i .. A 781 '1.5,, g g.-........ _. _ y i .u s.m.s...... ...,,,a ..d... 1 2 34 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 MEASUREMENT / SAMPLING FEET LOCATIONS 0 12 M g SINGLE-PolNT 0 4 WALLS METERS FIGURE 22: Reactor Building East Wall, Survey Units 205.1, 205.2 and 205.3 - Measurement and Sampling Locations Cmtichem %.ted. *
- 31 h wasyreportscmtichchedo 002
l 619-029 (3) r 1 4 13 12 11 ' O 9 8 7 6 5 4 3 2 1 e i i i A .. L. -... _..j _. i _, B u i J .,q ,.. e. f l D I l l E 3 f f 6 C N h JL T MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT h CElUNG FEET o 6 M I O 2 l METERS j FIGURE 23: Reactor Building, Control Room and Offices Ceilings, Survey Unit 206.2 - ( Measurement and Sampling Locations 32 Cmtschem incoquated. September 19, im m w p,,pon.. ucs,
619-006(2) A B C D E F G i 4 1 i l ..J.. -.... UN!T. > 208.1 l 2 i ) UNIT 205.1 3 i G l l_- i ,.s l i UNIT UNIT iUNIT .' UNff UNIT UNIT 4 208.1 208.1 208.1
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.i.. i 9 FLOOR e 5 8 UNIT 208.5 lO 6 ._ 4.. i UNT i' 208.1 7 I i ..i... 8 P UNIT 208.1 9 MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT WALLS AND FLOOR FEET l 0 3 l M 0 METERS FIGURE 24: Orifice Pit, Survey Units 208.1 and 208.5 - I Measurement and Sampling Locations Cmuchem Incorporated September 19. IM 33 aw.pon.,mucseme& 0c2
619-007 (2) r 1 {' i i i \\ \\ \\ \\ ) ... _1... / 1 i /; .. 4... t l '..f.9......_,.... .,.... 9... + g. 2 ,/ i 4. i.
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4 \\. .1.. e..,r...... /' i G O !.. . 4. --. t- - \\l A Y 5 l i l ..j..........q.... j._ y _. _._4. .j... .j... ...p., ..q 6 j .!...a._....... .a. 4 A D E F G H I J K L M Y Z Y \\ ke MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT WALLS AND FLOOR FEET 0 6 M 0 2 METERS FIGURE 25: Primary Pipe Trench, Survey Units 208.1, 208.2, 208.5, and 208.6 - Measurement and Sampling Lo:otions Cintiden Incorporated September 19,1996 M h WasapVeponstatichetuxedo 002
619-009 (2) N O P Q R S T U V ""3 l, i l ' ; NORTH SIDE OF 4 Sojt i i l NORTH WNL f i ~ ...i... ........[. l .".i h. ... i.. ...i.. l + i i ALL WALLS CONCRETE i bi UNIT 208.2 -2i f.. .q. ...f......... .7 -1 i j c l l .q..._ .. 9._ X 2 8 : I I
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3 f I s c s 1. i 4 s 3 a FLOOR _.. 4... - UN{T 208.6- - - 4-5 4 l 8l I I ... 4 i o. '.6 j. ..J... 5 i 8 i i .. l... ..1... _.4.. 6 1 i s i 9 \\r MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT WALLS AND FLOOR FEET 0 6 0 METERS l FIGURE 26: Primary Pipe Trench, Survey Units 208.2 and 208.6 - Measurernent and Sampling Locations Cmuchem incorporated September 19. IM 35 h w.. .utmachewuxeao co2
619-006(3) l l STAIRS i i i i i i i .d... ...i.-. ...i . ],- 3 -- --) ..7.....-.+ > > > > > > >.,-> > > >.> >..> > > > > > >.. > > > > >=, > > >, 7> MEASUREMENT / SAMPLING FEET LOCATIONS O 6 = SINGLE-POINT O ' WALLS AND FLOOR METERS { 7a caio stoex i FIGURE 27: Reactor Building North Wall Below 781'1.5", Survey Unit 208.4 - Measurement and Sampling Locations Cmtichem Incwpormed. September 19.1 M 36 h w p,,n.w.a,em m:
UNIT UNIT UNIT 209.2 209.6 209.9 4 U y 5;__ j _ d i-0 5 10 15 20 25 30 35 40 45 0 1 MEASUREMENT /SAMPUNG LOCATIONS FEET 0 15 g SINGLE-POINT M FLOOR 0 5 g l FIGURE 28: Reactor Building First Floor Storage Vaults, Survey Units 209.2, 209.6 and 209.9 - Measurement and Sampling Locations 37 Cmtschem Inctvierated. September 19. Im h. p ep,i.wmi.chewux ao002 t
619-020(3) 1 2 3 4 5 ELEV. 818'3" l A 1 2 3 4 5 B' 6 7 8 9 10 WINDOW ^ f2 l C 11 13 14 15 i _...[....._-.. l ELEV. i 808'3" e D 16 17 18 19 l 20 ..q.-. 'l l l E 21 22 23 24 ~ 25 4 i F 26 27 28 29 30 ELEV. 798'3" G 31 l 32 33 34 35 i N h MEASUREMENT / SAMPLING Nh LOCATIONS g SINGLE-POINT WALL dj FEET 0 6 6 2 METERS FIGURE 29: South Exterior Wall of Control and instrument Rooms. Survey Unit 210,1 - Measurement and Sampling Locations Cmuchern 1 incorporated. Septemter 19.1996 h h VePorts'cinuchetuxedo 002 P
l 619-022 (2) j I WEST WALL N S Cl l . j.. Bi 8 l ! O f -..... +..........l... '! -..j. l l l i' A! i + i i 5 6 5 4 3 2 1- / I- . CONTROL. ROOM _N SOUTH WALL - WEST WALL E W S N r i i ~ C i i t ..._i.. i i _..7..,..,..... 7 j e i a 3. ,... - l i t 1 1 A l 9 le l 16 15 14 13 12 11 10 9 8 7 l l l l I li- - MEASUREMENT / SAMPLING FEET LOCATIONS 0 6 SINGLE-POINT g WALL FIGURE 30: Control Room Walls, Survey Unit 210.2 - Measurement and. Sampling Locations Cmtichem incorparmed. September 19, lm 39 h w#wmehee =2
619-023(2) INTERIOR EAST SOUTH SOUTH WALL WALL WALL C d ... h... _ 9 B -?....... . 4._ j l OFFICE 11/ i i e i A i = 19' 20 21 22 1 2 3 4' 5 6 7 ~ / OFFICE il OFFICE I OFFICE I l EXTERIOR l SOUTH SOUTH EAST p WALL WALL WALL l i C j CONTROL' B ROOM h- = N I A = 8 9 10 11 12 13 14 15 16 17 18 OFFICE II OFFICE I j i i MEASUREMENT / SAMPLING LOCATIONS FEET 0 6 g SINGLE-POINT M WALL 0 2 METERS FIGURE 31: Office Walls Survey Unit 210.3 - Measurement and Sampling Locations Cechem incorparsted. September 19. Im 40 m mp,eg..meu ac
l l 619-Old ',2) 1 l WEST l WALL l l C i* B
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...t.. 4 i j 9 l i i A i-LAVATORY 6 5 4 3 2 1 i l N S l l ll1 lllllllllll,, l INST. RM. j \\ SOUTH WEST i s \\ WALL WALL 5 i h2 [ O N i lC i .j.. - ..p. _...t.._ .9._ .q t i i e is L,...._ . j. ..4...- 'e' e! lA ... L. . l.. _ ...L, 17 16 15 14 13 12 11 10 9 8 7 E N MEASUREMENT / SAMPLING FEET LOCATIONS 0 6 M SINGLE-POINT - 0 2 S WALL METERS l 1 FIGURE 32: Instrument Shop Wolls, Survey Unit 210.4 - Measurement and Sampling Locations t 41 h wsapveports'emtichetuxedo 002 c.tchemincer-ted september 19,1996
619-023(2) / EAST WALL c j... ...j...... { i 8 i .. s... ...}... l 9 i A . 2... } 1 2 3 4 l N S EAST SOUTH EAST WALL WALL WALL JL 7C ~ y m t l ~i c CALIBRATION s L 4.... L_ / I e e g g i. _. 4.. i jA M ... ~ _ / 13 14 15 16 17 18 19 20 21 22 23 N S E W S N i l'\\ SOUTH WEST WALL WALL c-L 1 c INST. RM. B 4 l 0 j A 5 6 7 8 9 10 11 12 W N MEASUREMENT / SAMPLING FEET LOCATIONS 0 6 SINGLE-POINT O o WALL METERS I 1 1 FIGURE 33: Mezzonine Walls, Survey Unit 210.5 - Measurement and Sampling Locations Cmtschem Incorporated - September 19,1996 h WasapreportsWmtscheauxedo 002
619-021 (2) { l J WEST SIDE OF CEILING EAST SIDE OF WEST WALL ELEV. WEST WALL 797"9.5" j i I ,l E E i i i t._ ....;.......t. i l ...........L. i 9. D D i o { ........ ~. i l C C I i i i i ,9 B B l 0 i i i _,........i.... f l A A O l i. h FLOOR 6 5 4 3 2 1 ELEV. 1 2 3 4 5 781'1.5" l N S S l l l l MEASUREMENT /SAMPUNG FEU LOCATIONS o 6 g SINGLE-POlNT 0 WALL METERS FIGURE 34:. interior / Exterior Count Laboratory Wall, Survey Unit 210.6 - Measurement and Sampling Locations ' Cmuchemincorporated. September 19,1996 h wusapWportsWnucheuuxedo 002 w-____--______-__
619-002 (3) NORTH WALL EAST WALL UNIT 211.5 UNIT 211.6 iG: .t,.o i ..9....,... 7 _..7... . i 7! C je -.7.... , 7 se: 9: i B
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i ... p _....'.......q.- .. 4 i# y i'i 7 i i'i i A' i i i i'i 1 2 3 4 6 7 8 9101112131415161718192021222324252627 AIR LOCK I MEASUREMENT / SAMPLING LOCATIONS FEET 0 12 g SINGLE-POINT WALLS AND FLOOR 4 METERS GRID BLOCK FIGURE 35: Reactor Tunnel Survey Units 211.1, 211.4, 211.5, 211.7 Upper Walls (above 2m), and 211.8 - Measurement and Sampling Locations Cmuchem incorporated. September 19,1996 44 h wsup' reports'smuchemmedo 002 (
619-004 (2)- i l ) EAST WALL SOUTH WALL WEST WALL NORTH WALL .....h....,.. ......i...,-, '...h...' d....1... .4.. ...1....3.....;. !G: ...j.4... 4.. .... 0.. :: B ,G.,!.,, 3 4 ....p..4. 6
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619-005(2) WALLS SOUTH NORTH UNIT 212.4 EAST EAST SOUTH NORTH WEST 1r O.... I O, c.....e.., . i. . ;.... i.. ;.. s .O O I .i....$... 7...I... g... !.... 4 9......... y I s i 121314CD14 D E FG1415G F E D C 1514131211 B A a G...,.... \\ .. 9.. 9... g.. .,..4...
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t F p j g 151413121110 9 8 7 6 " 4 3 2 1 FLOOR UNIT 212.7 ) 1 N s JL MEASUREMENT / SAMPLING LOCATIONS g SINGLE-POINT b WALLS AND FLOOR 1 t FEET 0 12 1-0 METERS FIGURE' 38: Upper Pump Room Survey Units 212.7 and 212.9 - Measurement and Sampling Locations 47 h wsap' epons'emtschetuxedo 002 Cmtachemincorporated September 19. tm v L _ _ _ _ _ _ _ _ _ _ - - -____--- _ a
l 619-026(2) l l l NORTH EAST SOUTH WEST i WALL WALL WALL WALL j i { j 1 C i-7 7 i 1 e, e B + i l . +... . i.. _. 9.. i ) i i l 8 i [ fA 1 2 3 4 5 6 7 8 9 10 11 12 13 UNIT 213.2 1 ] FLOOR i e> l c 1 e B 1 2 3 4 5 ) WEST EAST UNIT 213.1 i l i i MEASUREMENT / SAMPLING FEET LOCATIONS o 6 g SINGLE-P0lNT 0 2 FLOOR AND WALLS METERS i FIGURE 39: Tunnel Airlock, Survey Units 213.1 and 213.2 - Measurement and Sampling Locations Cmt chem incorporated. September 19.1996 48 h 'wssapveports'emtiche' tuxedo 002
619-010 (1) THIRD FLOOR j-LOOKING WEST I D LOOKING EAST LOOKING EAST e FIRST FLOOR \\ MEASUREMENT /SAMPUNG LOCATIONS NOT TO SCALE g SINGLE-POINT WALLS AND FLOOR FIGURE 40: Reactor Building Stair Stringers, Against Walls, Survey Unit 215.1 - Measurement and Sampling Locations c=>a i.co,por.i.a. sept.ms., io. im 49 w,, w w. e -.& oo2
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I '. 4 5 ' '.5". .' ', '. 5 PUMP p N / _J U U U U U La I N 7 SOIL r (UNIT 200.6) Il MEASUREMENT LOCATIONS ORIGINAL CONCRETE JL $(EXPOSURE RATE (UNIT 200.9) T CONCRETE SUB-FLOOR (UNIT 200.8) j BEDROCK b j (UNIT 200.9) NOT TO SCALE MGURE 41: Recctor Building - Exposure Rate Measurement Locations Cauchem incorporated. September 19. lu 50 h w p.epo,i,..ucheauxeao 002
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l j l j jl llIl 1l !I ll! ) 2 a e m 5 5 5 5 5 5 5 5 5 t f e l 1 l 1 1 1 l 1 l l c ob B t eai0 gvv0 n oi 1 t amc/ Ream l p a R d h 9 9 9 9 9 9< 9 9 9 ( p lA ega a t re e v B A ) 2 m k S c c L o 0 l E 0 B l V 1 / d a E m r h i L p G p Y d lA ( T y .K I ) S t d V A i R v E C I e i 0 0 0 O 0 0 0 0 0 t I u UR N c 0 0 Y A 2, 3, 2, 4, 2, I i AA s 2 2 2 t E2MW l t 0 3 0 0 0 3 n a n a 0 o 0 o 0 0 o t E o e te 9, o 9, o o 9, 9, C CEE t t ASH N T m B t t t 0 ( 0 l l 1 1 f e 0 0 0 0 0 FAC 1 E RHI O o r 0 0 0 u 9, 2, 9, 9, 9, L UP TD e s 2 l 1 l 1 g a NE n e C SRI X a M l A FOCI R T OF T i e 0 0 0 0 0 l 7 7 7 7 7 g a Y n h 0 0 0 0 R S p 7 o o 7 o o o 7 7 i t t t t t A lA 1 0 0 8 0 M 4 5 5 5 5 MU L L L L L S A A f " L o "', W W A r H 2 W e " H 6 9 b 5 4 5 5 2 3 m5 T T T 1 u8 U R S N' O O A M S N E G G G N N N er I I I D 2 2 2 uo D 0 0 D 1 1 1 1 gN L 2 2 L 2 2 2 2 L 2 2 2 .i I I I F U U U B B B R R R / n O O O .oN T 1 2 T 1 2 3 6 T I. 2 3 o i a C 3 3 C 4 4 4 4 C 5 5 5 t 0 0 0 0 0 0 0 0 0 c A 2 2 A 2 2 2 2 A 2 2 2 o"U E E E L R R R w" f [l8 E f5 3
e m e 1 1 1 l 1 l 1 lb yc B t ai0 v v0 i ot 1c/ Amp a R d h ( 9 9 9 9 9 9 9 p lA eg a a 00 7, r t e e v B 7 A ) 2 m k S c c L o 0 l E 0 B 1 V / d a E m r h 0 i L p G p 5< Y d lA ( T y ) S K I t d V A i R v u TE C i 0 I e O tc 0 n CR N Y A 0, I i AA s 7 t E2MW l t 0 0 0 0 0 0 n a 3 n a 0 0 0 0 0 0 o t E o e te 9, 2, 2, 2, 2, o 0, C CEE N T m B t 2 2 2 2 S 2 I ( ASI l 0 T f e S 0 F A.C O o G 5 2, 1 r L u E RHI L UP TD e s N U I 2 g a I A NE n e L 'I V C SRI X a M A FOC U R E I 8 7 E T OF T e C 0 5 06 G l 5 W g a 0 7 Y n h E 7 4 o O o A 2 1 R 5 o S p C 3 o 7 t i R 3 t t L 0 O A l I t 1 A F 9 4 E 5 4 M F 4 B T 4 M O S L R U D L O t S f n N A A O o e s mn W L r o M H F e e i b rt 5 4 1 5 5 4 1 ua O T T ms c u a o O R S O R NeL R I M I I L C N F O N G G R E 6 N N T R 2 I I 6 D 7 D 8 o N 3 4 4 T 2 2 2 2 L 2 L 2
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e m 5 5 5 5 5 5 t f e l l 1 l l l l c ob B e a gv n o t / a m m Re p a R d h 9 9 9 9 9 9 ( p lA e g a a r t e e v B A ) 2 m k S c c L o 0 l E 0 B V 1 / d a E m r h i L p G p Y d lA ( T y S K I t ) V A .R v i d u TE C i 0 I e 0 O 0 0 0 0 t M 0 CRN Y A c 0 0 0 2, 4, n I O 3, 0, 5, 2 AA i s t 2MW 2 l 0 2 t n 3 3 n a O 0 o o a o E t E o e te R 0, o o o C CEE t t ASH N T m B T 0 t t t 2 0 0 ( f e 0 0 0 0 FAC 0 0 0 S I r N 9, 9, 0, 9, L 9, E RHI O o u E TD e s l l L 2 L UP g a M 1 1 NE n e A B SRI X a M U W A FOC U R R T OF T e 0 0 T 7 Y 7 lg a S R Y n h N 8 0 0 0 R S p 5 7 7 7 o O o i I t t T A lA L 0 0 5 A 5 M O R M R O U T B t N S f n A o e O L r m C e e T b r F 4 5 5 S 5 7 N 4 u ms O L U ua L S L O Ne L L A C M A L W A R W P S O W O L R I L R H 2 O 9 M 0 3 4 1 A E O S 3 S 3 2 3 3 3 N IR L T W T O X E L N E E T R A E N / X L W M R I / E O U N O n Y H 1 R 2 E 3 R 4 A 5 6 o I 0 T 0 C 0 0 Z 0 R 0 i ta T T E 1 I 1 Z 1 1 1 1 N c " U 2 2 F 2 S 2 2 o8 E T 2 L O O F N M N S C O I I f( [1s ) f#}
e m 5 5 5 5 5 5 5 5 t f e l l 1 l l l l l l ob yc B t e ai0 gvv0 i n ot 1 mc/ aReam p R a d h ( 9 9 9 9 9 9 9 9 p l A ega a 00 6, r te ev B 2 A ) 2 m k S c c L o 0 l E 0 B V 1 / d a E m r h 4 i L p G p 3< Y d l A ( T y ) S K I t d V A .R v i u TE C e I i O 0 t CR N c 0 0 0 Y A 6 0 0 0, 9, 8, I i AA t s E2M,W l n a 0 0 0 0 6 8 0 tn a 0 0 0 0 1 o o o 0 t E C CEE o e te 9, 9, 9, o 2, 3, t t N T m B t l ( AS 2 0 0 5 l 1 1 l f e 0 FAC O o 0 0 1 r 0 u 9, 2, 2, E RHI TD e s 2 2 L UP g a 1 NE n e E SRI X a M A FOC U R T OF T e 0 0 0 l 7 3 3 g a Y n 1 1 R h 0 0 0 0 S p 7 7 7 o 5 o o A i A t t t N lA 4 M 1 1 3 4 4 M U I S f " s o ** n r o e 'r 0 3 i b t 5 5 1 7 9 5 " a m5 c 1 1 M u 8 o N'L O OR M E e L O V r E O uo 5 5 5 5 5 6 6 L 7 g N 3 3 3 3 3 R 3 3 A 3 .i N F N P V UT M Y U L R / P F n yo O e R R o vN T 5 7 8 4 1 2 5 E 4 i E t 1 C W . 2 2 T 2 1 1 1 1 1 a r t 21 1 1 1 1 1 c ui 1 1 2 2 T 2 oS n A 2 2 2 2 2 1 L U E O 2 U R L B nBI f E.{153.y mcn fikiea
ob B t e ai0 gvv0 i n ot 1 mc/ aReamp a R d h ( 9 9 9 9 9 p lA ega a t re e v B A ) 2 m k S c c L o 0 l E 0 B V 1 / d a E m r h i L p G p Y d lA ( T y ) S K I t d V i A .R v u T E C e I i O t n C RN c Y A I i A A t s E2MW la 0 0 0 0 0 n tn a 0 0 0 0 0 it e t E o e te 2, 2, 2, 9, 0, n C CEE N T m B 2 2 2 2 u I AS ( 1 I f e y FAC r I E R HI O o . ve u e TD e s L U P n r g a u NE n e il s B S RI X a e M i h A F OC U R d is T OF T e 0 ugt l 1 3 g a 7 n Y ei 1 n h S p o o 0 0 2 g R i d t 5 ? 3 a t e A S r l 1 e m A 1 M 4 4 R v r a o E f M d r G e e U N e p t S .c f n I xt oe R c o e n n r m T I t e S ,o y b 5 t 7 2 4 3 mni ms R u 1 v edi I u a hi t cd c Ne A it a M T t n n a S i eh M G Cmp ye la e N b r r O K I ul a uo O 8 8 C 9 9 D 0 d s t e a o g.i N R O 3 3 L 4 d et 3 3 I i mr F L v P U o R oef M B rlpgs I U A R si n t n / n P L O it s e o m o 7 9 E 1 2 T n s 1 R i a E N 3 3 C 5. un e t 2 2 a r ye u 1 1 1 1 1 c P 2 2 N 2 2 A 2 vMa e s o L U P U E r e U T R u - M S '- n[IfL f 0E f 1li$ba t
TABLE 2 EXPOSURE RATES FOR PIIASE 2 AREAS CINTICIIEM, INC. TUXEDO, NEW YORK e= a Location /Surves 0: it No." Exposure Rate (pR/h) at I m Above Surface TUNNEL Location 1 Background-211.1 14 Location 2 Background-211.1 13 Location 3-211.1 13 PUMP ROOM Location 4-212.07 12 Location 5-212.01 14 REACTOR BUILDING , Location 6-200.8 12 Location 7-200.8 13 Location 10 - 200.8 12 STALL FLOOR / POOL Location 8-201.4 13 Location 9-201.4 13 SECOND FLOOR Location Il-200.4 12 TIIIRD FLOOR i Location 12 - 200.2 12 ' Refer to Figure 41 l Cmuchem Incorporated - September !9. IM 58 m w p,mmaemcoo e
l. REFERENCES Cintichem, Inc. Final Status Survey Plan and Report, Cintichem, Inc., Tuxedo, New York; December 1994. i . Cintichem, Inc. Final Status Survey Plan ans' Report, Sections 7 and 8, Cintichem, Inc., Tuxedo, New York; March 1996. ' Oak Ridge Institute for Science and Education (ORISE). Confirmatory Survey of the Exterior Areas - of Buildings 1 and 2, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; May 1995a. Oak Ridge Institute for Science and Education. Survey Procedures Manual for the . Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; April 30,1995b. Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 7. Oak Ridge, Tennessee; January 31,1995c. - Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, TN; January 31,1995d. Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for the Phase 2 Areas, Cintichem, Inc., Tuxedo, New York (Docket No. 70-687 and RFTA No. 96-17). Oak Ridge, TN; May 1,1996a. Oak Ridge Institute for Science and Education. Comments on the Final Status Survey Plan and Report for the Cintichem, Inc. Decommissioning Project, Reactor Building Areas, Tuxedo, New ! York. Oak Ridge, Tennessee; April 1996b. U.S. Nuclear Regulatory Commission (NRC). Manual For Conducting Radiological Surveys in Support ofLicense Termination (Draft). NUREG/CR-5849. Washington, DC; June 1992. U.S. Nuclear Regulatory Commission. Letter from T. S. Michaels, NRC/HQ to J. McGovern, Cintichem, Modification ofRegulatory Guide (RG) 1.86 Surface Contamination Limits for Iron-55 (Fe-55) and Tritium (H-3). Washington, DC; October 3,1994. Cauchem locarparesed. Sepeernber 19. Im 59 mw pwmua.m.w2 s
l 1 ) APPENDIX A MAJOR INSTRUMENTATION 4 Canuchem Incorporated. September 19,1996 h hapweports'cmuchetuxedo 002
APPENDIX A MAJOR INSTRUMENTATION The display of a spec 3'ic product is not to be construed as an endorsement of the product or its manufacturer by the author or their employers. DIRECT RADIATION MEASUREMEE Instruments Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NM) Ludlum Floor Monitor Model 239-1 (Ludlum Measurements, Inc., Sweetwater, TX) Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) Detectors Ludlum Gas Proportional Detector Model 43-37 2 Effective Area,550 cm (Ludlum Measurements, Inc., Sweetwater, TX) Ludlum Gas Proportional Detector Model 43-68 2 Effective Area,126 cm. (Ludlum Measurements, Inc., Sweetwater, TA7 Reuter-Stokes Pressurized Ion Chamber l Model RSS-Ill I (Reuter-Stokes, Cleveland, OH) l A-1 aw powmisaa-a.m2 Cmtschem Incorporated. September 19, IM l
Victorcen Nal Scintillation Detector l Model 489-55 l . 3.2 cm x 3.8 cm Crystal l (Victoreen, Cleveland, OH) 3 LABORATORY ANALYTICAL INSTRUMENTATION ' Low Background Gas Proportional Counter J l Model LB-5110-W - (Oxford, Oak Ridge, TN) - I I l l t f l i l I 1 { I i \\ Canichem incorporated. September 19.1M A-2 m we..,a.wmiie==w2
) i l APPENDIX B SURVEY AND ANALYTICAL PROCEDURES Cinhchem incorporated. September 19, im h Wasartepartsemucheauxedo 002
c APPENDIX B SURVEY' AND ANALYTICAL PROCEDURES SURVEY PROCEDURES' L Sudace Scans Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum-nominally about I cm. Large surface area, gas proponional detectors were used to scan the floors and lower walls. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinations of detectors and instruments used for the scans were: Alpha-Beta -- gas proponional detector with ratemeter-scaler Gamma . Nal scintillation detector with ratemeter Surface Activity Measurements Measurements of total alpha and total beta activity levels were performed using gas proportional detectors with ratemeter-scalers. Alpha activity contributions to beta measurements made with gas proportional detectors were eliminated by using suitable absorber thicknesses to attenuate alpha radiation. Count rates (cpm), which were integrated over 1 minute in a static position, were converted to 2 activity levels (dpm/100 cm ) by dividing the net rate by the 4x efficiency and correcting for the i active area of the detector. The alpha activity background count rate for the gas proponional i detectors was 3 and 6 cpm, on concrete and painted concrete surfaces, respectively. The alpha efficiency factors ranged from 0.17 to 0.18 for the gas proportional detectors calibrated to Th-230. The beta activity background count rate for the gas proportional detectors was 475 and 385 cpm, on cua-i-,,-.4. s.n.ms., i,. im B-I w,,,,,, e m
concrete and paint'ed concrete surfaces, respectively. The beta efficiency factor was 0.15 for the gas proportional detectors calibrated to Tc-99. The effective probe area for the gas proportional l detectors is 126 cm?. l l Removable Activity Measurements i. l Removable activity levels were determined using numbered filter paper disks,47 mm in diameter. 2 Moderate pressure was applied to the smear and approximately 100 cm of the surface was wiped. - Smears were placed in labeled envelopes with the location and other pertinent information recorded. l Exposure Rate Measurements Measurements of gamma exposure rates were performed using a pressurized ionization chamber (PIC) positioned one meter above the surface and allowed to stabilize. ANALYTICAL PROCEDURES Gross Alphn/Bila - Smears were counted on a low background gas proportional system for gross alpha, and gross beta activity. i UNCERTAINTIES AND DETECTION LIMITS The uncertainties associated with the analytical data presented in the tables of this report represent the 95% confidence level for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. Additional uncertainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this l i report. B-2 hvasapvepons\\cmtiche\\ tuxedo 002 cantichem incorpmied. september u. s u I i
Detection linuts, referred to as minimum detectable concentration (MDC), were based on 2.71 plus 4.65 times the standard deviation of the background count [2.71 + (4.65/BKG)]. When the activity was determined to be less than the AfDC of the measurement procedure, the result was reported as less than MDC Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instmment to instmment. CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to NIST, when such standards / sources were available. In cases where they were not available, standards of an industry recognized organization were used. Calibration ofpressurized ionization chambers was performed by the manufacturer. Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program: Survey Procedures Manual, Revision 9 (April 1995) Laboratory Procedures hianual, Revision 9 (January 1995) Quality Assurance hianual, Revision 7 (January 1995) The procedures contained in these manuals were developed to meet the requirements of DOE Order 5700.6C and AShfE NQA-1 for Quality Assurance and contain measures to assess processes during their performance. Quality control procedures include: l Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations. Participation in EPA and EhfL laboratory Quality Assurance Programs. Training and certification of all individuals performing procedures. l Periodic internal and external audits. Canuchem incorporated. Septemher 19, im B-3 3% panouchemeanoo,
l APPENDIX C i REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS l { Cmtechem incorporated. Sepember19,1996 h weapvervtsstntichemmedo 002 l L_ __
APPENDLX C REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS I I l cmua m incorp-i.a. september 19,1996 h haphpons'cmtscheunedo 002 l
U.S. ATCMIC ENERGY COMMISSION Juns 1974 REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. INTRODUCTION important to the safety of reactor operation is no longer required. Once this possession-only license is issued, Section 50.51, ' Duration of license, renewal," of 10 reactor operation is not permitted. Other activities from CFR Part 50, " Licensing of Production and Utilization the reactor and placing it in storage (either onsite or Facilities," requires that each license to operate a offsite) may be continued. 1 pnxluction and utilization facility be issued for a specified duration. Upon expiration of the specified period, the A licensee having a possession-only license must l license may be either renewed or terminated by the retain, with the Part 50 license, authorization for special j Commission. Section 50.82, " Applications for nuclear material (10 CFR Part, 70, "Special Nuclear 1 termination of licenses," specifies the requirements that Material"), byproduct material (10 CFR Part 30, " Rules must be satisfied to terminate an operating license, of General Applicability to Licensing of Byproduct including the requirement that the dismantlement of the Material"), and source material (10 CFR Part 40, facility and disposal of the component parts not be " Licensing of Source Material *), until the fuel, inimical to the common defense and security or to the radioactive components, and sources are removed from I health and safety of the public. This guide describes the facility. Appropriate administrative controls and methods and procedures considered acceptable by the facility requirements are imposed by the Part 50 license Regulatory staff for the termination of operating licenses and the technical specifications to assure that proper for ranclear reactors. The advisory Committee on Reactor surveillance is performed and that the reactor facility is Safeguants has been consuhed concerning this guide and maintained in a safe condition and not operated. has concurred in the regulatory position. A possession-only license pennits various options arxl B. DISCUSSION procedures for decommissioning, such as mothballing, entombment, or dismantling. The requirements imposed When a licensee decides to terndnate his nuclear depend on the option selected. reactor operating license, he may, as a first step in the process, request that his operating Ecense be amended to Section 50.82 provides that the licensee may dismantle restrict him to possess but not operate the facility. The and dispose of the wormut parts of a nuclear reactor in advantage to the licensee of converting to such a accordance with existing regulations. For research possession-only license is reduced surveillance reactors and critical facilities, this has usually meant the requirements in that periodic surveillance of equipment disassembly of a reactor and its shipment orpnization for USAEC REGULATORY GUIDES g,,,,, I Regulatory raades are issued to describe and mee avdeble to the pubhc econd u W n Aumm Enwey commeen. Wencon. ac. 20s40 AH s He of R gul y sunderde. Commente end sup0.st'ene for memede ureptable u W AfC teguistey staff of amplemenuno pecdic pFlo P'ovmenu in mese owdee a enuureced and should be em a W s'*ecmury of W Cannmon. U.s. Atomic Energy commmeon, Weenmoton, of ite cc emes on's reguiet.one, to onomete techmouse used by the staff m evadusung speedes probleme er postulated occidas. or to provide swdence to e phcene. Rentsetery Guides are not substitutes fee regutst.ons and comphence D.C. 2W6. Anmim chel Mhc Proceedmos Steff. wah them a ret reeupted. Methods and solutaans different from those set out m em stedse wdl be acceptable if they provide e base for the fmdence roeissete to The Ou' des are mound m the following ten breed evisions. tte eseuence er centmuence of a permet er iscenes by the Commemon, p
- 2. Res. orch and int Reectwe
- 7. Transporteiian rimiehod owdeo we em mveed pemeedy. as appropnme, to accommedme 8'""*""d"""**'***'**
80**'*"*'H**h somments and to reneet emw mformmion or esperance.
- 4. Enverenments and ssung
- 9. Amstrust Revow
- s. umense end Pian Protecten io.c.enes Note: Section electronicelle reproduced from photocopy.
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i further use. The sita from which e reactor has been
- c. Any proposed changra to the technicel removed must be decontaminated, as necessary, and specifications that reflect the possession-only facility inspected by the Commission to determine whether status and the necessary disassembly / retirement unrestricted access can be approved. In the case of activities to be performed.
nuclear power reactors, dismantling has usually been accomplist ed by shipping fuel offsite, making the reactor
- d. A safety analysis of both the Mivities to be inoperable, and disposing of some of the radioactive accomplished and the proposed changes to the components.
technical specifications. Radior tive couWs may be either shipped off-site
- e. An inventory of activated materials and their for burial at an authorized burial ground or secured on the location in the facility, site. Those radioactive materials remaining on the site must be isolated from the public by physical barriers or
- 2. ALTERNATIVES FOR REACTOR RETIREMENT other means to prevent public access to hazardous levels of radiation. Surveillance is necessary to assure the long Four alternatives for retirement of nuclear reactor tenn irregrity of the barriers. The amount of surveillance facilities are considered acceptable by the Regulatory required depends upon (1) the potential hazard to the staff. These are:
health and safety of the public from radioactive material remaining on the site and (2) the integrity of the physical
- a. Mothballing. Mothballing of a nuclear reactor barriers. Before areas may be released for unrestricted facility consists -1 putting the facility in a state of use, they must have been decontaminated or the protective storage. In general, the facility may be left radioactivity must have decayed to less than prescribed intact excep that all fuel assemblies and the limits (Table 1),
radioactive fluids and waste should be removed from the site. Adequate radiation monitoring, The hazard associated with the returnwl facility is environmental surveillance, and appropriate security evaluated by considering ~the amount and type of procedures should be established under a remaining contammation, the degree of confinement of the possession-only license to ensure that the health and remaining radioactive materials, the physical security safety of the public is not endangered. provided by the confinement, the susceptibility to release of radiation as a result of natural phenomena, and the
- b. In-Place Entombment. In-place entombment duration of required surveillance.
consists of sealing all the remaining highly radioactive or contanunated components (e.g., the pressure vessel C. REGULATORY POSITION and reactor internals) within a structure integral with the biological shield after having all fuel assemblies,
- 1. APPLICATION FOR A LICENSE TO POSSESS radioactive fluids and wastes, and certain selected BUT NOT OPERATE (POSSESSION-ONLY components shipped offsite. The structure should LICENSE) provide integrity over the period of time in which significant quantities (greater than Table 1 levels) of A request to amend an ~ operating license to a radioactivity remain with the material in the posseesion<mly license should be made to the Director of entombment.
An appropriate and continuing Licensing, U.S. Atomic Energy Comndssion, rveih se program should be established under a Washington, D.C. 20545. The request should include possession-only license. the following information:
- c. Removal of Radioactive.
Components and l
- a. A description of the current 6tatus of the facihty.
Dismantling. All fuel assemblies, radioactive fluids and waste, arxl other materials having activities above
- b. A descripion of measures that will be taken to accepted unrestricted activity levels (Table 1) should prevent criticality or reactivity changes and to be removed from the site. 'Ihe facility owner may minimize releases of radioactivity from the facility.
then have unrestricted use of the site with no requirement for a license. If the facility owner so Note: Section electronicaHy reproduced from photocopy. C-2
I desires, the remainder of the reactor f:cility may be birritrs in the freility. Sunpling should be done tiong dismantled and all vestiges removed and disposed of. the most probable path by which radioactive material such as that stored in the inner containment regions could be
- d. Convenion to a New Nuclem System or a Fossil transported to the outer regions of the facility arul Fuel System. This alternative, which applies only to ultimately to the environs.
nuclear power plants, utilizes the existing turbine system with a new steam supply system, The original d. An environmental radiation survey should be reclear steam supply system shoukt be separated from performed at least semiannually to verify that no j the electric generating system and disposcd of in significant amounts of radiation have been released to the i accordance with one of the previous three retirement environment from the facility. Samples such as soil, alternatives. vegetation, and water shouki be taken at locations for which statistical data has been established during reactor
- 3. SURVEILLANCE AND SECURITY FOR THE operations.
RETIREMENT ALTERNATIVES WHOSE FINAL ) STATUS REQUIRES A POSSESSION-ONLY e. A site representative shoukt be designated to be LICENSE responsible for controlling authorized access into and movement within the facility. ) A facility which has been licensed under a j _ possession-only license may contain a significant amount
- f. Administrative procedures should be established for of radioactivity in the form of activated and contaminated the notification and reporting of abnormal occurrences 1
hardware and structural materials. Surveillance and such as (1) the entrance of an unauthorized person or commensurate security shouki be provided to assure that persons into the facility and (2) a significant change in the the public health and safety are not erulangered. radiation or contamination levels in the facility or the
- a. Physical security to prevent inadvertent exposure offsite environment.
of personnel shouki be provided by multiple locked barriers. The presence of these barriers shouki make it
- g. The following reports shoukt be made:
extremely difficult for an unauthorized person to gain cccess to areas where radiation or contamination levels (1) An annual report to the Director of Licensing, exceed those specified in Regulatory Position C.4. To U.S. Atomic Energy Commission Washington, D.C. prevent inadvertent exposure, radiation areas above 20545, describing the results of the environmental and 5 mR/hr, such as near the activated primary system of a facility radiation surveys, the status of the facility, and an power plant, shouki be appropriately marked and should evaluation of the performance of security and surveillance not be accessible except by cutting of welded closures or measures. the disassembly and removal of substantial structures and/or shickling material. Means such as a (2) An abnormal occurrence report to the Regtilatory remote-readout irgrusion alarm system should be provided Operations Regional Office by telephone within 24 hours to indicate to designated personnel when a physical barrier of discovery of an abnormal occurrence. The abnormal is penetrated. Security personnel that provide access occurrence will also be reported in the annual report control to the facility may be used instead of the physical described in the preceding item. barriers and the intrusion alarm systems, h. Records or logs relative to the following items
- b. 'Ihe physical barriers to unauthorized entrance into shoukt be kept and reained until the license is terminated, the facility, e.g., fences, buildings, welded doors, and after which they must be stored with other plant records:
access openings, shoukt be inspected at least quarterly to assure that these barriers have not deteriorated and that (1) Environmental surveys, locks and locking appantus are intact. (2) Facility radiation surveys,
- c. A facility radiation t.urvey should be performed at least quarterly to verify that no radioactive material is (3) Inspections of the physical barriers, and escaping or being transported through the containment Note: Section electronically reproduced from photocopy.
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(4) Abnormal occurrences, premises, equipment, scrip, aral radioactive contan inants and the nature, extent, and degree of residual surface Contamination.
- 4. DECONTAMINATION FOR RELEASE FOR UNRESTRICTED USE (2) A detailed halth and safety analysis indicating that the residual amounts of materials on surface areas, If it is desired to terminate a license arxl to eliminate together with other considerations such as the prospective any further surveillance requirements, the facility should use of the premises, equipment, or scrap, are unlikely to be sufficiently decontanunated to prevent risk to the public result in an unreasonable risk to the health and safety of health and safety.
After the decontamination is the public. satisfactorily accomplished and the site inspected by the Commission, the Conunission may authorize the license Prior to release of the premises for unrestricted e. to be termmated armi the facility abarxioned or released for use, the licensee shouki make a comprehensive radiation unrestricted use. The licensee shouki perform the survey establishing that contamination is within the limits l decontammation using the following guidelines: specified in Table 1. A survey report should be filed with the Director of Licensing, U.S. Atomic Emergy a. The licensee should make a reasonable effort to Commission, Washington, D.C. 20545, with a copy to the eliminate residual contamination. Director of the Regulatory Operations regional Office havingjurialiction. The report should be filed at least 30 b. No covering should be applied to radioactive days prior to the planned date of abandonment. The surfaces of equipment of structures by paint, plating, or rurvey report should: other covering material until it is known that contunination levels (determined by a survey and (1) Identify the premises; documented) are below the limits specified in Table 1. In addition, a reasonable effort should be made (and (2) Show that reasonable effort has been made to documented) to further minimize contamination prior to reduce residual contamination to as low as practicable any such covering. levels;
- c. The radioactivity of the interior surfaces of pipes, (3) Describe the scope of the survey arx! the general
] drain lines, or ductwork should be determined by raaking procedures followed; and 1 measurements at all traps and other appropriate access l points, provided contamination at these locations is likely (4) State the fuxling of the survey in units specified in to be representative of contammation on the interior of the Table 1. pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated After review of the report, the Commission may I but are of such size, construction, or location as to make inspect the facilities to confirm the survey prior to the surface inaccessible for purposes of measurement granting approval for abandonment. should be assumed to be contaminated in excess of the l i permissible radiation limits.
- 5. REACTOR RETIREMENT PROCEDURES i
- d. Upon request, the Commission may authorize a As indicated in Regulatory Position C.2, several licensee to relinquish possession or control of premises, aherrur2ives are acceptable for reactor facility retirement.
equipment, or scrap having surfaces contaminated in If minor disassembly or "mothballing" is planned, this excess of the limits specified. This may include, but is could be done by the existing operating and maintenar,ce not limited to, special circumstances such as the transfer procedures under the license in effect. Any plasmed of premises to another licensed organization that will actions involving an unreviewed safety question or a contiraic to work with radioactive materials. Requests for change in the technical specifications should tw reviewed such authorization should provide: and approved in accordance with the requirements of 10 CFR 5 50.59. (1) Detailed, specific information describing the I Note; Section electronically reproduced from photocopy, C-4
If major structural changes to radioactive comporents of the facility are planned, such as renoval of tim prmure vessel or major components of the primary sydem, a dismantlement plan including the information required by i 50.82 shouki be submitted to the Commission. A dismantlement plan shoukt be submitted for all the ahernatives of Regulatory Position C.2 except mothbalhng However, minor disassembly activities nay still be perfonned in the absence of such a plan, provided they am permitted by existing operating and maintenance procedures. A dismantlement plan shoukt include the following:
- a. A description of the ultimate status of the facility
- b. A description of the dismantling activities and tlw precautions to be taken, c.
A safety analysis of tlw dismantling activities including any effluents which may be released. d. A safety analysis of the facility in its ultimate status. Upon satisfactory review and approval of the dismantling plan, a dismantling order is issued by the Commission in accordance with 6 50.82. When dismantling is completed and the Commission has been notified by letter, the appropriate Regulatory Operations Regional Office inspects the facility and verifies - completion in accordance with ti e dismantlement plan. If residual radiation levels do not exceed the values in Table 1, the Commission may terminate the license. If possession-only-license under which the dismantling activities have been conducted or, as an alterna'ive, may make application to the State (if an Agreement State) for a byproduct materials license. l 1 ' Note: Section electronically reproduced f rom photocopy. C-5
TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS I 6d Nuclide' Average Maximum 6d 6 Removable ' knat, U-235, U-238, and 2 2 2 isoci;t:d decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm ransuranics, Ra-226, Ra-228, b230, Th-228, Pa-231, 2 2 2 e-227, I-125, I-129 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm bnat, Th-232, Sr-90, 2 2 2 0-223, Ra-224, U-232, I-126,- 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm >l31, I-133 GBa-gamma emitters (nuclides (th-decay modes other than j Bha emission or spontaneous 2 2 2 Ifon) except Sr-90 and others 5,000 dpm p-y/100 cm 15,000 dpm p-y/100 cm 1,000 dpm p-y/100 cm sted above. Rere surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-6 beta-gamma-emitting nuclides should apply independently. 3 used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined y correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric-mors associated with the instrumentation.- easur:ments of average contaminant should not be averaged over more than 1 square meter. For objects ofless c# ace area, the average should be derived for each such object. 2 te maximum contamination level applies to an area of not more than 100 cm, 2 te amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area 5th dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material a the. wipe with an appropriate instrument of known efficiency, When removable contamination on objects ofless face area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. C-6 hu. p % w e m s.m2 can.i-w.s
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